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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.1
- 수록면
- 415 - 420 (6page)
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초록· 키워드
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A determination method for 237Np in spent nuclear fuel samples was developed using an isotope dilution method with 239Np as a spike. In this method, inductively coupled plasma mass spectrometry (ICP-MS) was taken for the 237Np instead of the previously used alpha spectrometry. 237Np and 239Np were measured by ICP-MS and gamma spectrometry, respectively. The recovery yield of 237Np in synthetic samples was 95.9±9.7% (1S, n=4). The 237Np contents in the spent fuel samples were 0.15,0.25, and 1.06 μg/mgU and these values were compared with those from ORIGEN-2 code. A fairly good agreement between the measurements (m) and calculations (c) was obtained, giving ratios (m/c) of 0.93, 1.12 and 1.25 for the three PWR spent fuel samples with burnups of 16.7, 19.0, and 55.9 GWd/MtU, respectively.
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참고문헌 (17)
참고문헌 신청
C. E. Sanders / 2003 / Isotopic analysis of high-burnup PWR spent fuel samples from the Takahama-3 reactor
Emilio Fuentes / 1999 / Actinide-only burnup credit for pressurized water reactor spent nuclear fuel-II: Validation / Nuclear Technology 125 : 271 ~ 291
G. Rosner / 1993 / Simultaneous radiochemical determination of 237Np and 239Np with 235Np as a tracer, and application to environmental samples / J. Radioanal. and Nucl. Chem
Gauld, I.C. / 2009 / ORIGEN-S: Scale system module to calculate fuel depletion, actinide transmutation, fission product burnup and decay, and associated radiation source terms
J. M. Barrero Moreno / 1997 / Determination of Neptunium and plutonium in the presence of high concentration of uranium by ion chromatographyinductively coupled plasma mass s
Emilio Fuentes / 1999 / Actinide-only burnup credit for pressurized water reactor spent nuclear fuel-II: Validation / Nuclear Technology 125 : 271 ~ 291
G. Rosner / 1993 / Simultaneous radiochemical determination of 237Np and 239Np with 235Np as a tracer, and application to environmental samples / J. Radioanal. and Nucl. Chem
Gauld, I.C. / 2009 / ORIGEN-S: Scale system module to calculate fuel depletion, actinide transmutation, fission product burnup and decay, and associated radiation source terms
J. M. Barrero Moreno / 1997 / Determination of Neptunium and plutonium in the presence of high concentration of uranium by ion chromatographyinductively coupled plasma mass s
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