Determination of14C in spent moderator ion-exchange resin from Bruce Nuclear Generating Station A
| Autor: | J. D. Chen, D. C. Doern, D. L. Moir, D. L. Hoffman, W. A. Boivin, A. W. Tarr, K. J. Ross, E. L. Bialas, J. P. M. Ross |
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| Rok vydání: | 1994 |
| Předmět: |
Radionuclide
Fission products Chemistry Health Toxicology and Mutagenesis Radiochemistry technology industry and agriculture Public Health Environmental and Occupational Health Radioactive waste chemistry.chemical_element Fraction (chemistry) Uranium Pollution Analytical Chemistry Coolant Nuclear Energy and Engineering Deuterium Radiology Nuclear Medicine and imaging Ion-exchange resin Spectroscopy |
| Zdroj: | Journal of Radioanalytical and Nuclear Chemistry Articles. 185:69-81 |
| ISSN: | 1588-2780 0236-5731 |
| DOI: | 10.1007/bf02042953 |
| Popis: | Spent ion-exchange resins are produced in the purification of coolant and moderator systems during the normal operation of CANDU (Canada deuterium uranium) nuclear reactors. Carbon-14 is a radionuclide of concern in disposal of ion-exchange resins because of its relatively long half-life, its potential high mobility and its ability to be easily incorporated into organisms. Only limited data are presently available on the14C concentrations of spent from CANDU reactors. To establish a more comprehensive datahase for this radionuclide, concentrations of14C were determined for two moderator resins from Bruce Nuclear Generating Station A. Mixed bed resins were separated into anion and cation fractions using a sugar solution, and the14C concentrations were determined for each fraction. Carbon-14-was located predominantly on the anion beads. Samples of anion resin were found to undergo an 81% loss in the14C concentration over a period of 160 d following the sugar separation procedure. Some evidence is given to suggest this loss in14C may result from microbial activity. Concentrations and distributions of other predominant radionuclides, such as60Co and153Gd, are discussed as well. |
| Databáze: | OpenAIRE |
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