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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2019.1
- 수록면
- 943 - 948 (6page)
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초록· 키워드
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In this study, investigation of spent fuel was performed using six group delayed neutron parameters. Three used fuels (F1, F2, and F11) which are burnt over the years in the core of Missouri University ofScience and Technology Reactor (MSTR), were investigated. F16 fresh fuel was used as plutonium freefuel element and compared with irradiated used fuels to develop burnup and Pu discrimination method. The fast fission factor of the MSTR was calculated to be 1.071 which was used for burnup calculations. Burnup values of F2 and F11 fuel elements were estimated to be 1.98 g and 2.7 g, respectively. 239Puconversion was calculated to be 0.36 g and 0.50 g for F2 and F11 elements, respectively
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참고문헌 (16)
참고문헌 신청
M. L. Dennis / 2010 / Feasibility of 106Ru peak measurement for MOX fuel burnup analysis / Nucl. Eng. Des 240:3687~3696
K. A. Jordan / 2011 / A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel / Nucl. Instrum. Methods Phys. Res., Sect. A 634:91~100
C. Willman / 2006 / A nondestructive method for discriminating MOX fuel from LEU fuel for safeguards purpose / Ann. Nucl. Energy 33:766~773
S. Zhao / 2018 / One candidate method based on short-lived indicator for burnup analysis, Applied Radiation and Isotopes / Appl. Radiat. Isot 139:274~278
M. Å. Lindell / 2018 / Discrimination of irradiated MOX fuel from UOX fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes / Nucl. Instrum. Methods Phys. Res. A 885:67~78
K. A. Jordan / 2011 / A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel / Nucl. Instrum. Methods Phys. Res., Sect. A 634:91~100
C. Willman / 2006 / A nondestructive method for discriminating MOX fuel from LEU fuel for safeguards purpose / Ann. Nucl. Energy 33:766~773
S. Zhao / 2018 / One candidate method based on short-lived indicator for burnup analysis, Applied Radiation and Isotopes / Appl. Radiat. Isot 139:274~278
M. Å. Lindell / 2018 / Discrimination of irradiated MOX fuel from UOX fuel by multivariate statistical analysis of simulated activities of gamma-emitting isotopes / Nucl. Instrum. Methods Phys. Res. A 885:67~78
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