- P-ISSN 1225-0163
- E-ISSN 2288-8985
- P-ISSN1225-0163
- E-ISSN2288-8985
- SCOPUS, ESCI, KCI
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Determination of Tritium in Spent Pressurized Water Reactor (PWR) Fuels
Analytical Science and Technology / Analytical Science and Technology, (P)1225-0163; (E)2288-8985
2004, v.17 no.5, pp.381-387
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(2004). Determination of Tritium in Spent Pressurized Water Reactor (PWR) Fuels. Analytical Science and Technology, 17(5), 381-387.
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Abstract
To characterize chemically a spent pressurized water reactor (PWR) fuel, an analytical method for trace amounts of tritium (3H) in it has been established. Considering the effective management of radioactive wastes generated through the whole experimental process and the radiological safety for analysts, a separation condition under which 14C and 3H can be sequentially recovered from a single fuel sample was optimized using simulated spent PWR fuel dissolved solutions. 14CO2 evolved during dissolution of the spent PWR fuels with nitric acid was trapped in an aliquot of 1.5 M NaOH. 129I2 which was volatilized along with 14CO2 was removed using a silver nitrate-impregnated silica gel absorbent. 3H remaining in the fuel dissolved solution as 3H2O was selectively recovered by distillation. Its recovery yield was 97.9% with a relative standard deviation of 0.9% (n=3). 3H in a spent PWR fuel with burnup value of 37,000 MWd/MtU was analyzed, reliability of this analytical method being evaluated by standard addition method.
- keywords
- Tritium, Spent Pressurized Water Reactor (PWR) Fuels, Liquid scintillation counting
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