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Pertechnetate
The pertechnetate ion (/pərˈtɛknəteɪt/) is an oxyanion with the chemical formula TcO−
4. It is often used as a convenient water-soluble source of isotopes of the radioactive element technetium (Tc). In particular it is used to carry the 99mTc isotope (half-life 6 hours) which is commonly used in nuclear medicine in several nuclear scanning procedures.
Pertechnetate is poorly hydrated as [TcO4(H2O)n]− and [TcO4(H2O)n-m]−[H3O]+m (n = 1–50, m = 1–4) clusters that have been demonstrated by simulation with DFT. First hydration shell of TcO4− is asymmetric and contains no more than 7 water molecules. Only three of the four oxygen atoms of TcO4− form hydrogen bonds with water molecules.
A technetate(VII) salt is a compound containing this ion. Pertechnetate compounds are salts of technetic(VII) acid. Pertechnetate is analogous to permanganate but it has little oxidizing power. Pertechnetate has higher oxidation power than perrhenate.
Understanding pertechnetate is important in understanding technetium contamination in the environment and in nuclear waste management.
TcO−
4 is the starting material for most of the chemistry of technetium. Pertechnetate salts are usually colorless. TcO−
4 is produced by oxidizing technetium with nitric acid or with hydrogen peroxide. The pertechnetate anion is similar to the permanganate anion but is a weaker oxidizing agent. It is tetrahedral and diamagnetic. The standard electrode potential for TcO−
4/TcO
2 is only +0.738 V in acidic solution, as compared to +1.695 V for MnO−
4/MnO
2. Because of its diminished oxidizing power, TcO−
4 is stable in alkaline solution. TcO−
4 is more similar to ReO−
4. Depending on the reducing agent, TcO−
4 can be converted to derivatives containing Tc(VI), Tc(V), and Tc(IV). In the absence of strong complexing ligands, TcO−
4 is reduced to a +4 oxidation state via the formation of TcO
2 hydrate.
Some metals like actinides, barium, scandium, yttrium or zirconium may form complex salts with pertechnetate thus strongly effecting its liquid-liquid extraction behavior.
99m
Tc is conveniently available in high radionuclidic purity from molybdenum-99, which decays with 87% probability to 99m
Tc. The subsequent decay of 99m
Tc leads to either 99
Tc or 99
Ru. 99
Mo can be produced in a nuclear reactor via irradiation of either molybdenum-98 or naturally occurring molybdenum with thermal neutrons, but this is not the method currently in use today. Currently, 99
Mo is recovered as a product of the nuclear fission reaction of 235
U, separated from other fission products via a multistep process and loaded onto a column of alumina that forms the core of a 99
Mo/99m
Tc radioisotope generator.
As the 99
Mo continuously decays to 99m
Tc, the 99m
Tc can be removed periodically (usually daily) by flushing a saline solution (0.15 M NaCl in water) through the alumina column: the more highly charged 99
MoO2−
4 is retained on the column, where it continues to undergo radioactive decay, while the medically useful radioisotope 99m
TcO−
4 is eluted in the saline. The eluate from the column must be sterile and pyrogen free, so that the Tc drug can be used directly, usually within 12 hours of elution. In a few cases, sublimation or solvent extraction may be used.
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Pertechnetate AI simulator
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Pertechnetate
The pertechnetate ion (/pərˈtɛknəteɪt/) is an oxyanion with the chemical formula TcO−
4. It is often used as a convenient water-soluble source of isotopes of the radioactive element technetium (Tc). In particular it is used to carry the 99mTc isotope (half-life 6 hours) which is commonly used in nuclear medicine in several nuclear scanning procedures.
Pertechnetate is poorly hydrated as [TcO4(H2O)n]− and [TcO4(H2O)n-m]−[H3O]+m (n = 1–50, m = 1–4) clusters that have been demonstrated by simulation with DFT. First hydration shell of TcO4− is asymmetric and contains no more than 7 water molecules. Only three of the four oxygen atoms of TcO4− form hydrogen bonds with water molecules.
A technetate(VII) salt is a compound containing this ion. Pertechnetate compounds are salts of technetic(VII) acid. Pertechnetate is analogous to permanganate but it has little oxidizing power. Pertechnetate has higher oxidation power than perrhenate.
Understanding pertechnetate is important in understanding technetium contamination in the environment and in nuclear waste management.
TcO−
4 is the starting material for most of the chemistry of technetium. Pertechnetate salts are usually colorless. TcO−
4 is produced by oxidizing technetium with nitric acid or with hydrogen peroxide. The pertechnetate anion is similar to the permanganate anion but is a weaker oxidizing agent. It is tetrahedral and diamagnetic. The standard electrode potential for TcO−
4/TcO
2 is only +0.738 V in acidic solution, as compared to +1.695 V for MnO−
4/MnO
2. Because of its diminished oxidizing power, TcO−
4 is stable in alkaline solution. TcO−
4 is more similar to ReO−
4. Depending on the reducing agent, TcO−
4 can be converted to derivatives containing Tc(VI), Tc(V), and Tc(IV). In the absence of strong complexing ligands, TcO−
4 is reduced to a +4 oxidation state via the formation of TcO
2 hydrate.
Some metals like actinides, barium, scandium, yttrium or zirconium may form complex salts with pertechnetate thus strongly effecting its liquid-liquid extraction behavior.
99m
Tc is conveniently available in high radionuclidic purity from molybdenum-99, which decays with 87% probability to 99m
Tc. The subsequent decay of 99m
Tc leads to either 99
Tc or 99
Ru. 99
Mo can be produced in a nuclear reactor via irradiation of either molybdenum-98 or naturally occurring molybdenum with thermal neutrons, but this is not the method currently in use today. Currently, 99
Mo is recovered as a product of the nuclear fission reaction of 235
U, separated from other fission products via a multistep process and loaded onto a column of alumina that forms the core of a 99
Mo/99m
Tc radioisotope generator.
As the 99
Mo continuously decays to 99m
Tc, the 99m
Tc can be removed periodically (usually daily) by flushing a saline solution (0.15 M NaCl in water) through the alumina column: the more highly charged 99
MoO2−
4 is retained on the column, where it continues to undergo radioactive decay, while the medically useful radioisotope 99m
TcO−
4 is eluted in the saline. The eluate from the column must be sterile and pyrogen free, so that the Tc drug can be used directly, usually within 12 hours of elution. In a few cases, sublimation or solvent extraction may be used.