摘要: In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has worked with the NRC to develop information useful to inspectors in the planning and performance of inspections of auxiliary feedw... 展开
| 作者 | B. F. Gore T. V. Vo D. G. Harrison | ||
|---|---|---|---|
| 原报告号 | DE91011331 | 总页数 | 10 |
| 主办者 | Technical Information Center Oak Ridge Tennessee | ||
| 报告分类号 | [77H - Reactor Engineering & Nuclear Power Plants , 97Q - Selected Studies In Nuclear Technology ] | ||
| 报告类别/文献类型 | DE / NTIS科技报告 | ||
| 关键词 | Automation Auxiliary Water Systems EDB/220200 EDB/220900 Failure Mode Analysis Heat Transfer Hydraulics Inspection Loss of Coolant Meetings Nuclear Power Plants Probabilistic Estimation Pumps Reactor Safety Risk Assessment Safety Analysis US NRC Valves | ||
