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DETERMINATION OF BURNUP AND PU/U RATIO OF PWR SPENT FUELS BY GAMMA-RAY SPECTROMETRY
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  • DETERMINATION OF BURNUP AND PU/U RATIO OF PWR SPENT FUELS BY GAMMA-RAY SPECTROMETRY
  • DETERMINATION OF BURNUP AND PU/U RATIO OF PWR SPENT FUELS BY GAMMA-RAY SPECTROMETRY
저자명
Park. Kwang-June,Ju. June-Sik,Kim. Jung-Suk,Shin. Hee-Sung,Chun. Yong-Bum,Kim. Ho-Dong
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2009년|41권 10호|pp.1307-1314 (8 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

The isotope ratio of $^{134}Cs/^{137}Cs$ in a spent PWR fuel sample was obtained with a newly developed gamma/neutron combined measuring system at KAERI. Burnup and Pu/U ratio of the spent fuel sample were determined by using the measured isotope ratio and the burnup-isotope ratio correlation equations calculated from the ORIGEN-ARP computer code. The results were compared and evaluated with the chemically determined burnup and Pu/U ratio. As a result of the comparative evaluation, the nondestructively determined burnup and Pu/U ratio values showed a good agreement with the chemically obtained results to within a 4.5% and 0.8% difference, respectively.