Analytical Science and Technology (분석과학)

The Korean Society of Analytical Sciences (한국분석과학회)
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Determination of carbon-14 and tritium in a PWR spent nuclear fuel

PWR 사용후핵연료 중 탄소-14 및 트리튬 정량

  • 김정석 (한국원자력연구소 원자력화학연구부) ;
  • 박순달 (한국원자력연구소 원자력화학연구부) ;
  • 이창헌 (한국원자력연구소 원자력화학연구부) ;
  • 송병철 (한국원자력연구소 원자력화학연구부) ;
  • 지광용 (한국원자력연구소 원자력화학연구부)
  • Received : 2005.06.10
  • Accepted : 2005.06.28
  • Published : 2005.08.25
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Abstract

The methods for determining C-14 and tritium contents in the spent nuclear fuel sample were developed. The carbon-14($^{14}CO_2$) released during the dissolution of the spent fuel sample and $CaCO_3$ ($CO_2$ carrier) with 8 M $HNO_3$ at $90^{\circ}C$ was collected in trap containing 1.5 M NaOH. The volatile radioactive iodine evolved when the spent fuel was dissolved, was trapped on to Ag-silicagel (Ag-impregnated silicagel) adsorbent in column which is connected to two NaOH traps. The solutions which contain tritium as HTO after fuel dissolution were decontaminated by deionization with a mixture of cation and anion exchange resins and inorganic ionexchangers. The amount of C-14 in the trap solutions and the HTO concentration in the resulting deionization water were then determined by liquid scintillation counting.

사용후핵연료시료 중에 함유된 탄소-l4와 트리튬을 회수 및 정량하였다. $CO_2$ 운반체($CaCO_3$)를 포함한 사용후핵연료시료를 $90^{\circ}C$에서 8M $HNO_3$ 용액으로 용해하면서 휘발된 $^{14}CO_2$를 1.5 M NaOH 용액을 포함한 포집관에 수집하였다. 용해 중 휘발되는 방사성 요오드는 Ag-silica gel 흡착체를 담은 포집 관으로 사전제거하였다. 핵연료 용해용액 중에 남아있는 트리튬(HTO)를 정량하기 위하여 양이온과 음이온 교환수지 혼합물 및 무기이온교환체를 이용한 뱃치 및 분리관법으로 용해용액을 탈이온화시켜 간섭이온을 제거하였다. 포집용액 중의 탄소-14와 탈이온화수 중의 트리튬을 액체섬광계수법으로 정량하였다.

Keywords

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