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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 975 - 981 (7page)
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초록· 키워드
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The containment response during the first 24 hours of a low-pressure severe accidentscenario in a nuclear power plant with a two-loop Westinghouse-type pressurizedwater reactor was simulated with the CONTAIN 2.0 computer code. The accidentconsidered in this study is a large-break loss-of-coolant accident, which is not successfullymitigated by the action of safety systems. The analysis includes pressure andtemperature responses, as well as investigation into the influence of spray on theretention of fission products and the prevention of hydrogen combustion in thecontainment.
목차
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참고문헌 (9)
참고문헌 신청
F.C. Rahim / 2012 / A study of large break LOCA in the AP1000 reactor containment / Prog. Nucl. Energy 54:132~137
R. Frutos / 2000 / Calculation of fission product behaviour in an advanced containment in case of a severe accident / Nucl. Eng. Des 202:173~178
CONTAIN 2.0 Code Manual / 1997 / A Computer Code for Nuclear Containment Analysis / Prepared for the U.S. Nuclear Regulatory Commission
RELAP5/SCDAP//MOD3.2 Code Manuals / 1997 / A Computer Code for Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During Severe Accidents, Prepared for the U.S. Nuclear Regulatory Commission
Nordostschweizerische Kraftwerke / 2003 / Safety Analysis Report
R. Frutos / 2000 / Calculation of fission product behaviour in an advanced containment in case of a severe accident / Nucl. Eng. Des 202:173~178
CONTAIN 2.0 Code Manual / 1997 / A Computer Code for Nuclear Containment Analysis / Prepared for the U.S. Nuclear Regulatory Commission
RELAP5/SCDAP//MOD3.2 Code Manuals / 1997 / A Computer Code for Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During Severe Accidents, Prepared for the U.S. Nuclear Regulatory Commission
Nordostschweizerische Kraftwerke / 2003 / Safety Analysis Report
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