Determination of Tritium in Spent Pressurized Water Reactor (PWR) Fuels

가압 경수로 사용후핵연료 중 삼중수소 분석

  • Lee, Chang Heon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Suh, Moo Yul (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Choi, Kwang Soon (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Jee, Kwang Yong (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute) ;
  • Kim, Won Ho (Nuclear Chemistry Research Team, Korea Atomic Energy Research Institute)
  • 이창헌 (한국원자력연구소, 원자력화학연구부) ;
  • 서무열 (한국원자력연구소, 원자력화학연구부) ;
  • 최광순 (한국원자력연구소, 원자력화학연구부) ;
  • 지광용 (한국원자력연구소, 원자력화학연구부) ;
  • 김원호 (한국원자력연구소, 원자력화학연구부)
  • Received : 2004.06.10
  • Accepted : 2004.09.09
  • Published : 2004.10.25

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 $^{14}C$ and $^3H$ can be sequentially recovered from a single fuel sample was optimized using simulated spent PWR fuel dissolved solutions. $^{14}CO_2$ evolved during dissolution of the spent PWR fuels with nitric acid was trapped in an aliquot of 1.5 M NaOH. $^{129}I_2$ which was volatilized along with $^{14}CO_2$ was removed using a silver nitrate-impregnated silica gel absorbent. $^3H$ remaining in the fuel dissolved solution as $^3H_2O$ 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

Acknowledgement

Supported by : 과학기술부

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