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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.11
- 수록면
- 2,415 - 2,421 (7page)
- DOI
- https://doi.org/10.1016/j.net.2020.04.015
이용수
초록· 키워드
오류제보하기
The axial heterogeneous void distribution in a fuel channel is a relevant and important issue duringnuclear reactor analysis for LWR, especially for boiling water channel-type reactors. Variation of thecoolant density in fuel channel has an effect on the neutron spectrum that will in turn have an impact onthe values of absolute reactivity, the void reactivity coefficient, and the fuel isotopic compositions duringirradiation. This effect is referring to as the history effect in light water reactor calculations. As the voidreactivity effect is positive in RBMK type reactors, the underestimation of water density heterogeneity in3D reactor core numerical calculations could cause an uncertainty during assessment of safe operation ofnuclear reactor. Thus, this issue is analysed with different cross-section libraries which were generatedwith WIMS8 code at different reference water densities. The libraries were applied in single fuel model ofthe nodal code of QUABOX-CUBBOX/HYCA. The thermohydraulic part of HYCA allowed to simulate axialwater distribution along fuel assembly model and to estimate water density history effect for RBMK typefuel
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참고문헌 (13)
참고문헌 신청
Y. Maruyama / 2006 / Single rod experiments on transient void behavior during low-pressure reactivity-initiated accidents in light water reactors / Nucl. Eng. Des 236:1693~1700
2010 / Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors vol. 1654 / IAEA-TECDOC
K. Almenas / 1500 / Ignalina RBMK-1500. A Source Book. Extended and Updated Version / Lithuanian Energy Institute
M. Fratoni / 2009 / Neutronic design of hydride fueled BWRs / Nucl. Eng. Des 239:1531~1543
2018 / Nuclear Power Reactors in the world / IAEA AEA-RDS-2/38
2010 / Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors vol. 1654 / IAEA-TECDOC
K. Almenas / 1500 / Ignalina RBMK-1500. A Source Book. Extended and Updated Version / Lithuanian Energy Institute
M. Fratoni / 2009 / Neutronic design of hydride fueled BWRs / Nucl. Eng. Des 239:1531~1543
2018 / Nuclear Power Reactors in the world / IAEA AEA-RDS-2/38
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