摘要: The probability that reactivity feedbacks fail to prevent damage is computed by propagating data and modeling uncertainties through transient calculations, with these uncertainties being constrained by experimental evidence. Scree... 展开
作者 | Schaefer, R. W. | ||
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原报告号 | DE91007211 | 总页数 | 16 |
主办者 | Technical Information Center Oak Ridge Tennessee | ||
报告分类号 | [77H - Reactor Engineering & Nuclear Power Plants77K - Reactor Physics] | ||
报告类别/文献类型 | DE / NTIS科技报告 | ||
关键词 | EBR-2 Reactor Reactor Kinetics Reactor Operation Risk Assessment ANL ATWS After-Heat Removal Blackouts Control Elements Deformation Efficiency Errors Experimental Data Failures Fission Product Release Fuel-Cladding Interactions Loss of Flow Mathematical Models Mitigation Monte Carlo Method Natural Convection P Codes Primary Coolant Circuits Probability Pumps Reactivity Reactor Accidents Reactor Core Disruption Reactor Safety Reliability Response Functions S Codes Sodium Transient Overpower Accidents Transients Meetings Tables(data) EDB/220900 EDB/210500 EDB/220700 Probabilistic estimation |