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Details for article 61 of 74 found articles
| Title: |
Technetium-99m in production and use |
| Author: |
Vučina Jurij Nikolić Nadežda Petrović Đokica |
| Appeared in: |
Nuclear technology & radiation protection |
| Paging: | Volume 24 (2009) nr. 1 pages 68-73 |
| Year: |
2009 |
| Contents: |
Several types of generators have been developed for the production of 99mTc. Due to its excellent performances, the chromatographic type, based on the fission-produced 99Mo sorbed in alumina, is predominant. Technetium-99m is obtained in the form of sodium pertechnetate-99mTc. However, due to the known disadvantages of the production of (n, f)99Mo, attempts are made to avoid uranium fission. The technologies based on (n, g)99Mo (sublimation, extraction, gel) are, with the exception of the gel generator, of limited importance. Certain nuclear reactions in cyclotrons can produce 99Mo (or directly 99mTc) but the obtained results are still not satisfying. Technetium-99m is used in the form of radiopharmaceuticals which are prepared by addition of 99mTc-eluate to the inactive components comprised in the 'cold' kits. The chromatographic (n, f)99Mo/99mTc generator and several 99mTc-radiopharmaceuticals have been developed and are regularly produced in the Vinča Institute of Nuclear Sciences (Laboratory for Radioisotopes). |
| Publisher: |
VINČA Institute of Nuclear Sciences (provided by DOAJ) |
| Source file: |
Elektronische Wetenschappelijke Tijdschriften |
Details for article 61 of 74 found articles
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