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Actinides in the periodic table
Hydrogen Helium
Lithium Beryllium Boron Carbon Nitrogen Oxygen Fluorine Neon
Sodium Magnesium Aluminium Silicon Phosphorus Sulfur Chlorine Argon
Potassium Calcium Scandium Titanium Vanadium Chromium Manganese Iron Cobalt Nickel Copper Zinc Gallium Germanium Arsenic Selenium Bromine Krypton
Rubidium Strontium Yttrium Zirconium Niobium Molybdenum Technetium Ruthenium Rhodium Palladium Silver Cadmium Indium Tin Antimony Tellurium Iodine Xenon
Caesium Barium Lanthanum Cerium Praseodymium Neodymium Promethium Samarium Europium Gadolinium Terbium Dysprosium Holmium Erbium Thulium Ytterbium Lutetium Hafnium Tantalum Tungsten Rhenium Osmium Iridium Platinum Gold Mercury (element) Thallium Lead Bismuth Polonium Astatine Radon
Francium Radium Actinium Thorium Protactinium Uranium Neptunium Plutonium Americium Curium Berkelium Californium Einsteinium Fermium Mendelevium Nobelium Lawrencium Rutherfordium Dubnium Seaborgium Bohrium Hassium Meitnerium Darmstadtium Roentgenium Copernicium Nihonium Flerovium Moscovium Livermorium Tennessine Oganesson

The actinide (/ˈæktɪnd/) or actinoid (/ˈæktɪnɔɪd/) series encompasses at least the 14 metallic chemical elements in the 5f series, with atomic numbers from 89 to 102, actinium through nobelium. Number 103, lawrencium, is also generally included despite being part of the 6d transition series. The actinide series derives its name from the first element in the series, actinium. The informal chemical symbol An is used in general discussions of actinide chemistry to refer to any actinide.[1][2][3]

The 1985 IUPAC Red Book recommends that actinoid be used rather than actinide, since the suffix -ide normally indicates a negative ion. However, owing to widespread current use, actinide is still allowed.

Actinium through nobelium are f-block elements, while lawrencium is a d-block element[4][5] and a transition metal.[6] The series mostly corresponds to the filling of the 5f electron shell, although as isolated atoms in the ground state many have anomalous configurations involving the filling of the 6d shell due to interelectronic repulsion. In comparison with the lanthanides, also mostly f-block elements, the actinides show much more variable valence. They all have very large atomic and ionic radii and exhibit an unusually large range of physical properties. While actinium and the late actinides (from curium onwards) behave similarly to the lanthanides, the elements thorium, protactinium, and uranium are much more similar to transition metals in their chemistry, with neptunium, plutonium, and americium occupying an intermediate position.

All actinides are radioactive and release energy upon radioactive decay; naturally occurring uranium and thorium, and synthetically produced plutonium are the most abundant actinides on Earth. These have been used in nuclear reactors, and uranium and plutonium are critical elements of nuclear weapons. Uranium and thorium also have diverse current or historical uses, and americium is used in the ionization chambers of most modern smoke detectors.

Due to their long half-lives, only thorium and uranium are found on Earth and astrophysically in substantial quantities. The radioactive decay of uranium produces transient amounts of actinium and protactinium, and atoms of neptunium and plutonium are occasionally produced from transmutation reactions in uranium ores. The other actinides are purely synthetic elements.[1][7] Nuclear weapons tests have released at least six actinides heavier than plutonium into the environment; analysis of debris from the 1952 first test of a hydrogen bomb showed the presence of americium, curium, berkelium, californium, and the discovery of einsteinium and fermium.[8]

In presentations of the periodic table, the f-block elements are customarily shown as two additional rows below the main body of the table.[1] This convention is entirely a matter of aesthetics and formatting practicality; a rarely used wide-formatted periodic table inserts the 4f and 5f series in their proper places, as parts of the table's sixth and seventh rows (periods).

Discovery, isolation and synthesis

[edit]
Synthesis of transuranium elements[9][notes 1]
Element Year Method
Neptunium 1940 Bombarding 238U with neutrons
Plutonium 1941 Bombarding 238U with deuterons
Americium 1944 Bombarding 239Pu with neutrons
Curium 1944 Bombarding 239Pu with α-particles
Berkelium 1949 Bombarding 241Am with α-particles
Californium 1950 Bombarding 242Cm with α-particles
Einsteinium 1952 As a product of nuclear explosion
Fermium 1952 As a product of nuclear explosion
Mendelevium 1955 Bombarding 253Es with α-particles
Nobelium 1965 Bombarding 243Am with 15N
or 238U with 22Ne
Lawrencium 1961
–1971
Bombarding 252Cf with 10B or 11B
and of 243Am with 18O

Like the lanthanides, the actinides form a family of elements with similar properties. Within the actinides, there are two overlapping groups: transuranium elements, which follow uranium in the periodic table; and transplutonium elements, which follow plutonium. Compared to the lanthanides, which (except for promethium) are found in nature in appreciable quantities, most actinides are rare. Most do not occur in nature, and of those that do, only thorium and uranium do so in more than trace quantities. The most abundant or easily synthesized actinides are uranium and thorium, followed by plutonium, americium, actinium, protactinium, neptunium, and curium.[10]

The existence of transuranium elements was suggested in 1934 by Enrico Fermi, based on his experiments.[11][12] However, even though four actinides were known by that time, it was not yet understood that they formed a family similar to lanthanides. The prevailing view that dominated early research into transuranics was that they were regular elements in the 7th period, with thorium, protactinium and uranium corresponding to 6th-period hafnium, tantalum and tungsten, respectively. Synthesis of transuranics gradually undermined this point of view. By 1944, an observation that curium failed to exhibit oxidation states above 4 (whereas its supposed 6th period homolog, platinum, can reach oxidation state of 6) prompted Glenn Seaborg to formulate an "actinide hypothesis". Studies of known actinides and discoveries of further transuranic elements provided more data in support of this position, but the phrase "actinide hypothesis" (the implication being that a "hypothesis" is something that has not been decisively proven) remained in active use by scientists through the late 1950s.[13][14]

At present, there are two major methods of producing isotopes of transplutonium elements: (1) irradiation of the lighter elements with neutrons; (2) irradiation with accelerated charged particles. The first method is more important for applications, as only neutron irradiation using nuclear reactors allows the production of sizeable amounts of synthetic actinides; however, it is limited to relatively light elements. The advantage of the second method is that elements heavier than plutonium, as well as neutron-deficient isotopes, can be obtained, which are not formed during neutron irradiation.[15]

In 1962–1966, there were attempts in the United States to produce transplutonium isotopes using a series of six underground nuclear explosions. Small samples of rock were extracted from the blast area immediately after the test to study the explosion products, but no isotopes with mass number greater than 257 could be detected, despite predictions that such isotopes would have relatively long half-lives of α-decay. This non-observation was attributed to spontaneous fission owing to the large speed of the products and to other decay channels, such as neutron emission and nuclear fission.[16]

From actinium to uranium

[edit]
Enrico Fermi suggested the existence of transuranium elements in 1934.

Uranium and thorium were the first actinides discovered. Uranium was identified in 1789 by the German chemist Martin Heinrich Klaproth in pitchblende ore. He named it after the planet Uranus,[7] which had been discovered eight years earlier. Klaproth was able to precipitate a yellow compound (likely sodium diuranate) by dissolving pitchblende in nitric acid and neutralizing the solution with sodium hydroxide. He then reduced the obtained yellow powder with charcoal, and extracted a black substance that he mistook for metal.[17] Sixty years later, the French scientist Eugène-Melchior Péligot identified it as uranium oxide. He also isolated the first sample of uranium metal by heating uranium tetrachloride with metallic potassium.[18] The atomic mass of uranium was then calculated as 120, but Dmitri Mendeleev in 1872 corrected it to 240 using his periodicity laws. This value was confirmed experimentally in 1882 by K. Zimmerman.[19][20]

Thorium oxide was discovered by Friedrich Wöhler in the mineral thorianite, which was found in Norway (1827).[21] Jöns Jacob Berzelius characterized this material in more detail in 1828. By reduction of thorium tetrachloride with potassium, he isolated the metal and named it thorium after the Norse god of thunder and lightning Thor.[22][23] The same isolation method was later used by Péligot for uranium.[7]

Actinium was discovered in 1899 by André-Louis Debierne, an assistant of Marie Curie, in the pitchblende waste left after removal of radium and polonium. He described the substance (in 1899) as similar to titanium[24] and (in 1900) as similar to thorium.[25] The discovery of actinium by Debierne was however questioned in 1971[26] and 2000,[27] arguing that Debierne's publications in 1904 contradicted his earlier work of 1899–1900. This view instead credits the 1902 work of Friedrich Oskar Giesel, who discovered a radioactive element named emanium that behaved similarly to lanthanum. The name actinium comes from the Ancient Greek: ακτίς, ακτίνος (aktis, aktinos), meaning beam or ray. This metal was discovered not by its own radiation but by the radiation of the daughter products.[28][29] Owing to the close similarity of actinium and lanthanum and low abundance, pure actinium could only be produced in 1950. The term actinide was probably introduced by Victor Goldschmidt in 1937.[30][31]

Protactinium was possibly isolated in 1900 by William Crookes.[32] It was first identified in 1913, when Kasimir Fajans and Oswald Helmuth Göhring encountered the short-lived isotope 234mPa (half-life 1.17 minutes) during their studies of the 238U decay chain. They named the new element brevium (from Latin brevis meaning brief);[33][34] the name was changed to protoactinium (from Greek πρῶτος + ἀκτίς meaning "first beam element") in 1918 when two groups of scientists, led by the Austrian Lise Meitner and Otto Hahn of Germany and Frederick Soddy and John Arnold Cranston of Great Britain, independently discovered the much longer-lived 231Pa. The name was shortened to protactinium in 1949. This element was little characterized until 1960, when Alfred Maddock and his co-workers in the U.K. isolated 130 grams of protactinium from 60 tonnes of waste left after extraction of uranium from its ore.[35]

Neptunium and above

[edit]

Neptunium (named for the planet Neptune, the next planet out from Uranus, after which uranium was named) was discovered by Edwin McMillan and Philip H. Abelson in 1940 in Berkeley, California.[36] They produced the 239Np isotope (half-life 2.4 days) by bombarding uranium with slow neutrons.[35] It was the first transuranium element produced synthetically.[37]

Glenn T. Seaborg and his group at the University of California at Berkeley synthesized Pu, Am, Cm, Bk, Cf, Es, Fm, Md, No and element 106, which was later named seaborgium in his honor while he was still living. They also synthesized more than a hundred actinide isotopes.

Transuranium elements do not occur in sizeable quantities in nature and are commonly synthesized via nuclear reactions conducted with nuclear reactors. For example, under irradiation with reactor neutrons, uranium-238 partially converts to plutonium-239:

This synthesis reaction was used by Fermi and his collaborators in their design of the reactors located at the Hanford Site, which produced significant amounts of plutonium-239 for the nuclear weapons of the Manhattan Project and the United States' post-war nuclear arsenal.[38]

Actinides with the highest mass numbers are synthesized by bombarding uranium, plutonium, curium and californium with ions of nitrogen, oxygen, carbon, neon or boron in a particle accelerator. Thus nobelium was produced by bombarding uranium-238 with neon-22 as

.

The first isotopes of transplutonium elements, americium-241 and curium-242, were synthesized in 1944 by Glenn T. Seaborg, Ralph A. James and Albert Ghiorso.[39] Curium-242 was obtained by bombarding plutonium-239 with 32-MeV α-particles:

.

The americium-241 and curium-242 isotopes also were produced by irradiating plutonium in a nuclear reactor. The latter element was named after Marie Curie and her husband Pierre who are noted for discovering radium and for their work in radioactivity.[40]

Bombarding curium-242 with α-particles resulted in an isotope of californium 245Cf in 1950, and a similar procedure yielded berkelium-243 from americium-241 in 1949.[41] The new elements were named after Berkeley, California, by analogy with its lanthanide homologue terbium, which was named after the village of Ytterby in Sweden.[42]

In 1945, B. B. Cunningham obtained the first bulk chemical compound of a transplutonium element, namely americium hydroxide.[43] Over the few years, milligram quantities of americium and microgram amounts of curium were accumulated that allowed production of isotopes of berkelium[44][45] and californium.[46][47][48] Sizeable amounts of these elements were produced in 1958,[49] and the first californium compound (0.3 μg of CfOCl) was obtained in 1960 by B. B. Cunningham and J. C. Wallmann.[50]

Einsteinium and fermium were identified in 1952–1953 in the fallout from the "Ivy Mike" nuclear test (1 November 1952), the first successful test of a hydrogen bomb. Instantaneous exposure of uranium-238 to a large neutron flux resulting from the explosion produced heavy isotopes of uranium, which underwent a series of beta decays to nuclides such as einsteinium-253 and fermium-255. The discovery of the new elements and the new data on neutron capture were initially kept secret on the orders of the US military until 1955 due to Cold War tensions.[8][51] Nevertheless, the Berkeley team were able to prepare einsteinium and fermium by civilian means, through the neutron bombardment of plutonium-239, and published this work in 1954 with the disclaimer that it was not the first studies that had been carried out on those elements.[52][53] The "Ivy Mike" studies were declassified and published in 1955.[51] The first significant (submicrogram) amounts of einsteinium were produced in 1961 by Cunningham and colleagues, but this has not been done for fermium yet.[54]

The first isotope of mendelevium, 256Md (half-life 87 min), was synthesized by Albert Ghiorso, Glenn T. Seaborg, Gregory Robert Choppin, Bernard G. Harvey and Stanley Gerald Thompson when they bombarded an 253Es target with alpha particles in the 60-inch cyclotron of Berkeley Radiation Laboratory; this was the first isotope of any element to be synthesized one atom at a time.[55]

There were several attempts to obtain isotopes of nobelium by Swedish (1957) and American (1958) groups, but the first reliable result was the synthesis of 256No by the Russian group of Georgy Flyorov in 1965, as acknowledged by the IUPAC in 1992. In their experiments, Flyorov et al. bombarded uranium-238 with neon-22.[9]

In 1961, Ghiorso et al. obtained the first isotope of lawrencium by irradiating californium (mostly californium-252) with boron-10 and boron-11 ions.[9] The mass number of this isotope was not clearly established (possibly 258 or 259) at the time. In 1965, 256Lr was synthesized by Flyorov et al. from 243Am and 18O. Thus IUPAC recognized the nuclear physics teams at Dubna and Berkeley as the co-discoverers of lawrencium.

Isotopes

[edit]
Actinides have 89–103 protons and usually 117–159 neutrons.

Thirty-four isotopes of actinium and eight excited isomeric states of some of its nuclides are known, ranging in mass number from 203 to 236.[56] Three isotopes, 225Ac, 227Ac and 228Ac, were found in nature and the others were produced in the laboratory; only the three natural isotopes are used in applications. Actinium-225 is a member of the radioactive neptunium series;[59] it was first discovered in 1947 as a decay product of uranium-233 and it is an α-emitter with a half-life of 10 days. Actinium-225 is less available than actinium-228, but is more promising in radiotracer applications.[29] Actinium-227 (half-life 21.77 years) occurs in all uranium ores, but in small quantities. One gram of uranium (in radioactive equilibrium) contains only 2×10−10 gram of 227Ac.[29][56] Actinium-228 is a member of the radioactive thorium series formed by the decay of 228Ra;[59] it is a β emitter with a half-life of 6.15 hours. In one tonne of thorium there is 5×10−8 gram of 228Ac. It was discovered by Otto Hahn in 1906.[29]

There are 32 known isotopes of thorium ranging in mass number from 207 to 238.[56] Of these, the longest-lived is 232Th, whose half-life of 1.4×1010 years means that it still exists in nature as a primordial nuclide. The next longest-lived is 230Th, an intermediate decay product of 238U with a half-life of 75,400 years. Several other thorium isotopes have half-lives over a day; all of these are also transient in the decay chains of 232Th, 235U, and 238U.

Twenty-nine isotopes of protactinium are known with mass numbers 211–239[56] as well as three excited isomeric states. Only 231Pa and 234Pa have been found in nature. All the isotopes have short lifetimes, except for protactinium-231 (half-life 32,760 years). The most important isotopes are 231Pa and 233Pa, which is an intermediate product in obtaining uranium-233 and is the most affordable among artificial isotopes of protactinium. 233Pa has convenient half-life and energy of γ-radiation, and thus was used in most studies of protactinium chemistry. Protactinium-233 is a β-emitter with a half-life of 26.97 days.[56][60]

There are 27 known isotopes of uranium, having mass numbers 215–242 (except 220).[57] Three of them, 234U, 235U and 238U, are present in appreciable quantities in nature. Among others, the most important is 233U, which is a final product of transformation of 232Th irradiated by slow neutrons. 233U has a much higher fission efficiency by low-energy (thermal) neutrons, compared e.g. with 235U. Most uranium chemistry studies were carried out on uranium-238 owing to its long half-life of 4.4×109 years.[61]

There are 25 isotopes of neptunium with mass numbers 219–244 (except 221);[57] they are all highly radioactive. The most popular among scientists are long-lived 237Np (t1/2 = 2.20×106 years) and short-lived 239Np, 238Np (t1/2 ~ 2 days).[37]

There are 21 known isotopes of plutonium, having mass numbers 227–247.[57] The most stable isotope of plutonium is 244Pu with half-life of 8.13×107 years.[56]

Eighteen isotopes of americium are known with mass numbers from 229 to 247 (with the exception of 231).[57] The most important are 241Am and 243Am, which are alpha-emitters and also emit soft, but intense γ-rays; both of them can be obtained in an isotopically pure form. Chemical properties of americium were first studied with 241Am, but later shifted to 243Am, which is almost 20 times less radioactive. The disadvantage of 243Am is production of the short-lived daughter isotope 239Np, which has to be considered in the data analysis.[62]

Among 19 isotopes of curium, ranging in mass number from 233 to 251,[57] the most accessible are 242Cm and 244Cm; they are α-emitters, but with much shorter lifetime than the americium isotopes. These isotopes emit almost no γ-radiation, but undergo spontaneous fission with the associated emission of neutrons. More long-lived isotopes of curium (245–248Cm, all α-emitters) are formed as a mixture during neutron irradiation of plutonium or americium. Upon short irradiation, this mixture is dominated by 246Cm, and then 248Cm begins to accumulate. Both of these isotopes, especially 248Cm, have a longer half-life (3.48×105 years) and are much more convenient for carrying out chemical research than 242Cm and 244Cm, but they also have a rather high rate of spontaneous fission. 247Cm has the longest lifetime among isotopes of curium (1.56×107 years), but is not formed in large quantities because of the strong fission induced by thermal neutrons.

Seventeen isotopes of berkelium have been identified with mass numbers 233, 234, 236, 238, and 240–252.[57] Only 249Bk is available in large quantities; it has a relatively short half-life of 330 days and emits mostly soft β-particles, which are inconvenient for detection. Its alpha radiation is rather weak (1.45×10−3% with respect to β-radiation), but is sometimes used to detect this isotope. 247Bk is an alpha-emitter with a long half-life of 1,380 years, but it is hard to obtain in appreciable quantities; it is not formed upon neutron irradiation of plutonium because β-decay of curium isotopes with mass number below 248 is not known.[62] (247Cm would actually release energy by β-decaying to 247Bk, but this has never been seen.)

The 20 isotopes of californium with mass numbers 237–256 are formed in nuclear reactors;[57] californium-253 is a β-emitter and the rest are α-emitters. The isotopes with even mass numbers (250Cf, 252Cf and 254Cf) have a high rate of spontaneous fission, especially 254Cf of which 99.7% decays by spontaneous fission. Californium-249 has a relatively long half-life (352 years), weak spontaneous fission and strong γ-emission that facilitates its identification. 249Cf is not formed in large quantities in a nuclear reactor because of the slow β-decay of the parent isotope 249Bk and a large cross section of interaction with neutrons, but it can be accumulated in the isotopically pure form as the β-decay product of (pre-selected) 249Bk. Californium produced by reactor-irradiation of plutonium mostly consists of 250Cf and 252Cf, the latter being predominant for large neutron fluences, and its study is hindered by the strong neutron radiation.[63]

Properties of some transplutonium isotope pairs[64]
Parent
isotope
t1/2 Daughter
isotope
t1/2 Time to establish
radioactive equilibrium
243Am 7370 years 239Np 2.35 days 47.3 days
245Cm 8265 years 241Pu 14 years 129 years
247Cm 1.64×107 years 243Pu 4.95 hours 7.2 days
254Es 270 days 250Bk 3.2 hours 35.2 hours
255Es 39.8 days 255Fm 22 hours 5 days
257Fm 79 days 253Cf 17.6 days 49 days

Among the 18 known isotopes of einsteinium with mass numbers from 240 to 257,[57] the most affordable is 253Es. It is an α-emitter with a half-life of 20.47 days, a relatively weak γ-emission and small spontaneous fission rate as compared with the isotopes of californium. Prolonged neutron irradiation also produces a long-lived isotope 254Es (t1/2 = 275.5 days).[63]

Twenty isotopes of fermium are known with mass numbers of 241–260. 254Fm, 255Fm and 256Fm are α-emitters with a short half-life (hours), which can be isolated in significant amounts. 257Fm (t1/2 = 100 days) can accumulate upon prolonged and strong irradiation. All these isotopes are characterized by high rates of spontaneous fission.[63][65]

Among the 17 known isotopes of mendelevium (mass numbers from 244 to 260),[57] the most studied is 256Md, which mainly decays through electron capture (α-radiation is ≈10%) with a half-life of 77 minutes. Another alpha emitter, 258Md, has a half-life of 53 days. Both these isotopes are produced from rare einsteinium (253Es and 255Es respectively), that therefore limits their availability.[56]

Long-lived isotopes of nobelium and isotopes of lawrencium (and of heavier elements) have relatively short half-lives. For nobelium, 13 isotopes are known, with mass numbers 249–260 and 262. The chemical properties of nobelium and lawrencium were studied with 255No (t1/2 = 3 min) and 256Lr (t1/2 = 35 s). The longest-lived nobelium isotope, 259No, has a half-life of approximately 1 hour.[56] Lawrencium has 14 known isotopes with mass numbers 251–262, 264, and 266. The most stable of them is 266Lr with a half-life of 11 hours.

Among all of these, the only isotopes that occur in sufficient quantities in nature to be detected in anything more than traces and have a measurable contribution to the atomic weights of the actinides are the primordial 232Th, 235U, and 238U, and three long-lived decay products of natural uranium, 230Th, 231Pa, and 234U. Natural thorium consists of 0.02(2)% 230Th and 99.98(2)% 232Th; natural protactinium consists of 100% 231Pa; and natural uranium consists of 0.0054(5)% 234U, 0.7204(6)% 235U, and 99.2742(10)% 238U.[66]

Formation in nuclear reactors

[edit]
Table of nuclides: Buildup of actinides in a nuclear reactor, including radioactive decay

The figure buildup of actinides is a table of nuclides with the number of neutrons on the horizontal axis (isotopes) and the number of protons on the vertical axis (elements). The red dot divides the nuclides in two groups, so the figure is more compact. Each nuclide is represented by a square with the mass number of the element and its half-life.[67] Naturally existing actinide isotopes (Th, U) are marked with a bold border, alpha emitters have a yellow colour, and beta emitters have a blue colour. Pink indicates electron capture (236Np), whereas white stands for a long-lasting metastable state (242Am).

The formation of actinide nuclides is primarily characterised by:[68]

  • Neutron capture reactions (n,γ), which are represented in the figure by a short right arrow.
  • The (n,2n) reactions and the less frequently occurring (γ,n) reactions are also taken into account, both of which are marked by a short left arrow.
  • Even more rarely and only triggered by fast neutrons, the (n,3n) reaction occurs, which is represented in the figure with one example, marked by a long left arrow.

In addition to these neutron- or gamma-induced nuclear reactions, the radioactive conversion of actinide nuclides also affects the nuclide inventory in a reactor. These decay types are marked in the figure by diagonal arrows. The beta-minus decay, marked with an arrow pointing up-left, plays a major role for the balance of the particle densities of the nuclides. Nuclides decaying by positron emission (beta-plus decay) or electron capture (ϵ) do not occur in a nuclear reactor except as products of knockout reactions; their decays are marked with arrows pointing down-right. Due to the long half-lives of the given nuclides, alpha decay plays almost no role in the formation and decay of the actinides in a power reactor, as the residence time of the nuclear fuel in the reactor core is rather short (a few years). Exceptions are the two relatively short-lived nuclides 242Cm (T1/2 = 163 d) and 236Pu (T1/2 = 2.9 y). Only for these two cases, the α decay is marked on the nuclide map by a long arrow pointing down-left. A few long-lived actinide isotopes, such as 244Pu and 250Cm, cannot be produced in reactors because neutron capture does not happen quickly enough to bypass the short-lived beta-decaying nuclides 243Pu and 249Cm; they can however be generated in nuclear explosions, which have much higher neutron fluxes.

Distribution in nature

[edit]
Unprocessed uranium ore

Thorium and uranium are the most abundant actinides in nature with the respective mass concentrations of 16 ppm and 4 ppm.[69] Uranium mostly occurs in the Earth's crust as a mixture of its oxides in the mineral uraninite, which is also called pitchblende because of its black color. There are several dozens of other uranium minerals such as carnotite (KUO2VO4·3H2O) and autunite (Ca(UO2)2(PO4)2·nH2O). The isotopic composition of natural uranium is 238U (relative abundance 99.2742%), 235U (0.7204%) and 234U (0.0054%); of these 238U has the largest half-life of 4.51×109 years.[70][71] The worldwide production of uranium in 2009 amounted to 50,572 tonnes, of which 27.3% was mined in Kazakhstan. Other important uranium mining countries are Canada (20.1%), Australia (15.7%), Namibia (9.1%), Russia (7.0%), and Niger (6.4%).[72]

Content of plutonium in uranium and thorium ores[73]
Ore Location Uranium
content, %
Mass ratio
239Pu/ore
Ratio
239Pu/U (×10−12)
Uraninite Canada 13.5 9.1×10−12 7.1
Uraninite Congo 38 4.8×10−12 12
Uraninite Colorado, US 50 3.8×10−12 7.7
Monazite Brazil 0.24 2.1×10−14 8.3
Monazite North Carolina, US 1.64 5.9×10−14 3.6
Fergusonite - 0.25 <1×10−14 <4
Carnotite - 10 <4×10−14 <0.4

The most abundant thorium minerals are thorianite (ThO2), thorite (ThSiO4) and monazite, ((Th,Ca,Ce)PO4). Most thorium minerals contain uranium and vice versa; and they all have significant fraction of lanthanides. Rich deposits of thorium minerals are located in the United States (440,000 tonnes), Australia and India (~300,000 tonnes each) and Canada (~100,000 tonnes).[74]

The abundance of actinium in the Earth's crust is only about 5×10−15%.[60] Actinium is mostly present in uranium-containing, but also in other minerals, though in much smaller quantities. The content of actinium in most natural objects corresponds to the isotopic equilibrium of parent isotope 235U, and it is not affected by the weak Ac migration.[29] Protactinium is more abundant (10−12%) in the Earth's crust than actinium. It was discovered in uranium ore in 1913 by Fajans and Göhring.[33] As actinium, the distribution of protactinium follows that of 235U.[60]

The half-life of the longest-lived isotope of neptunium, 237Np, is negligible compared to the age of the Earth. Thus neptunium is present in nature in negligible amounts produced as intermediate decay products of other isotopes.[37] Traces of plutonium in uranium minerals were first found in 1942, and the more systematic results on 239Pu are summarized in the table (no other plutonium isotopes could be detected in those samples). The upper limit of abundance of the longest-living isotope of plutonium, 244Pu, is 3×10−20%. Plutonium could not be detected in samples of lunar soil. Owing to its scarcity in nature, most plutonium is produced synthetically.[73]

Extraction

[edit]
Monazite: a major thorium mineral

Owing to the low abundance of actinides, their extraction is a complex, multistep process. Fluorides of actinides are usually used because they are insoluble in water and can be easily separated with redox reactions. Fluorides are reduced with calcium, magnesium or barium:[75]

Among the actinides, thorium and uranium are the easiest to isolate. Thorium is extracted mostly from monazite: thorium pyrophosphate (ThP2O7) is reacted with nitric acid, and the produced thorium nitrate treated with tributyl phosphate. Rare-earth impurities are separated by increasing the pH in sulfate solution.[75]

In another extraction method, monazite is decomposed with a 45% aqueous solution of sodium hydroxide at 140 °C. Mixed metal hydroxides are extracted first, filtered at 80 °C, washed with water and dissolved with concentrated hydrochloric acid. Next, the acidic solution is neutralized with hydroxides to pH = 5.8 that results in precipitation of thorium hydroxide (Th(OH)4) contaminated with ~3% of rare-earth hydroxides; the rest of rare-earth hydroxides remains in solution. Thorium hydroxide is dissolved in an inorganic acid and then purified from the rare earth elements. An efficient method is the dissolution of thorium hydroxide in nitric acid, because the resulting solution can be purified by extraction with organic solvents:[75]

Separation of uranium and plutonium from spent nuclear fuel using the PUREX process[76]
Th(OH)4 + 4 HNO3 → Th(NO3)4 + 4 H2O

Metallic thorium is separated from the anhydrous oxide, chloride or fluoride by reacting it with calcium in an inert atmosphere:[77]

ThO2 + 2 Ca → 2 CaO + Th

Sometimes thorium is extracted by electrolysis of a fluoride in a mixture of sodium and potassium chloride at 700–800 °C in a graphite crucible. Highly pure thorium can be extracted from its iodide with the crystal bar process.[78]

Uranium is extracted from its ores in various ways. In one method, the ore is burned and then reacted with nitric acid to convert uranium into a dissolved state. Treating the solution with a solution of tributyl phosphate (TBP) in kerosene transforms uranium into an organic form UO2(NO3)2(TBP)2. The insoluble impurities are filtered and the uranium is extracted by reaction with hydroxides as (NH4)2U2O7 or with hydrogen peroxide as UO4·2H2O.[75]

When the uranium ore is rich in such minerals as dolomite, magnesite, etc., those minerals consume much acid. In this case, the carbonate method is used for uranium extraction. Its main component is an aqueous solution of sodium carbonate, which converts uranium into a complex [UO2(CO3)3]4−, which is stable in aqueous solutions at low concentrations of hydroxide ions. The advantages of the sodium carbonate method are that the chemicals have low corrosivity (compared to nitrates) and that most non-uranium metals precipitate from the solution. The disadvantage is that tetravalent uranium compounds precipitate as well. Therefore, the uranium ore is treated with sodium carbonate at elevated temperature and under oxygen pressure:

2 UO2 + O2 + 6 CO2−
3
→ 2 [UO2(CO3)3]4−

This equation suggests that the best solvent for the uranyl carbonate processing is a mixture of carbonate with bicarbonate. At high pH, this results in precipitation of diuranate, which is treated with hydrogen in the presence of nickel yielding an insoluble uranium tetracarbonate.[75]

Another separation method uses polymeric resins as a polyelectrolyte. Ion exchange processes in the resins result in separation of uranium. Uranium from resins is washed with a solution of ammonium nitrate or nitric acid that yields uranyl nitrate, UO2(NO3)2·6H2O. When heated, it turns into UO3, which is converted to UO2 with hydrogen:

UO3 + H2 → UO2 + H2O

Reacting uranium dioxide with hydrofluoric acid changes it to uranium tetrafluoride, which yields uranium metal upon reaction with magnesium metal:[77]

4 HF + UO2 → UF4 + 2 H2O

To extract plutonium, neutron-irradiated uranium is dissolved in nitric acid, and a reducing agent (FeSO4, or H2O2) is added to the resulting solution. This addition changes the oxidation state of plutonium from +6 to +4, while uranium remains in the form of uranyl nitrate (UO2(NO3)2). The solution is treated with a reducing agent and neutralized with ammonium carbonate to pH = 8 that results in precipitation of Pu4+ compounds.[75]

In another method, Pu4+ and UO2+
2
are first extracted with tributyl phosphate, then reacted with hydrazine washing out the recovered plutonium.[75]

The major difficulty in separation of actinium is the similarity of its properties with those of lanthanum. Thus actinium is either synthesized in nuclear reactions from isotopes of radium or separated using ion-exchange procedures.[29]

Properties

[edit]

Actinides have similar properties to lanthanides. Just as the 4f electron shells are filled in the lanthanides, the 5f electron shells are filled in the actinides. Because the 5f, 6d, 7s, and 7p shells are close in energy, many irregular configurations arise; thus, in gas-phase atoms, just as the first 4f electron only appears in cerium, so the first 5f electron appears even later, in protactinium. However, just as lanthanum is the first element to use the 4f shell in compounds,[79] so actinium is the first element to use the 5f shell in compounds.[80] The f-shells complete their filling together, at ytterbium and nobelium.[81] The first experimental evidence for the filling of the 5f shell in actinides was obtained by McMillan and Abelson in 1940.[82] As in lanthanides (see lanthanide contraction), the ionic radius of actinides monotonically decreases with atomic number (see also actinoid contraction).[83]

The shift of electron configurations in the gas phase does not always match the chemical behaviour. For example, the early-transition-metal-like prominence of the highest oxidation state, corresponding to removal of all valence electrons, extends up to uranium even though the 5f shells begin filling before that. On the other hand, electron configurations resembling the lanthanide congeners already begin at plutonium, even though lanthanide-like behaviour does not become dominant until the second half of the series begins at curium. The elements between uranium and curium form a transition between these two kinds of behaviour, where higher oxidation states continue to exist, but lose stability with respect to the +3 state.[81] The +2 state becomes more important near the end of the series, and is the most stable oxidation state for nobelium, the last 5f element.[81] Oxidation states rise again only after nobelium, showing that a new series of 6d transition metals has begun: lawrencium shows only the +3 oxidation state, and rutherfordium only the +4 state, making them respectively congeners of lutetium and hafnium in the 5d row.[81]

Properties of actinides (the mass of the most long-lived isotope is in square brackets)[71][84]
Element Ac Th Pa U Np Pu Am Cm Bk Cf Es Fm Md No Lr
Core charge (Z) 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103
Atomic mass [227] 232.0377(4) 231.03588(2) 238.02891(3) [237] [244] [243] [247] [247] [251] [252] [257] [258] [259] [266]
Number of natural isotopes[85] 3 8 3 8 3 4 0 0 0 0 0 0 0 0 0
Natural isotopes[85][86] 225, 227, 228 227–234 231, 233, 234 233–240 237, 239, 240 238–240, 244
Natural quantity isotopes 230, 232 231 234, 235, 238
Longest-lived isotope 227 232 231 238 237 244 243 247 247 251 252 257 258 259 266
Half-life of the longest-lived isotope 21.8 years 14 billion years (1.4×1010 years) 32,500 years 4.47 billion years (4.47×109 years) 2.14 million years (2,140,000 years) 80.8 million years (80,800,000 years) 7,370 years 15.6 million years (15,600,000 years) 1,380 years 900 years 1.29 years 100.5 d 52 d 58 min 11 h
Most common isotope 227 232 231 238 237 239 241 244 249 252 253 255 256 255 260
Half-life of the most common isotope 21.8 years 14 billion years (1.4×1010 years) 32,500 years 4.47 billion years (4.47×109 years) 2.14 million years (2,140,000 years) 24,100 years 433 years 18.1 years 320 d 2.64 years 20.47 d 20.07 h 78 min 3.1 min 2.7 min
Electronic configuration in
the ground state (gas phase)
6d17s2 6d27s2 5f26d17s2 5f36d17s2 5f46d17s2 5f67s2 5f77s2 5f76d17s2 5f97s2 5f107s2 5f117s2 5f127s2 5f137s2 5f147s2 5f147s27p1
Oxidation states 2, 3 2, 3, 4 2, 3, 4, 5 2, 3, 4, 5, 6 3, 4, 5, 6, 7 3, 4, 5, 6, 7 2, 3, 4, 5, 6, 7 2, 3, 4, 6 2, 3, 4 2, 3, 4 2, 3, 4 2, 3 2, 3 2, 3 3
Metallic radius (nm) 0.203 0.180 0.162 0.153 0.150 0.162 0.173 0.174 0.170 0.186 0.186 ? 0.198 ? 0.194 ? 0.197 ? 0.171
Ionic radius (nm):
An4+
An3+


0.126

0.114

0.104
0.118

0.103
0.118

0.101
0.116

0.100
0.115

0.099
0.114

0.099
0.112

0.097
0.110

0.096
0.109

0.085
0.098

0.084
0.091

0.084
0.090

0.084
0.095

0.083
0.088
Temperature (°C):
melting
boiling
1050
3198
1842
4788
1568
? 4027
1132.2
4131
639
? 4174
639.4
3228
1176
? 2607
1340
3110
986
2627

900
? 1470
860
? 996
1530
830
830
1630
Density, g/cm3 10.07 11.78 15.37 19.06 20.45 19.84 11.7 13.51 14.78 15.1 8.84 ? 9.7 ? 10.3 ? 9.9 ? 14.4
Standard electrode potential (V):
E° (An4+/An0)
E° (An3+/An0)

−2.13

−1.83

−1.47

−1.38
−1.66

−1.30
−1.79

−1.25
−2.00

−0.90
−2.07

−0.75
−2.06

−0.55
−1.96

−0.59
−1.97

−0.36
−1.98

−0.29
−1.96


−1.74


−1.20


−2.10
Color:
[M(H2O)n]4+
[M(H2O)n]3+


Colorless

Colorless
Blue

Yellow
Dark blue

Green
Purple

Yellow-green
Purple

Brown
Violet

Red
Rose

Yellow
Colorless

Beige
Yellow-green

Green
Green


Pink








Approximate colors of actinide ions in aqueous solution
Colors for the actinides 100–103 are unknown as sufficient quantities have not yet been synthesized. The colour of CmO2+2 was likewise not recorded.

[87][88]

Actinide (Z) 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103
Oxidation state
+2 Fm2+ Md2+ No2+
+3 Ac3+ Th3+ Pa3+ U3+ Np3+ Pu3+ Am3+ Cm3+ Bk3+ Cf3+ Es3+ Fm3+ Md3+ No3+ Lr3+
+4 Th4+ Pa4+ U4+ Np4+ Pu4+ Am4+ Cm4+ Bk4+ Cf4+
+5 PaO+
2
UO+
2
NpO+
2
PuO+
2
AmO+
2
+6 UO2+
2
NpO2+
2
PuO2+
2
AmO2+
2
CmO2+
2
+7 NpO3+
2
PuO3+
2
AmO3−
5

Physical properties

[edit]
Major crystal structures of some actinides vs. temperature Metallic and ionic radii of actinides[84]
A pellet of 238PuO2 to be used in a radioisotope thermoelectric generator for either the Cassini or Galileo mission. The pellet produces 62 watts of heat and glows because of the heat generated by the radioactive decay (primarily α). Photo is taken after insulating the pellet under a graphite blanket for minutes and removing the blanket.
Californium

Actinides are typical metals. All of them are soft and have a silvery color (but tarnish in air),[89] relatively high density and plasticity. Some of them can be cut with a knife. Their electrical resistivity varies between 15 and 150 μΩ·cm.[84] The hardness of thorium is similar to that of soft steel, so heated pure thorium can be rolled in sheets and pulled into wire. Thorium is nearly half as dense as uranium and plutonium, but is harder than either of them. All actinides are radioactive, paramagnetic, and, with the exception of actinium, have several crystalline phases: plutonium has seven, and uranium, neptunium and californium three. The crystal structures of protactinium, uranium, neptunium and plutonium do not have clear analogs among the lanthanides and are more similar to those of the 3d-transition metals.[71]

All actinides are pyrophoric, especially when finely divided, that is, they spontaneously ignite upon reaction with air at room temperature.[89][90] The melting point of actinides does not have a clear dependence on the number of f-electrons. The unusually low melting point of neptunium and plutonium (~640 °C) is explained by hybridization of 5f and 6d orbitals and the formation of directional bonds in these metals.[71]

Chemical properties

[edit]

Like the lanthanides, all actinides are highly reactive with halogens and chalcogens; however, the actinides react more easily. Actinides, especially those with a small number of 5f-electrons, are prone to hybridization. This is explained by the similarity of the electron energies at the 5f, 7s and 6d shells. Most actinides exhibit a larger variety of valence states, and the most stable are +6 for uranium, +5 for protactinium and neptunium, +4 for thorium and plutonium and +3 for actinium and other actinides.[92]

Actinium is chemically similar to lanthanum, which is explained by their similar ionic radii and electronic structures. Like lanthanum, actinium almost always has an oxidation state of +3 in compounds, but it is less reactive and has more pronounced basic properties. Among other trivalent actinides Ac3+ is least acidic, i.e. has the weakest tendency to hydrolyze in aqueous solutions.[29][71]

Thorium is rather active chemically. Owing to lack of electrons on 6d and 5f orbitals, tetravalent thorium compounds are colorless. At pH < 3, solutions of thorium salts are dominated by the cations [Th(H2O)8]4+. The Th4+ ion is relatively large, and depending on the coordination number can have a radius between 0.95 and 1.14 Å. As a result, thorium salts have a weak tendency to hydrolyse. The distinctive ability of thorium salts is their high solubility both in water and polar organic solvents.[71]

Protactinium exhibits two valence states; the +5 is stable, and the +4 state easily oxidizes to protactinium(V). Thus tetravalent protactinium in solutions is obtained by the action of strong reducing agents in a hydrogen atmosphere. Tetravalent protactinium is chemically similar to uranium(IV) and thorium(IV). Fluorides, phosphates, hypophosphates, iodates and phenylarsonates of protactinium(IV) are insoluble in water and dilute acids. Protactinium forms soluble carbonates. The hydrolytic properties of pentavalent protactinium are close to those of tantalum(V) and niobium(V). The complex chemical behavior of protactinium is a consequence of the start of the filling of the 5f shell in this element.[60]

Uranium has a valence from 3 to 6, the last being most stable. In the hexavalent state, uranium is very similar to the group 6 elements. Many compounds of uranium(IV) and uranium(VI) are non-stoichiometric, i.e. have variable composition. For example, the actual chemical formula of uranium dioxide is UO2+x, where x varies between −0.4 and 0.32. Uranium(VI) compounds are weak oxidants. Most of them contain the linear "uranyl" group, UO2+
2
. Between 4 and 6 ligands can be accommodated in an equatorial plane perpendicular to the uranyl group. The uranyl group acts as a hard acid and forms stronger complexes with oxygen-donor ligands than with nitrogen-donor ligands. NpO2+
2
and PuO2+
2
are also the common form of Np and Pu in the +6 oxidation state. Uranium(IV) compounds exhibit reducing properties, e.g., they are easily oxidized by atmospheric oxygen. Uranium(III) is a very strong reducing agent. Owing to the presence of d-shell, uranium (as well as many other actinides) forms organometallic compounds, such as UIII(C5H5)3 and UIV(C5H5)4.[71][93]

Neptunium has valence states from 3 to 7, which can be simultaneously observed in solutions. The most stable state in solution is +5, but the valence +4 is preferred in solid neptunium compounds. Neptunium metal is very reactive. Ions of neptunium are prone to hydrolysis and formation of coordination compounds.[37]

Plutonium also exhibits valence states between 3 and 7 inclusive, and thus is chemically similar to neptunium and uranium. It is highly reactive, and quickly forms an oxide film in air. Plutonium reacts with hydrogen even at temperatures as low as 25–50 °C; it also easily forms halides and intermetallic compounds. Hydrolysis reactions of plutonium ions of different oxidation states are quite diverse. Plutonium(V) can enter polymerization reactions.[94][95]

The largest chemical diversity among actinides is observed in americium, which can have valence between 2 and 6. Divalent americium is obtained only in dry compounds and non-aqueous solutions (acetonitrile). Oxidation states +3, +5 and +6 are typical for aqueous solutions, but also in the solid state. Tetravalent americium forms stable solid compounds (dioxide, fluoride and hydroxide) as well as complexes in aqueous solutions. It was reported that in alkaline solution americium can be oxidized to the heptavalent state, but these data proved erroneous. The most stable valence of americium is 3 in aqueous solution and 3 or 4 in solid compounds.[96]

Valence 3 is dominant in all subsequent elements up to lawrencium (with the exception of nobelium). Curium can be tetravalent in solids (fluoride, dioxide). Berkelium, along with a valence of +3, also shows the valence of +4, more stable than that of curium; the valence 4 is observed in solid fluoride and dioxide. The stability of Bk4+ in aqueous solution is close to that of Ce4+.[97] Only valence 3 was observed for californium, einsteinium and fermium. The divalent state is proven for mendelevium and nobelium, and in nobelium it is more stable than the trivalent state. Lawrencium shows valence 3 both in solutions and solids.[96]

The redox potential increases from −0.32 V in uranium, through 0.34 V (Np) and 1.04 V (Pu) to 1.34 V in americium revealing the increasing reduction ability of the An4+ ion from americium to uranium. All actinides form AnH3 hydrides of black color with salt-like properties. Actinides also produce carbides with the general formula of AnC or AnC2 (U2C3 for uranium) as well as sulfides An2S3 and AnS2.[92]

Compounds

[edit]

Oxides and hydroxides

[edit]
Dioxides of some actinides
Chemical formula ThO2 PaO2 UO2 NpO2 PuO2 AmO2 CmO2 BkO2 CfO2
CAS Number 1314-20-1 12036-03-2 1344-57-6 12035-79-9 12059-95-9 12005-67-3 12016-67-0 12010-84-3 12015–10–0
Molar mass 264.04 263.035 270.03 269.047 276.063 275.06 270–284** 279.069 283.078
Melting point[103] 3390 °C 2865 °C 2547 °C 2400 °C 2175 °C
Crystal structure
An4+: __  /  O2−: __
Space group Fm3m
Coordination number An[8], O[4]
An – actinide
**Depending on the isotopes

Some actinides can exist in several oxide forms such as An2O3, AnO2, An2O5 and AnO3. For all actinides, oxides AnO3 are amphoteric and An2O3, AnO2 and An2O5 are basic, they easily react with water, forming bases:[92]

An2O3 + 3 H2O → 2 An(OH)3.

These bases are poorly soluble in water and by their activity are close to the hydroxides of rare-earth metals.[92] Np(OH)3 has not yet been synthesized, Pu(OH)3 has a blue color while Am(OH)3 is pink and Cm(OH)3 is colorless.[104] Bk(OH)3 and Cf(OH)3 are also known, as are tetravalent hydroxides for Np, Pu and Am and pentavalent for Np and Am.[104]

The strongest base is of actinium. All compounds of actinium are colorless, except for black actinium sulfide (Ac2S3).[92] Dioxides of tetravalent actinides crystallize in the cubic system, same as in calcium fluoride.

Thorium reacting with oxygen exclusively forms the dioxide:

Thorium dioxide is a refractory material with the highest melting point among any known oxide (3390 °C).[102] Adding 0.8–1% ThO2 to tungsten stabilizes its structure, so the doped filaments have better mechanical stability to vibrations. To dissolve ThO2 in acids, it is heated to 500–600 °C; heating above 600 °C produces a very resistant to acids and other reagents form of ThO2. Small addition of fluoride ions catalyses dissolution of thorium dioxide in acids.

Two protactinium oxides have been obtained: PaO2 (black) and Pa2O5 (white); the former is isomorphic with ThO2 and the latter is easier to obtain. Both oxides are basic, and Pa(OH)5 is a weak, poorly soluble base.[92]

Decomposition of certain salts of uranium, for example UO2(NO3)·6H2O in air at 400 °C, yields orange or yellow UO3.[102] This oxide is amphoteric and forms several hydroxides, the most stable being uranyl hydroxide UO2(OH)2. Reaction of uranium(VI) oxide with hydrogen results in uranium dioxide, which is similar in its properties with ThO2. This oxide is also basic and corresponds to the uranium hydroxide U(OH)4.[92]

Plutonium, neptunium and americium form two basic oxides: An2O3 and AnO2. Neptunium trioxide is unstable; thus, only Np3O8 could be obtained so far. However, the oxides of plutonium and neptunium with the chemical formula AnO2 and An2O3 are well characterized.[92]

Salts

[edit]
Trichlorides of some actinides[105]
Chemical formula AcCl3 UCl3 NpCl3 PuCl3 AmCl3 CmCl3 BkCl3 CfCl3
CAS-number 22986-54-5 10025-93-1 20737-06-8 13569-62-5 13464-46-5 13537-20-7 13536-46-4 13536–90–8
Molar mass 333.386 344.387 343.406 350.32 349.42 344–358** 353.428 357.438
Melting point 837 °C 800 °C 767 °C 715 °C 695 °C 603 °C 545 °C
Boiling point 1657 °C 1767 °C 850 °C
Crystal structure The crystal structure of uranium trichloride
An3+: __  /  Cl: __
Space group P63/m
Coordination number An*[9], Cl [3]
Lattice constants a = 762 pm
c = 455 pm
a = 745.2 pm
c = 432.8 pm
a = 739.4 pm
c = 424.3 pm
a = 738.2 pm
c = 421.4 pm
a = 726 pm
c = 414 pm
a = 738.2 pm
c = 412.7 pm
a = 738 pm
c = 409 pm
*An – actinide
**Depending on the isotopes
Einsteinium triiodide glowing in the dark

Actinides easily react with halogens forming salts with the formulas MX3 and MX4 (X = halogen). So the first berkelium compound, BkCl3, was synthesized in 1962 with an amount of 3 nanograms. Like the halogens of rare earth elements, actinide chlorides, bromides, and iodides are water-soluble, and fluorides are insoluble. Uranium easily yields a colorless hexafluoride, which sublimates at a temperature of 56.5 °C; because of its volatility, it is used in the separation of uranium isotopes with gas centrifuge or gaseous diffusion. Actinide hexafluorides have properties close to anhydrides. They are very sensitive to moisture and hydrolyze forming AnO2F2.[108] The pentachloride and black hexachloride of uranium were synthesized, but they are both unstable.[92]

Action of acids on actinides yields salts, and if the acids are non-oxidizing then the actinide in the salt is in low-valence state:

U + 2 H2SO4U(SO4)2 + 2 H2
2 Pu + 6 HCl → 2 PuCl3 + 3 H2

However, in these reactions the regenerating hydrogen can react with the metal, forming the corresponding hydride. Uranium reacts with acids and water much more easily than thorium.[92]

Actinide salts can also be obtained by dissolving the corresponding hydroxides in acids. Nitrates, chlorides, sulfates and perchlorates of actinides are water-soluble. When crystallizing from aqueous solutions, these salts form hydrates, such as Th(NO3)4·6H2O, Th(SO4)2·9H2O and Pu2(SO4)3·7H2O. Salts of high-valence actinides easily hydrolyze. So, colorless sulfate, chloride, perchlorate and nitrate of thorium transform into basic salts with formulas Th(OH)2SO4 and Th(OH)3NO3. The solubility and insolubility of trivalent and tetravalent actinides is like that of lanthanide salts. So phosphates, fluorides, oxalates, iodates and carbonates of actinides are weakly soluble in water; they precipitate as hydrates, such as ThF4·3H2O and Th(CrO4)2·3H2O.[92]

Actinides with oxidation state +6, except for the AnO22+-type cations, form [AnO4]2−, [An2O7]2− and other complex anions. For example, uranium, neptunium and plutonium form salts of the Na2UO4 (uranate) and (NH4)2U2O7 (diuranate) types. In comparison with lanthanides, actinides more easily form coordination compounds, and this ability increases with the actinide valence. Trivalent actinides do not form fluoride coordination compounds, whereas tetravalent thorium forms K2ThF6, KThF5, and even K5ThF9 complexes. Thorium also forms the corresponding sulfates (for example Na2SO4·Th(SO4)2·5H2O), nitrates and thiocyanates. Salts with the general formula An2Th(NO3)6·nH2O are of coordination nature, with the coordination number of thorium equal to 12. Even easier is to produce complex salts of pentavalent and hexavalent actinides. The most stable coordination compounds of actinides – tetravalent thorium and uranium – are obtained in reactions with diketones, e.g. acetylacetone.[92]

Applications

[edit]
Interior of a smoke detector containing americium-241.

While actinides have some established daily-life applications, such as in smoke detectors (americium)[109][110] and gas mantles (thorium),[77] they are mostly used in nuclear weapons and as fuel in nuclear reactors.[77] The last two areas exploit the property of actinides to release enormous energy in nuclear reactions, which under certain conditions may become self-sustaining chain reactions.

Self-illumination of a nuclear reactor by Cherenkov radiation.

The most important isotope for nuclear power applications is uranium-235. It is used in the thermal reactor, and its concentration in natural uranium does not exceed 0.72%. This isotope strongly absorbs thermal neutrons releasing much energy. One fission act of 1 gram of 235U converts into about 1 MW·day. Of importance, is that 235
92
U
emits more neutrons than it absorbs;[111] upon reaching the critical mass, 235
92
U
enters into a self-sustaining chain reaction.[71] Typically, uranium nucleus is divided into two fragments with the release of 2–3 neutrons, for example:

235
92
U
+ 1
0
n
115
45
Rh
+ 118
47
Ag
+ 31
0
n

Other promising actinide isotopes for nuclear power are thorium-232 and its product from the thorium fuel cycle, uranium-233.

Nuclear reactor[71][112][113]
The core of most Generation II nuclear reactors contains a set of hollow metal rods, usually made of zirconium alloys, filled with solid nuclear fuel pellets – mostly oxide, carbide, nitride or monosulfide of uranium, plutonium or thorium, or their mixture (the so-called MOX fuel). The most common fuel is oxide of uranium-235.
Nuclear reactor scheme
Nuclear reactor scheme

Fast neutrons are slowed by moderators, which contain water, carbon, deuterium, or beryllium, as thermal neutrons to increase the efficiency of their interaction with uranium-235. The rate of nuclear reaction is controlled by introducing additional rods made of boron or cadmium or a liquid absorbent, usually boric acid. Reactors for plutonium production are called breeder reactor or breeders; they have a different design and use fast neutrons.

Emission of neutrons during the fission of uranium is important not only for maintaining the nuclear chain reaction, but also for the synthesis of the heavier actinides. Uranium-239 converts via β-decay into plutonium-239, which, like uranium-235, is capable of spontaneous fission. The world's first nuclear reactors were built not for energy, but for producing plutonium-239 for nuclear weapons.

About half of produced thorium is used as the light-emitting material of gas mantles.[77] Thorium is also added into multicomponent alloys of magnesium and zinc. Mg-Th alloys are light and strong, but also have high melting point and ductility and thus are widely used in the aviation industry and in the production of missiles. Thorium also has good electron emission properties, with long lifetime and low potential barrier for the emission.[111] The relative content of thorium and uranium isotopes is widely used to estimate the age of various objects, including stars (see radiometric dating).[114]

The major application of plutonium has been in nuclear weapons, where the isotope plutonium-239 was a key component due to its ease of fission and availability. Plutonium-based designs allow reducing the critical mass to about a third of that for uranium-235.[115] The "Fat Man"-type plutonium bombs produced during the Manhattan Project used explosive compression of plutonium to obtain significantly higher densities than normal, combined with a central neutron source to begin the reaction and increase efficiency. Thus only 6.2 kg of plutonium was needed for an explosive yield equivalent to 20 kilotons of TNT.[116] (See also Nuclear weapon design.) Hypothetically, as little as 4 kg of plutonium—and maybe even less—could be used to make a single atomic bomb using very sophisticated assembly designs.[117]

Plutonium-238 is potentially more efficient isotope for nuclear reactors, since it has smaller critical mass than uranium-235, but it continues to release much thermal energy (0.56 W/g)[110][118] by decay even when the fission chain reaction is stopped by control rods. Its application is limited by its high price (about US$1000/g). This isotope has been used in thermopiles and water distillation systems of some space satellites and stations. The Galileo and Apollo spacecraft (e.g. Apollo 14[119]) had heaters powered by kilogram quantities of plutonium-238 oxide; this heat is also transformed into electricity with thermopiles. The decay of plutonium-238 produces relatively harmless alpha particles and is not accompanied by gamma rays. Therefore, this isotope (~160 mg) is used as the energy source in heart pacemakers where it lasts about 5 times longer than conventional batteries.[110]

Actinium-227 is used as a neutron source. Its high specific energy (14.5 W/g) and the possibility of obtaining significant quantities of thermally stable compounds are attractive for use in long-lasting thermoelectric generators for remote use. 228Ac is used as an indicator of radioactivity in chemical research, as it emits high-energy electrons (2.18 MeV) that can be easily detected. 228Ac-228Ra mixtures are widely used as an intense gamma-source in industry and medicine.[29]

Development of self-glowing actinide-doped materials with durable crystalline matrices is a new area of actinide utilization as the addition of alpha-emitting radionuclides to some glasses and crystals may confer luminescence.[120]

Toxicity

[edit]
Schematic illustration of penetration of radiation through sheets of paper, aluminium and lead brick
Periodic table with elements colored according to the half-life of their most stable isotope.

Radioactive substances can harm human health via (i) local skin contamination, (ii) internal exposure due to ingestion of radioactive isotopes, and (iii) external overexposure by β-activity and γ-radiation. Together with radium and transuranium elements, actinium is one of the most dangerous radioactive poisons with high specific α-activity. The most important feature of actinium is its ability to accumulate and remain in the surface layer of skeletons. At the initial stage of poisoning, actinium accumulates in the liver. Another danger of actinium is that it undergoes radioactive decay faster than being excreted. Adsorption from the digestive tract is much smaller (~0.05%) for actinium than radium.[29]

Protactinium in the body tends to accumulate in the kidneys and bones. The maximum safe dose of protactinium in the human body is 0.03 μCi that corresponds to 0.5 micrograms of 231Pa. This isotope, which might be present in the air as aerosol, is 2.5×108 times more toxic than hydrocyanic acid.[60][page needed]

Plutonium, when entering the body through air, food or blood (e.g. a wound), mostly settles in the lungs, liver and bones with only about 10% going to other organs, and remains there for decades. The long residence time of plutonium in the body is partly explained by its poor solubility in water. Some isotopes of plutonium emit ionizing α-radiation, which damages the surrounding cells. The median lethal dose (LD50) for 30 days in dogs after intravenous injection of plutonium is 0.32 milligram per kg of body mass, and thus the lethal dose for humans is approximately 22 mg for a person weighing 70 kg; the amount for respiratory exposure should be approximately four times greater. Another estimate assumes that plutonium is 50 times less toxic than radium, and thus permissible content of plutonium in the body should be 5 μg or 0.3 μCi. Such amount is nearly invisible under microscope. After trials on animals, this maximum permissible dose was reduced to 0.65 μg or 0.04 μCi. Studies on animals also revealed that the most dangerous plutonium exposure route is through inhalation, after which 5–25% of inhaled substances is retained in the body. Depending on the particle size and solubility of the plutonium compounds, plutonium is localized either in the lungs or in the lymphatic system, or is absorbed in the blood and then transported to the liver and bones. Contamination via food is the least likely way. In this case, only about 0.05% of soluble and 0.01% of insoluble compounds of plutonium absorbs into blood, and the rest is excreted. Exposure of damaged skin to plutonium would retain nearly 100% of it.[94]

Using actinides in nuclear fuel, sealed radioactive sources or advanced materials such as self-glowing crystals has many potential benefits. However, a serious concern is the extremely high radiotoxicity of actinides and their migration in the environment.[121] Use of chemically unstable forms of actinides in MOX and sealed radioactive sources is not appropriate by modern safety standards. There is a challenge to develop stable and durable actinide-bearing materials, which provide safe storage, use and final disposal. A key need is application of actinide solid solutions in durable crystalline host phases.[120]

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from Grokipedia

The actinides comprise a series of 15 metallic chemical elements in the periodic table, with atomic numbers ranging from 89 () to 103 (). These f-block elements feature the filling of the 5f electron subshell, resulting in properties akin to the lanthanides, such as multiple oxidation states from +3 to +6 or higher, dense silvery appearances, and high reactivity with oxygen, water, and acids. All actinides are radioactive, undergoing , or gamma decay, with only and present in appreciable natural abundances; the transuranic members ( through ) are artificially synthesized via or charged-particle bombardment. Discovered progressively from in 1789 to the heaviest via mid-20th-century nuclear research, actinides underpin in reactors and weapons, serve as fuels like and , and enable applications in radioisotope thermoelectric generators and targeted cancer therapies, despite challenges from their intense radioactivity and long-lived waste products.

History and Discovery

Natural Actinides: Actinium to Uranium

The natural actinides—, , , and —are the only members of this series found in significant quantities in , primarily as trace components in uranium- and thorium-bearing minerals such as pitchblende and . Thorium and uranium occur at concentrations of about 6 parts per million (ppm) and 2.8 ppm, respectively, making them more abundant than many rare earth elements, while and exist only in minute traces (less than 0.001 ppm) as decay products of uranium-235 and uranium-238. These elements were identified through classical chemical and spectroscopic techniques in the 18th and 19th centuries, predating nuclear reactors and accelerators, relying instead on fractional , , and mineral dissolution to separate them from ores. Uranium was the first natural actinide discovered, isolated in 1789 by German chemist from pitchblende ore sourced from the Joachimsthal mines in . Klaproth dissolved the ore in , reduced the resulting yellow oxide with , and observed a black metallic residue, which he named "uranium" after the recently discovered planet ; he confirmed its elemental nature through solubility tests and precipitation reactions, distinguishing it from known metals like iron and . Early analyses revealed uranium's radioactivity, noted by in 1896, but its key isotopes— (99.27% abundance, half-life of 4.468 billion years) and (0.72% abundance, half-life of 704 million years)—were not resolved until the 1930s via by Francis Aston and later Alfred Nier, who separated microgram quantities to measure isotopic masses differing by three neutrons. Thorium followed in 1828, when Swedish chemist analyzed thorite, a discovered by Morten Thrane Esmark in . Berzelius heated thorite with to yield thorium fluoride, then converted it to thorium chloride and reduced it with metal to obtain impure thorium, characterizing it as a new earth metal similar to yttria through in acids and formation of white oxides. Thorium's primary isotope, (virtually 100% natural abundance, half-life of 14.05 billion years), drives its geochemical persistence, with monazite sands later identified as a major commercial source containing up to 12% thorium oxide. Actinium, the lightest natural actinide, was isolated in 1900 by French chemist André-Louis Debierne from pitchblende residues after extraction. Debierne precipitated actinium from solutions of extracts, noting its intense and chemical similarity to ; Friedrich Giesel independently confirmed the element in 1902 via similar fractional crystallization, while verified its presence in 1903 through spectroscopic emission lines in purified fractions. Actinium-227, its sole natural isotope (beta and alpha decay half-life of 21.77 years), arises from decay chains, occurring at about 0.1 parts per trillion in uranium ores. Protactinium, bridging thorium and uranium, proved elusive due to its scarcity but was identified in 1917 by German chemists and , who purified 1 microgram from 100 tons of pitchblende via repeated precipitation with and zirconium hydroxide, detecting its alpha activity. Independently, and John Cranston in Britain used similar chemical purification from residues, confirming protactinium-231 (half-life 32,760 years, alpha emitter from decay) through its insolubility in acids and spectroscopic lines. These discoveries relied on laborious radiochemical separations, yielding milligram quantities only decades later.

Transuranic Synthesis: Neptunium to Lawrencium

Transuranic elements, with atomic numbers greater than 92, are synthesized artificially through nuclear reactions involving or charged-particle bombardment, as they do not occur naturally in significant quantities. These processes rely on successive beta decays following neutron absorption in nuclear reactors or direct transmutation via ion accelerators, enabling the extension of the periodic table beyond . Early efforts during , driven by the Manhattan Project's focus on fissile materials, accelerated the identification of and , while post-war advancements in and linear accelerator technology facilitated the production of heavier actinides up to . Neptunium, element 93, was first synthesized on June 1940 by Edwin M. McMillan and Philip H. Abelson at the , via irradiation of with neutrons in a , producing uranium-239 through the reaction 238^{238}U(n,γ\gamma)239^{239}U, followed by to 239^{239}Np with a of 23.5 minutes. This marked the initial artificial creation of a transuranic element, confirmed through chemical separation and radioactive analysis distinct from uranium fission products. Plutonium, element 94, was discovered in February 1941 by , , , and Arthur C. Wahl using the 60-inch at Berkeley to bombard with deuterons, yielding 239^{239}Pu via 238^{238}U(d,p)239^{239}U followed by two beta decays. The element was chemically isolated in microgram quantities and identified by its characteristic oxidation states and fission properties, with wartime secrecy delaying public announcement until 1946. Plutonium production scaled up in reactors for the , providing the bulk material for atomic bombs while enabling further transuranic research. In 1944, amid efforts, (element 95) was produced by Seaborg's team through successive neutron captures on in a , yielding which beta decayed to 241^{241}Am. (element 96) was synthesized concurrently by bombarding 239^{239}Pu with alpha particles in the 60-inch , forming 242^{242}Cm via 239^{239}Pu(α\alpha,n)242^{242}Cm. These discoveries, declassified in 1946, highlighted the complementary roles of reactors for multi-neutron processes and accelerators for charged-particle reactions. Subsequent actinides were created through escalating challenges, including diminishing production cross-sections and fleeting half-lives requiring rapid chemical separation techniques like ion-exchange . Berkelium (97) emerged in 1949 from helium-ion bombardment of , californium (98) in 1950 from curium-alpha reactions, and (101) in 1955 via helium on , all at Berkeley accelerators. (103), the heaviest known actinide at the time, was synthesized in March 1961 by and coworkers using the heavy-ion linear accelerator (HILAC) to bombard californium-252 with boron-11 or boron-10 ions, producing isotopes like 256^{256}Lr with half-lives under 30 seconds. These syntheses underscored the limits of then-available technology, with yields often in atomic rather than microgram quantities.

Occurrence and Production

Natural Abundance and Distribution

Thorium and are the only actinides present in significant quantities in the , with average abundances of approximately 10.5 parts per million (ppm) and 2.7 ppm, respectively, in the upper . These elements originated as primordial nuclides formed during the rapid neutron-capture (r-process) in astrophysical events such as supernovae and mergers, with their terrestrial abundances reflecting geochemical during rather than ongoing production. Actinium occurs only in trace amounts, primarily as a short-lived intermediate ( 21.77 years) in the decay chain, yielding concentrations on the order of 10^{-10} ppm or less in uranium-bearing minerals. , another decay product in the actinium series, is similarly negligible at around 10^{-12} ppm. Transuranic actinides beyond uranium are virtually absent naturally, except for primordial traces of , estimated at a total of about 9 grams globally in the crust due to its 81 million-year and r-process origin. Thorium concentrates in accessory minerals like ((Ce,La,Nd,Th)PO_4), found in granitic pegmatites, alkaline rocks, and heavy-mineral sands, often alongside rare earth elements. is enriched in pitchblende (massive , UO_2) and secondary minerals in hydrothermal vein deposits, unconformity-related ores, and sandstone-hosted formations. Seawater contains dissolved at an average concentration of 3.3 (ppb), uniformly distributed via ocean circulation, representing a vast but dilute resource equivalent to thousands of years of global demand if extractable.

Artificial Production in Reactors and Accelerators

Plutonium-239, the most significant artificially produced actinide for energy and weapons applications, forms in nuclear reactors via neutron capture on uranium-238 followed by two beta decays: ^{238}U + n → ^{239}U → ^{239}Np → ^{239}Pu, with half-lives of 23 minutes and 2.36 days for the intermediates, respectively. The thermal neutron radiative capture cross-section for ^{238}U is 2.68 barns, enabling efficient conversion in high-flux environments. Industrial-scale production began at the Hanford Site in Washington state, where the B Reactor achieved criticality on September 26, 1944, yielding the plutonium used in the Nagasaki bomb and subsequent wartime output. In breeder reactors, particularly fast-spectrum designs, neutron economy supports a breeding ratio exceeding 1, producing more fissile ^{239}Pu than consumed uranium-235 or other fissiles, with typical ratios of 1.2 to 1.5 depending on core configuration and flux. This process utilizes fast neutrons to minimize parasitic captures, enhancing yields from fertile ^{238}U. Modern closed fuel cycles incorporate plutonium recycling via mixed oxide (MOX) fuel, blending 7-10% plutonium oxide with uranium oxide; for example, light-water reactors loaded with MOX generate additional plutonium in the ^{238}U component while burning existing stockpiles, with global annual MOX fabrication consuming around 10 metric tons of plutonium. Heavier actinides, such as , , and , require multiple neutron captures and are produced in specialized high-flux reactors like HFIR at Oak Ridge, but initial synthesis and trace quantities often rely on particle accelerators. In accelerators, heavy-ion beams collide with target nuclei to fuse and form transuranics; , for instance, was first synthesized in December 1949 at Berkeley Lab by bombarding with alpha particles in a , producing microgram quantities via ^{241}Am(^{4}He,2n)^{243}Bk followed by . These methods yield minuscule amounts—often picograms to milligrams—due to low fusion cross-sections (on the order of picobarns) and rapid decay, necessitating rapid chemical separation.

Nuclear Properties and Isotopes

Isotopic Stability and Decay Modes

Actinide isotopes exhibit a range of decay modes, with predominating across the series due to the high atomic numbers and resulting repulsion favoring emission of nuclei. For heavier actinides beyond , remains the primary mode, though emerges as a competing pathway starting with isotopes, where the nuclear barrier against fission lowers sufficiently to allow barrier penetration without external excitation. occurs in some lighter isotopes, such as those of and , but is less common overall compared to alpha processes. and are rare and typically confined to neutron-deficient isotopes produced in accelerators. Half-lives of actinide isotopes vary dramatically, reflecting differences in nuclear binding and fission barriers; they range from sub-second durations for the heaviest, neutron-rich transuranics to billions of years for primordial nuclides. For instance, ^{257}Lr, the most stable of , has a of 0.646 seconds, decaying primarily by alpha emission to ^{253}Md. In contrast, ^{238}U possesses a of (4.4683 ± 0.0024) × 10^9 years, enabling its persistence in since planetary formation. Transplutonium isotopes generally show decreasing half-lives with increasing , though local enhancements occur near neutron numbers influenced by shell closures, such as N=152, which increases fission resistance and extends lifetimes empirically observed in and isotopes. Natural actinides contribute to four distinct decay chains, differentiated by the modulo 4, each culminating in stable lead isotopes after successive alpha and beta decays. The 4n+1 uranium series, headed by ^{238}U, proceeds through ^{234}Th, ^{234}Pa, and others to ^{206}Pb; the 4n+2 thorium series from ^{232}Th leads to ^{208}Pb; the 4n+3 actinium series originates with ^{235}U (via of ^{235}Pa) and ends at ^{207}Pb; while the 4n neptunium series, starting from extinct ^{237}Np or ^{241}Pu, terminates at ^{205}Tl followed by to ^{205}Pb but leaves no significant natural traces due to short primordial half-lives. These chains underscore the sequential instability of actinide nuclides, with branching ratios determined by competing alpha and beta partial half-lives. Synthetic isotopes beyond form transient chains, often terminating quickly via alpha cascades without stable endpoints in nature. Nuclear shell effects, arising from filled subshells at magic proton (Z=82, 90) or neutron (N=126, 152) numbers, modulate isotopic stability by enhancing binding energies and raising fission barriers, as evidenced in the relatively longer half-lives of even-neutron isotopes near these closures compared to odd-neutron neighbors. This empirical pattern, observed in decay data for berkelium through mendelevium, contrasts with smoother trends expected from liquid-drop models alone, highlighting quantum shell structure's role in actinide persistence. Spontaneous fission half-lives, calculated via barrier penetration integrals, further reveal these effects, with californium isotopes like ^{252}Cf showing partial SF half-lives around 10^9 years despite dominant alpha decay.

Fissile, Fertile, and Key Isotopes

Fissile isotopes among the actinides, notably , , and , sustain nuclear chain reactions primarily through fission induced by low-energy () neutrons, where the probability of leading to fission exceeds parasitic absorption or scattering, enabling a multiplication factor k>1k > 1. These isotopes exhibit odd neutron numbers, correlating with lower fission barriers and higher cross-sections for -induced fission compared to even-neutron counterparts. , in particular, has a fission cross-section of approximately 750 barns, facilitating higher neutron yields per fission (averaging 2.9 neutrons) than (2.5 neutrons), which influences reactor design for sustained criticality. Fertile actinide isotopes, such as , absorb s to form fissile daughters via successive capture and : uranium-238 captures a neutron to yield uranium-239, which decays to neptunium-239 and then . In fast-spectrum reactors, where neutron energies minimize resonance capture losses, breeding from uranium-238 can achieve ratios exceeding 1, converting more fertile material into fissile plutonium-239 than is fissioned. Similarly, ( 90, an actinide) serves as a fertile precursor to through , protactinium-233 intermediate, and , supporting thorium-based breeding cycles with potential for high conversion in both and fast systems due to favorable neutron economy. Other key actinide isotopes include and curium-244, valued for neutron emission properties independent of external fluxes. Americium-241 decays via alpha emission ( 432.6 years), producing neutrons at ~0.6 per second per gram when paired with in (α,n) sources, enabling applications in and detection without reliance on fission chains. Curium-244, with a spontaneous fission yield of approximately 2.3 × 10^9 neutrons per second per milligram and average energy ~2.3 MeV, provides high-intensity, self-sustaining neutron fluxes suitable for similar uses, though its 18.1-year limits longevity. These properties stem from inherent decay modes rather than induced reactions, distinguishing them from fissile/fertile roles in energy production.

Physical Properties

Crystal Structures and Phase Transitions

Actinide metals exhibit a range of crystal structures at ambient conditions, transitioning from relatively simple close-packed lattices in the early members to more complex, low-symmetry forms in the light transuranics due to directional 5f bonding, before reverting to lanthanide-like close-packed structures in heavier elements as 5f electrons localize. Thorium crystallizes in a face-centered cubic (fcc) structure with lattice parameter a = 508.4 pm. Protactinium adopts a body-centered tetragonal lattice, uranium a distorted orthorhombic α-phase (space group Cmcm), neptunium an orthorhombic α-phase, and plutonium a low-symmetry monoclinic α-phase at room temperature. From americium to curium, double hexagonal close-packed (dhcp) structures predominate, with subsequent actinides showing hexagonal close-packed (hcp) or fcc variants. These structures correlate with density trends, which rise sharply from (11.8 g/cm³) through (19.1 g/cm³) and (20.5 g/cm³) to (19.9 g/cm³), driven by increasing 5f delocalization and strength, before dropping to ~13.5–13.7 g/cm³ for and as 5f localization reduces overlap and promotes more atomic-like character. and diffraction studies confirm these lattice parameters and reveal anomalies, such as the unusually low density of δ- (~15.8 g/cm³), attributable to its fcc arrangement stabilized by minor doping (1–2 at.%) to prevent transformation to the denser α-phase. Temperature-induced phase transitions are prominent, often martensitic and accompanied by volume changes detectable via dilatometry and resistivity measurements. Uranium's α-phase converts to tetragonal β at 667 °C and body-centered cubic (bcc) γ at 775 °C, with the α-β transition involving a 0.5% volume contraction. Plutonium displays six allotropes, with the fcc δ-phase stable between 310 °C and 452 °C in pure form but extendable to via alloying, transforming to bcc δ' above 452 °C; this multiplicity arises from near-degeneracy of electronic states. Neptunium undergoes an α (orthorhombic) to β (tetragonal) transition at approximately 576 °C, followed by bcc γ. Heavier actinides show fewer transitions, with curium's dhcp structure persisting to higher temperatures before melting. data underscore how these shifts reflect competition between 5f itinerancy and localization, influencing mechanical properties like in stabilized δ-plutonium.

Thermodynamic and Magnetic Properties

The thermodynamic properties of actinides reflect the dual nature of their 5f electrons, which can behave as itinerant band states in lighter elements or localized moments in heavier ones, leading to enhanced low-temperature heat capacities. Calorimetric studies show that the electronic specific heat coefficient γ for α-uranium is approximately 10.4 mJ mol⁻¹ K⁻², arising from a high at the due to partial 5f delocalization and hybridization with 6d and 7s orbitals. In , γ reaches values up to 50 mJ mol⁻¹ K⁻² in certain phases, signaling stronger electron correlations and quasiparticle masses influenced by 5f localization. These anomalies in specific heat, often manifesting as λ-type peaks or Schottky contributions, causally link to phase transitions where 5f electrons drive magnetic or structural instabilities, as seen in compounds like UN with γ ≈ 75 mJ mol⁻¹ K⁻² from heavy fermion behavior. Magnetic properties transition from Pauli paramagnetism in early actinides, where delocalized 5f electrons yield temperature-independent susceptibilities (e.g., χ ≈ 1.5 × 10⁻⁴ emu mol⁻¹ Oe⁻¹ for metal), to ordered states in heavier elements due to increasing localization from relativistic contraction and analogs. Alpha-neptunium exhibits below T_N ≈ 7 K with a saturated moment of 2.2 μ_B per atom, reflecting localized 5f³ configuration and exchange interactions. metal lacks long-range order but displays anomalous susceptibility enhancements from self-irradiation defects creating local moments, with no bulk despite theoretical predictions of short-range correlations. This shift underscores causal realism in 5f bandwidth narrowing across the series, enabling magnetic ordering where electron itinerancy suppresses it. Certain actinide intermetallics exhibit tied to 5f-derived electronic states, such as UBe₁₃ with T_c ≈ 0.85 K, where unconventional p-wave pairing emerges from strong coupling to spin fluctuations in a sea (effective mass m* ≈ 2-3 m_e). Thermal conductivity in δ-phase Pu-Ga alloys (e.g., 2-4 at.% Ga) is notably low, ranging from 5-15 W m⁻¹ K⁻¹ between 25-500°C, attributed to by anisotropic 5f bonding and electronic contributions limited by umklapp processes in the stabilized face-centered cubic lattice. These properties, derived from empirical transport and calorimetric data, highlight how 5f delocalization controls thermal transport efficiency in applications like nuclear fuels.

Chemical Properties

Oxidation States and Reactivity

Actinide elements exhibit oxidation states ranging from +3 to +6, with some achieving +2 or +7 under specific conditions, reflecting the comparable energies of 5f, 6d, and 7s orbitals that enable facile electron transfer. is predominantly limited to +4, as higher states are unstable and lower ones rare in aqueous media. displays +3 to +6, with +4 and +6 being particularly stable; the +6 state persists in the ion (UO₂²⁺), which resists reduction under ambient conditions. and extend to +7, though +7 is transient for and requires strong oxidants; these elements coexist in multiple states in solution, complicating . Early transactinides like favor +3, with +4 accessible but less stable, while and heavier analogs are dominantly trivalent due to half-filled or filled 5f shells enhancing +3 stability. Reactivity trends across the actinides diminish with increasing , attributable to actinide contraction—the gradual ionic radius decrease from to arising from imperfect 5f shielding of nuclear charge, which amplifies effective nuclear attraction and stabilizes ions against further reduction or . This contraction parallels behavior but is more pronounced, leading to harder Lewis acid character and reduced coordination flexibility in later elements. Finely divided metals, particularly , display heightened reactivity; plutonium powder ignites spontaneously in air at or below 150°C, driven by exothermic formation and surface area effects that accelerate oxidation kinetics. Bulk plutonium requires higher temperatures (around 475°C) for ignition, underscoring size-dependent relevant to handling protocols. Empirical standard reduction potentials quantify accessibility and guide reactivity predictions. The Pu⁴⁺/Pu³⁺ couple exhibits E° ≈ +0.97 V (vs. SHE in acidic media), rendering Pu³⁺ a strong reductant relative to U³⁺ (E° ≈ -0.52 V for U⁴⁺/U³⁺), which informs selective oxidation in reprocessing schemes like where plutonium partitioning relies on differential potentials. Similarly, NpO₂²⁺/NpO₂⁺ at +1.14 V facilitates neptunium valence control, while decreasing potentials for M⁴⁺/M³⁺ couples (e.g., Am⁴⁺/Am³⁺ > +2 V) reflect rising stability of +3 states, correlating with contraction-induced orbital contraction and reduced electron donation capacity. These potentials, measured via electrochemical cells or , vary modestly with anion complexation but underpin process design for actinide handling.

Electronic Structure and Relativistic Effects

The electronic configuration of actinides features the filling of the 5f orbitals, which generally host 0 to 14 electrons across the series from (5f^0) to (5f^{14}). In early actinides such as through , the 5f electrons exhibit itinerant character, delocalizing to participate in and hybridization with ligand orbitals, as evidenced by band structure calculations and photoelectron showing extended bandwidths. This delocalization transitions to more localized 5f states in transplutonium elements like and beyond, where electrons behave akin to core-like orbitals with minimal overlap, leading to narrower bands and reduced conductivity. Relativistic effects, particularly Dirac contraction and spin-orbit coupling, profoundly influence actinide bonding by altering orbital energies and radial distributions. The high nuclear charge (Z > 89) contracts the 7s and 7p orbitals while expanding the 6d and 5f shells, enhancing 5f-ligand hybridization and stabilizing higher oxidation states (e.g., +5 and +6 in uranium and neptunium) through better energy matching with valence orbitals. These scalar relativistic and spin-orbit contributions, absent or weaker in lanthanides due to lower Z, increase the availability of 5f electrons for covalent interactions without overemphasizing their role beyond spectroscopic confirmation. X-ray photoelectron spectroscopy (XPS) of 5d core levels reveals multiplet splittings indicative of strong 5f-5d exchange and hybridization, while extended X-ray absorption fine structure (EXAFS) data quantify shortened bond lengths consistent with partial covalency in compounds like uranyl. Ionization energies across the actinides show irregular trends, with first ionization potentials ranging from approximately 499 kJ/mol for to 578 kJ/mol for , reflecting poor shielding by 5f electrons that amplifies despite increasing Z. Electron affinities remain generally low and negative, decreasing slightly toward heavier actinides due to relativistic stabilization of neutral atoms over anions, contrasting the more uniform trends where 4f localization limits variability. These patterns arise from first-principles considerations of radial wavefunction overlap and core contraction, enabling greater chemical versatility in actinides than in lanthanides.

Compounds and Coordination Chemistry

Oxides, Halides, and Binary Compounds

The dioxides of tetravalent actinides, including thorium(IV) oxide (ThO₂), uranium(IV) oxide (UO₂), neptunium(IV) oxide (NpO₂), plutonium(IV) oxide (PuO₂), americium(IV) oxide (AmO₂), and curium(IV) oxide (CmO₂), adopt the face-centered cubic fluorite structure with space group Fmm, characterized by a lattice parameter of approximately 5.6 Å for UO₂ and similar values for PuO₂. This structure features octahedral coordination of oxygen around the actinide cation, with eightfold coordination for the metal, contributing to their high thermodynamic stability and low solubility in aqueous media, as evidenced by solubility product constants (Ksp) on the order of 10-50 to 10-60 for UO₂ under neutral conditions derived from experimental solubility measurements. Sesquioxides of trivalent actinides (An₂O₃, An = Am to Lr) typically form either hexagonal A-type or cubic C-type (bixbyite) structures, with the former predominant for lighter actinides like americium due to closer packing and lower density. Actinide halides exhibit diverse structures depending on oxidation state and halide anion. Trivalent actinide chlorides (AnCl₃, An = Ac to Cf) generally crystallize in hexagonal structures akin to the PuBr₃ type, with layers of AnCl₉ tricapped trigonal prisms linked by edge-sharing, though some heavier analogs show orthorhombic distortions due to actinide contraction reducing An-An distances by about 0.2 Å across the series. Tetravalent fluorides (AnF₄, An = Th to Cm) display ionic layered structures, such as the body-centered tetragonal arrangement in ThF₄ (space group I4₁/amd) or monoclinic in UF₄ (P2₁/n), with AnF₁₂ polyhedra forming chains or sheets stabilized by fluorine bridges; these compounds hydrolyze readily in moist air, forming AnO₂ or oxyfluorides via stepwise replacement of F⁻ by OH⁻, as quantified by hydrolysis constants (Kh) around 10-3 to 10-5 from potentiometric studies. Tetravalent chlorides like UCl₄ and PuCl₄ adopt tetragonal structures with AnCl₈ square antiprisms, while hexafluorides such as UF₆ form orthorhombic crystals (Pnnm*) notable for their volatility, subliming at 56.5°C under standard pressure. Uranyl fluoride (UO₂F₂), a key binary oxyfluoride, exhibits volatility in fluoride-based processing routes, decomposing or converting to UF₆ at elevated temperatures above 300°C in fluorine atmospheres, facilitating uranium purification through gas-phase separation with decomposition yields exceeding 99% under controlled conditions. Solubility studies indicate low aqueous stability for most binary actinide halides, with Ksp values for AnF₃ around 10-20 to 10-25, reflecting strong lattice energies but susceptibility to that limits their handling without inert atmospheres.
Compound TypeExamplesStructureKey Stability Feature
AnO₂ (+4)UO₂, PuO₂ (Fmm)Ksp ~10-55
An₂O₃ (+3)Am₂O₃Hexagonal A-typeThermally stable to >1000°C
AnCl₃ (+3)UCl₃Hexagonal PuBr₃-typeHydrolysis Kh ~10-4
AnF₄ (+4)ThF₄, UF₄Tetragonal/MonoclinicLayered ionic, low solubility
AnCl₄ (+4)UCl₄TetragonalSublimes ~500°C

Organometallics and Molecular Complexes

, formulated as U(η⁸-C₈H₈)₂, stands as the prototypical organoactinide sandwich complex, synthesized in 1968 via the reaction of uranium tetrachloride with and metal in , yielding a dark-brown, air-sensitive solid with a of 170–175 °C under vacuum. This compound exhibits bent metallocene-like geometry with U–C distances averaging 2.64 and demonstrates notable stability for an actinide organometallic, attributed to delocalized π-bonding involving 6d, 5f, and orbitals, as evidenced by UV-visible showing absorptions at 490 nm and 590 nm indicative of f–f transitions modulated by ligand field effects. Unlike d-block metallocenes, uranocene's bonding incorporates significant 5f covalency, confirmed through photoelectron revealing 5f potentials around 6–7 eV. Advancements in sterically encumbered cyclooctatetraenyl ligands have enabled the isolation of homoleptic An(η⁸-COT')₂ complexes across early actinides, including thorium, uranium, neptunium, and plutonium, with reports in 2025 detailing asymmetric variants like An(hdcCOT)₂ that probe electronic structure trends via near-infrared spectroscopy and density functional theory calculations. These complexes feature An–C bond lengths decreasing from Th (2.72 Å) to Pu (2.58 Å), reflecting contraction of 5f orbitals and increasing relativistic stabilization, while X-ray crystallography highlights parallel ring orientations with inter-ring distances of approximately 3.6 Å. Extension to transplutonium elements culminated in the 2025 synthesis of tetravalent berkelocene, Bk(η⁸-C₈H₈)₂, via oxidation of trivalent precursor with Ag(I), marking the first such complex for berkelium and revealing enhanced Bk–C covalency through shorter bonds (2.55 Å) compared to uranocene, as probed by single-crystal diffraction. Molecular complexes employing macrocyclic ligands, such as phosphinoylated p-tert-butylcalixarenes, form discrete 1:1 adducts with actinides in oxidation states III–VI, where the calixarenes adopt cone conformations to encapsulate the metal via oxygen and phosphorus donor atoms, achieving coordination numbers up to 10. These ligands exploit size-selective cavity effects for preferential actinide binding over lanthanides, with extraction efficiencies for Am(III) exceeding 90% in media, as quantified by liquid–liquid distribution coefficients; spectroscopic confirmation via shows red-shifted emission for U(VI) complexes due to 5f– charge transfer. In gas-phase applications, volatile organoactinides like U(C₅H₅)₃Cl exhibit sublimation points below 150 °C, enabling chromatographic separations monitored by , which reveal isotopic fractionation patterns tied to molecular volatility. Resonant inelastic X-ray scattering (RIXS) and X-ray absorption near-edge (XANES) analyses of these complexes 5f orbital involvement in , with examples displaying post-edge features at 17–20 keV attributable to 5f–6d hybridization, distinguishing actinide covalency from ionic interactions. Such spectroscopic signatures, combined with computational analyses yielding Wiberg indices of 0.2–0.4 for An–C σ-bonds, affirm that 5f electrons contribute to both σ- and π-interactions, enhancing reactivity in small-molecule activation like dinitrogen reduction observed in low-valent congeners.

Separation and Extraction Methods

Hydrometallurgical and Solvent Extraction Techniques

Hydrometallurgical techniques for actinides begin with acid leaching of ores to solubilize metal ions, followed by solvent extraction to isolate and purify specific elements from impurities. For ores such as deposits, leaching dissolves U(VI) species, achieving extraction efficiencies up to 98% under optimized conditions like elevated temperatures (40–60°C) and controlled pulp density. Subsequent solvent extraction employs tertiary amines (e.g., Alamine 336) or (TBP) in diluents, with distribution coefficients favoring U(VI) over co-extracted metals like iron or , enabling >99% recovery in multi-stage counter-current systems at low acid concentrations (e.g., 0.15 M H₂SO₄). The process, central to reprocessing , involves dissolving irradiated fuel in 5–7 M to form nitrate complexes, followed by selective extraction of U(VI) and Pu(IV) into 30% TBP/ from the aqueous phase. Distribution coefficients for UO₂(NO₃)₂·2TBP and Pu(NO₃)₄·2TBP exceed 10 at concentrations above 3 M, allowing efficient partitioning from fission products. is selectively stripped as Pu(III) using reductants like ferrous sulfamate, while is recovered via aqueous stripping or reduction, yielding >99% overall recovery for both elements and minimizing waste volumes in industrial operations. Thorium extraction from monazite sands employs digestion to convert thorium to soluble , followed by solvent exchange using TBP or quaternary ammonium salts (e.g., ) in media to separate Th(IV) from rare earth elements. Bench-scale processes achieve thorium recovery exceeding 95% in two-cycle extractions, with thorium stripped using dilute acid or oxalate precipitation for isolation. Separating trivalent actinides (e.g., Am(III), Cm(III)) from lanthanides in poses challenges due to their similar ionic radii (separation factors often <10) and coordination preferences, limiting straightforward TBP-based methods to higher-valent species. Established hydrometallurgical approaches rely on pH adjustments or multi-extractant cycles, but co-extraction inefficiencies necessitate tailored conditions, with empirical recoveries for minor actinides typically below 90% without advanced ligands.

Advanced Separation Technologies

The Group Actinide Extraction (GANEX) process represents a key advancement in homogeneous co-extraction of transuranic actinides from spent nuclear fuel, with the EURO-GANEX variant demonstrating robust performance in continuous counter-current tests conducted in 2022, achieving over 99% recovery of plutonium, neptunium, americium, and curium while minimizing lanthanide co-extraction under nitric acid conditions. This process partitions actinides as a group prior to individual separations, reducing secondary waste streams by up to 90% compared to sequential minor actinide extractions, as validated in lab-scale flowsheets simulating high-burnup fuels. Empirical data from these tests confirm distribution ratios exceeding 10 for key actinides at 3-5 M HNO₃, supporting scalability for closed fuel cycles. Graphene oxide (GO) membranes have emerged as a novel ion-sieving platform for actinide-lanthanide (An/Ln) separation, with a 2023 study reporting selective permeation of spherical Ln³⁺ ions over linear actinyl ions (AnO₂²⁺/AnO₂⁺) under highly acidic conditions (1-3 M HNO₃), achieving separation factors greater than 100 for uranium(VI) versus europium(III) due to size-exclusion and hydration differences. These membranes, fabricated via layer-by-layer assembly, exhibited flux rates of 10-20 L m⁻² h⁻¹ bar⁻¹ and stability over 100 hours of operation, enabling group partitioning without chemical degradation typical of solvent-based methods. Lab demonstrations confirmed >95% rejection of actinyl species while permeating lanthanides, empirically lowering volumes by concentrating minor actinides for transmutation. For americium-curium (Am/Cm) partitioning, diglycolamide ligands in the AmSel have been refined post-2020, with N,N-diisopropyl-N′,N′-didodecyldiglycolamide (iPDdDGA) yielding Am/Cm separation factors of 3-5 in media, surpassing traditional TODGA by reducing extraction via steric hindrance, as shown in 2024 batch and column experiments. Integrated with ionic liquids like Aliquat-336 , these systems enhance selectivity for Am(III) over Cm(III) and lanthanides, with distribution coefficients >50 for at pH 2-3, while maintaining stability under simulated gamma doses up to 100 kGy. Such metrics support volume reduction by isolating for targeted transmutation, with empirical recoveries exceeding 99% in multi-stage extractions from raffinates.

Applications

Nuclear Fuel Cycle and Energy Production

Actinides, particularly uranium and plutonium isotopes, serve as the primary fissile materials in nuclear fission for energy production. In light water reactors (LWRs), which dominate global nuclear capacity, uranium-235 constitutes the initial fissile component of enriched uranium fuel, typically at 3-5% enrichment, undergoing fission to release energy. During operation, uranium-238 captures neutrons to form plutonium-239, which becomes a significant fissile contributor, accounting for up to half of the energy output in a typical fuel cycle. The of actinide-based vastly exceeds that of fossil fuels, enabling compact fuel requirements for substantial output. One of can produce approximately 2.7 million times the energy of an equivalent mass of by mass, reflecting the ~10^6-fold advantage in content due to fission's release of from heavy nuclei. This efficiency translates to a single uranium fuel pellet generating equivalent to several tons of or , minimizing and transport needs. Mixed oxide (MOX) fuel, incorporating recycled oxide with oxide, enhances resource utilization in LWRs by closing the fuel cycle partially. MOX, typically containing 5-7% , achieves rates comparable to conventional fuel, with operational data from facilities like France's Melox demonstrating energy equivalence and performance metrics on par with UO2, including fission gas release and cladding integrity. via MOX has supported about 10% of France's nuclear production, recovering over 95% of the energy potential from reprocessed spent fuel. Fast breeder reactors extend actinide resources through breeding, converting fertile isotopes like to fissile or to uranium-233. In plutonium-uranium cycles, breeding ratios exceed 1.0, potentially multiplying fuel supply by factors of 60-100 over mining alone; the thorium-uranium cycle, viable in both thermal and fast spectra, leverages abundant reserves for sustainable fission. Designs like or sodium-cooled fast reactors optimize economy for multi-recycling of actinides, reducing long-term fuel dependency. Nuclear fission from actinides yields lifecycle CO2 emissions of 10-20 g/kWh, orders of magnitude below (820 g/kWh) or gas (490 g/kWh), with emissions arising mainly from and rather than operation. This low-carbon profile, combined with capacity factors exceeding 90% for baseload operation, provides dispatchable power contrasting the intermittency of renewables like (35% capacity factor) and solar (25%), enabling grid stability without backup.

Military and Defense Applications

Actinides, particularly and , serve as the primary fissile materials in the cores of nuclear weapons, enabling fission chain reactions that underpin implosion-type designs. , an isotope transmuted from in breeder reactors, forms the spherical pit at the heart of these devices, surrounded by high explosives that compress it to supercriticality upon detonation. The bomb, the first plutonium-based weapon deployed in combat, utilized a 6.2 kg plutonium core and exploded over on August 9, 1945, producing a yield of 21 kilotons of . Modern thermonuclear warheads retain plutonium pits for their primary fission stage, with yields scalable to megatons through fusion boosting, ensuring reliability under programs that certify performance without full-scale testing. Depleted uranium, predominantly the isotope with trace radioactivity after enrichment processes remove fissile , is alloyed into dense penetrators for munitions. These long-rod projectiles, typically 10-15 kg in mass and fired at muzzle velocities over 1,500 m/s from tank guns such as the ' 120 mm , exploit uranium's 19.1 g/cm³ and pyrophoric fragmentation to defeat armored targets by eroding and self-sharpening on impact. Deployed in operations like the 1991 , where over 100 tons were expended by U.S. forces, munitions provide superior penetration against composite and reactive armors compared to alternatives, enhancing battlefield lethality without explosive warheads. The integration of actinides into arsenals bolsters through credible nuclear deterrence, where the assured capacity for devastating retaliation discourages large-scale aggression among peers. Since 1945, this posture has correlated with no direct conventional wars between nuclear-armed states, as adversaries weigh the risk of escalation to existential threats against territorial gains. Complementing deterrence, (IAEA) safeguards enforce material accountancy and inspections on separated and to verify non-diversion from civilian to military uses, applying to over 2,000 facilities globally under comprehensive agreements.

Non-Nuclear Uses: Medical, Industrial, and Space

Americium-241 serves as the primary actinide in detectors, where its alpha emissions ionize air in a detection chamber, creating a current disrupted by smoke particles to trigger alarms. Typical residential units contain approximately 0.9 to 1 microcurie (37 kBq) of Am-241, enabling reliable detection with minimal . Beyond consumer safety devices, Am-241 functions as a in industrial applications such as non-destructive testing of machinery, thickness gauging in , and moisture content measurement in materials. Californium-252 provides high for specialized industrial neutron sources, supporting prompt gamma (PGNAA) to determine elemental composition in bulk materials like , , and minerals. These sources enable on-stream process control, neutron radiography for flaw detection in metals, and calibration of gauging equipment, with Cf-252's yielding up to 2.3 × 10^6 neutrons per second per . Such applications remain low-volume due to production costs but deliver high precision in and resource . ![InsideSmokeDetector.jpg][float-right] In medical contexts, actinium-225 enables targeted alpha therapy (TAT) for solid tumors, particularly prostate cancer, by conjugating the isotope to ligands like PSMA-617 that bind selectively to cancer cells, delivering localized alpha particle doses that induce DNA double-strand breaks with minimal penetration beyond 0.1 mm. Clinical trials since 2013 have demonstrated response rates exceeding 50% in metastatic castration-resistant prostate cancer patients refractory to other therapies, with Ac-225 decaying through four alpha-emitting daughters for enhanced cytotoxicity. Supply constraints limit widespread adoption, prompting research into generators from thorium-229 and radium-225 precursors. For , fuels radioisotope thermoelectric generators (RTGs), converting decay heat to electricity via thermocouples for missions lacking solar access, as in the and 2 probes launched in 1977, which initially produced 470 watts electrical from three RTGs each containing about 3.5 kg of PuO2. With a of 87.7 years, Pu-238 sustains output degradation to about half over mission lifetimes, providing 0.57 watts thermal per gram and low neutron/gamma emissions suitable for uncrewed deep-space operations. Historical prototypes briefly employed for its high initial power density, but its 138-day necessitated replacement by Pu-238 for long-duration reliability. ![Radioisotope thermoelectric generator plutonium pellet.jpg][center]

Health, Safety, and Environmental Considerations

Radiotoxicity Mechanisms and Biological Effects

![Alpha, beta, and gamma radiation penetration][float-right] The radiotoxicity of actinides stems predominantly from their emissions during , which produce high (LET) radiation of approximately 100 keV/μm, causing dense ionization tracks that inflict severe localized cellular damage, including clustered DNA double-strand breaks and high (RBE) values typically around 20 for cancer induction in models. Alpha particles travel only 20-100 μm in , limiting external penetration but amplifying internal hazards when actinides are internalized, as the short range concentrates energy deposition in sensitive organs like the lungs, liver, and bone. This mechanism contrasts with beta or gamma emitters, where energy is more diffusely deposited, resulting in lower RBE for effects. Inhalation represents the dominant uptake pathway for insoluble actinide oxides such as plutonium dioxide (PuO₂), where respirable particles (<5 μm) deposit in the pulmonary alveoli and exhibit slow dissolution rates, leading to prolonged lung retention with biological half-lives exceeding 100 days. Systemic translocation occurs via gradual solubilization and macrophage-mediated transport to regional lymph nodes or bloodstream, after which tetravalent actinides like Pu(IV) and Am(IV) sequester primarily in the liver (40-70% of burden) and skeleton (20-40%), where alpha emissions irradiate adjacent hematopoietic and parenchymal cells, elevating risks of fibrosis, necrosis, and carcinogenesis. For occupational exposure, the annual limit of intake (ALI) for PuO₂ inhalation is approximately 200-800 Bq, reflecting the compound's class S (slow absorption) biokinetics and the need to constrain committed effective doses below 20 mSv. Lethal dose 50% (LD50) values from rodent inhalation studies indicate acute pulmonary toxicity at 3-10 μg PuO₂/kg body weight, corresponding to rapid inflammatory responses and radiation pneumonitis rather than purely stochastic effects. Empirical data from the Mayak Production Association workers, exposed to elevated plutonium via chronic inhalation (cumulative lung doses up to several Gy in high-exposure cohorts), demonstrate dose-dependent increases in lung, liver, and bone malignancies, with excess relative risks of approximately 0.4-1.0 per Gy for lung cancer, yet no detectable effects in subgroups with doses below 0.2-0.5 Gy, suggesting potential thresholds or overestimation by linear no-threshold extrapolations from high-dose data. These observations, derived from longitudinal tracking of over 25,000 workers since the 1940s, indicate that actual health burdens align more closely with moderate risk coefficients than alarmist projections, particularly when accounting for confounding factors like external gamma exposure and smoking. Comparative assessments reveal that radiotoxicity per unit energy generated in the nuclear fuel cycle is substantially lower than radon progeny risks in coal mining or inherent radioactivity in coal fly ash, with coal-related ionizing radiation linked to 18-fold higher normalized mortality rates. Mitigation via chelation therapy employs diethylenetriaminepentaacetic acid (DTPA), typically as calcium or zinc salts, which binds transuranic actinides like Pu and Am to form excretable complexes, achieving up to 50% decorporation of systemic burdens if administered within hours of intake, though efficacy diminishes over time due to tissue sequestration. In vivo models confirm DTPA's preferential enhancement of urinary elimination over fecal, with repeated dosing protocols reducing long-term organ doses by factors of 2-10 for early interventions.

Waste Management Strategies and Transmutation

High-level waste (HLW) from nuclear fuel reprocessing, which includes minor actinides such as and alongside fission products, is commonly immobilized through vitrification, converting liquid waste into durable glass logs for long-term storage and disposal. This process encapsulates radionuclides, reducing leach rates and volume by factors of 5-10 compared to untreated waste, with operational facilities like France's La Hague plant vitrifying over 4,000 canisters annually since the 1990s. Vitrification matrices, typically borosilicate glass, withstand repository conditions for millennia, though actinide solubility limits loading to 10-20 wt% to prevent phase separation. To address the long-lived radiotoxicity of minor actinides (MAs), partitioning and transmutation (P&T) strategies separate these elements via advanced aqueous or pyrochemical processes following initial PUREX extraction of uranium and plutonium, enabling targeted fission in high-neutron-flux environments. Partitioning achieves >99% recovery of MAs like and curium-244, reducing HLW actinide content and allowing transmutation, which converts them into shorter-lived fission products through and fission. In accelerator-driven systems (ADS), a proton accelerator generates spallation neutrons in a subcritical lead-bismuth core, providing a hard spectrum ideal for MA fission cross-sections of approximately 1-2 barns for and isotopes. Generation IV fast reactors, such as sodium- or lead-cooled designs, similarly facilitate MA burning in a closed cycle, with transmutation rates up to 50-100 kg/year per gigawatt thermal in optimized cores, leveraging fast spectra to fission >90% of loaded MAs over multiple recycles. P&T demonstrably lowers the radiotoxicity index—measured in sieverts per initial heavy metal—by factors exceeding 100 over 10^5 years, shortening the period for radiotoxicity to approach levels from millions to hundreds of years. France's PUREX-based reprocessing at , operational since 1966, exemplifies empirical closure of the uranium-plutonium cycle, recycling 96% of spent and vitrifying residual with MA partitioning R&D yielding 80-90% radiotoxicity cuts over 300-500 years in advanced variants. This avoids accumulation of "infinite" by recycling fissile materials and targeting MAs for , with no evidence of unbounded volume growth in three decades of operation. ![Plutonium and uranium extraction from nuclear fuel-eng.svg.png][float-right] Challenges in P&T include minor actinide handling due to high (e.g., curium-242 of 163 days) and economy losses from parasitic captures, necessitating >10% MA doping limits in fuels to maintain criticality. Ongoing trials, such as Europe's ADS prototype targeting 50 MWth by 2030, validate these approaches for commercial scalability.

Controversies and Risk Assessments

Proliferation Risks vs. Strategic Benefits

The dual-use characteristics of actinide processing technologies, such as uranium enrichment and plutonium reprocessing in the , inherently pose proliferation risks by enabling the production of weapons-grade materials alongside civilian fuel. These risks are addressed through IAEA safeguards, which employ material accountancy, , , and on-site inspections to verify that states fulfill non-proliferation obligations and detect any diversion of declared from peaceful uses with high timeliness. For instance, HEU downblending programs have converted excess weapons-grade into LEU unsuitable for bombs; the U.S. downblended approximately 12.1 metric tons of HEU starting in 2008, while earlier efforts at sites like processed 14.9 metric tons between 2003 and 2011 into LEU for commercial reactors. Strategic benefits of actinide utilization outweigh unmanaged risks when paired with robust verification, particularly in enhancing and . Nuclear propulsion systems powered by enable naval vessels, including U.S. ballistic missile submarines, to achieve near-indefinite submerged endurance and stealth, sustaining strategic deterrence patrols without reliance on vulnerable refueling logistics; this capability has underpinned continuous at-sea deterrence for over 50 years. In civilian contexts, actinide-fueled reactors provide baseload that directly displaces imports, bolstering ; empirical analyses indicate nuclear-intensive grids reduce exposure to and gas supply disruptions, as evidenced by stable electricity mixes in high-nuclear-share nations amid global fossil price volatility. Empirically, proliferation alarms have not materialized into verified diversions under IAEA-monitored programs, despite decades of dual-use operations and predictions of inevitable spread; safeguards have deterred misuse by maximizing detection probabilities, with no confirmed cases of safeguarded being weaponized from peaceful facilities. This track record underscores that while zero-risk scenarios are illusory, targeted measures like additional protocols and export controls render actinide technologies viable for strategic gains without systemic proliferation cascades.

Environmental Claims and Empirical Risk Data

Empirical monitoring data from the Chernobyl accident indicate that actinide releases, primarily plutonium isotopes, were largely confined to the immediate vicinity of the reactor due to their association with refractory particles, resulting in negligible contributions to external doses beyond the 30-km exclusion zone. Post-accident assessments by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) estimate additional annual effective doses from all radionuclides, including actinides, at less than 1 mSv/year in areas outside the zone, comparable to or below natural background levels in many regions. Similarly, at Fukushima Daiichi, transuranic actinides such as plutonium and americium showed limited dispersion, with soil concentrations decreasing rapidly with distance; aerial and ground surveys confirm public doses beyond 30 km remained under 1 mSv/year, dominated by volatile fission products rather than actinides. Groundwater migration models often predict extensive actinide transport, yet field data reveal strong retardation via onto minerals, with distribution coefficients (Kd) exceeding 10^3 mL/g for tetravalent and under typical conditions, limiting mobility to millimeters per year. This is corroborated by site-specific studies at nuclear facilities, where observed actinide plumes advance far slower than diffusive models suggest, due to , complexation, and colloidal filtration. Natural analogs, such as the reactors in operational approximately 2 billion years ago, provide evidence of long-term containment: and fission products, including actinide analogs, remained largely immobilized in host over geological timescales, with migration distances under 100 meters despite . Uranium mining for actinide fuel cycles generates with radiological and , but per unit produced, its environmental footprint aligns with or falls below that of extraction, which produces up to 2,000 tons of toxic waste per ton of rare earth oxide due to acid leaching and radioactive byproducts. Regulated in-situ leaching methods for minimize surface disturbance compared to open-pit rare earth operations, which have caused widespread groundwater acidification in sites like Bayan Obo, . Deployment of nuclear energy has empirically averted substantial : global nuclear generation from 1971 to 2009 prevented an estimated 1.84 million premature deaths from air particulates and 64 gigatonnes of CO2-equivalent emissions, based on displacement of and oil equivalents. These quantified benefits underscore causal trade-offs, where localized actinide risks are offset by broader reductions in combustion-related externalities.

Current Research and Future Prospects

Recent Advances in Actinide Chemistry

In 2025, researchers synthesized a series of isostructural actinide organometallic complexes, An(COTbig)₂ (where An = Th, U, Np, Pu and COTbig denotes the bulky 1,4-bis(triphenylsilyl)cyclooctatetraenide ), enabling direct comparison of electronic structures across the early actinide series. These asymmetric metallocenes revealed trends in 5f orbital participation, with increasing covalency and hybridization from to , as probed by and computational modeling, highlighting deviations from analogs due to relativistic effects and 5f-6d orbital mixing. Synchrotron-based (XAS) advancements have elucidated bonding in high-valent light actinides, such as and compounds, by exploiting sensitivity of 5d pre-edge features to crystal-field splitting and covalency. A 2025 study demonstrated that these pre-edge structures in high-oxidation-state light actinides respond to hybridization effects, providing empirical data on ligand-metal interactions under extreme conditions, with techniques refined at facilities like enhancing resolution for transuranic . Progress in actinide metal-organic frameworks (An-MOFs) has yielded stable porous materials incorporating and nodes, with 2025 reports detailing enhanced hydrolytic resilience and tunable pore architectures via design.00445-X) These frameworks exhibit unique 5f-driven electronic properties, including redox-active sites, distinguishing them from counterparts and enabling precise control over actinide coordination geometries.00445-X) For minor actinides, serial dilution techniques in non-aqueous solvents have facilitated isolation and characterization of and complexes, revealing oxidation-state-dependent coordination preferences and thermodynamic stabilities not accessible via traditional methods. Complementary biogeochemical studies from 2024 quantify environmental of and , integrating microbial reduction-oxidation cycles with speciation modeling to predict mobility in subsurface conditions, underscoring colloid-facilitated transport over aqueous free-ion dominance.

Emerging Applications and Challenges

Advanced nuclear fuels incorporating minor actinides into tristructural-isotropic (TRISO) particles represent a verifiable extension for high-temperature reactors, enabling greater transmutation of long-lived isotopes like and while maintaining integrity under extreme conditions. Experimental designs demonstrate that TRISO variants with minor actinide doping can achieve burnups exceeding 15% heavy metal, with neutronics analyses showing minor actinide inventories increasing by 4.2% to 27.7% over cycles, thereby reducing waste radiotoxicity compared to traditional uranium-plutonium s. Recovery processes for these fuels, however, remain underdeveloped, as current pyroprocessing methods struggle with breaching silicon carbide layers without generating excessive carbon waste. Nuclear thermal propulsion (NTP) systems, fueled by low-enriched uranium actinides, offer propulsion efficiencies with specific impulses around 900 seconds, facilitating reduced transit times to Mars—potentially halving durations relative to chemical propulsion—through direct heating of propellant via fission. Ground testing of NTP prototypes, such as those under NASA's Demonstration Rocket for Agile Operations, confirms thermal output scalability to 100-500 kN levels using actinide ceramics like nitride. Beyond radioisotope thermoelectric generators, which rely on decay for steady power, NTP addresses dynamic needs but requires shielding against neutron-induced activation in components. Fusion-fission hybrid reactors utilize fusion-generated s to drive subcritical fission blankets loaded with minor actinides, achieving transmutation rates up to 90% for isotopes like neptunium-237 and over operational cycles, as modeled in lead-lithium-cooled designs. These systems lower the neutron economy demands on fusion components while fissioning actinides at rates exceeding standalone fast reactors, with scoping studies indicating self-sustaining breeding ratios above 1.05. Empirical simulations project hybrid multiplication factors of 10-30, prioritizing actinide over net power generation. Key challenges include relativistic effects in quantum modeling of actinide bonding, where scalar-relativistic corrections are essential for accurate prediction of covalency in complexes like and cyclopentadienyls, as deviations without them exceed 0.1 e in orbital populations. Handling costs escalate due to requirements for glovebox-scale separations and remote fabrication, with actinide facilities incurring up to 20-30% higher capital expenses than light-water cycles owing to radiolytic degradation and criticality controls. Scalability is further impeded by the need for advanced pyrochemical partitioning to isolate minor actinides at purities above 99%, amid empirical data showing incomplete transmutation in prototypes due to mismatches.

References

  1. Dec 8, 2021 · Uranium and thorium, the first actinides discovered and the most abundant on earth, found initial use in nuclear weapons and nuclear reactors.
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