美国核管会,10 CFR Part 50, Appendix A,核电厂设计总则.docVIP

下载本文档

109
0
约4.47万字
约 21页
2017-05-26 发布于河南
举报
版权申诉

美国核管会,10 CFR Part 50, Appendix A,核电厂设计总则.doc

1、有哪些信誉好的足球投注网站（book118）网站文档一经付费（服务费），不意味着购买了该文档的版权，仅供个人/单位学习、研究之用，不得用于商业用途，未经授权，严禁复制、发行、汇编、翻译或者网络传播等，侵权必究。。
2、本站所有内容均由合作方或网友上传，本站不对文档的完整性、权威性及其观点立场正确性做任何保证或承诺！文档内容仅供研究参考，付费前请自行鉴别。如您付费，意味着您自己接受本站规则且自行承担风险，本站不退款、不进行额外附加服务；查看《如何避免下载的几个坑》。如果您已付费下载过本站文档，您可以点击这里二次下载。
3、如文档侵犯商业秘密、侵犯著作权、侵犯人身权等，请点击“版权申诉”（推荐），也可以打举报电话：400-050-0827(电话支持时间：9:00-18:30)。
4、该文档为VIP文档，如果想要下载，成为VIP会员后，下载免费。
5、成为VIP后，下载本文档将扣除1次下载权益。下载后，不支持退款、换文档。如有疑问请联系我们。
6、成为VIP后，您将拥有八大权益，权益包括：VIP文档下载权益、阅读免打扰、文档格式转换、高级专利检索、专属身份标志、高级客服、多端互通、版权登记。
7、VIP文档为合作方或网友上传，每下载1次，网站将根据用户上传文档的质量评分、类型等，对文档贡献者给予高额补贴、流量扶持。如果你也想贡献VIP文档。上传文档

美国核管会,10 CFR Part 50, Appendix A,核电厂设计总则

美国核管会，10 CFR Part 50, Appendix A，核电厂设计总则 Appendix A to Part 50--General Design Criteria for Nuclear Power Plants Table of Contents Introduction Definitions Nuclear Power Unit Loss of Coolant Accidents Single Failure Anticipated Operational Occurrences CRITERIA ? Number I. Overall Requirements: Quality Standards and Records 1 Design Bases for Protection Against Natural Phenomena 2 Fire Protection 3 Environmental and Dynamic Effects Design Bases 4 Sharing of Structures, Systems, and Components 5 II. Protection by Multiple Fission Product Barriers: Reactor Design 10 Reactor inherent Protection 11 Suppression of Reactor Power Oscillations 12 Instrumentation and Control 13 Reactor Coolant Pressure Boundary 14 Reactor Coolant System Design 15 Containment Design 16 Electric Power Systems 17 Inspection and Testing of Electric Power Systems 18 Control Room 19 III. Protection and Reactivity Control Systems: Protection System Functions 20 Protection System Reliability and Testability 21 Protection System Independence 22 Protection System Failure Modes 23 Separation of Protection and Control Systems 24 Protection System Requirements for Reactivity Control Malfunctions 25 Reactivity Control System Redundancy and Capability 26 Combined Reactivity Control Systems Capability 27 Reactivity Limits 28 Protection Against Anticipated Operational Occurrences 29 IV. Fluid Systems: Quality of Reactor Coolant Pressure Boundary 30 Fracture Prevention of Reactor Coolant Pressure Boundary 31 Inspection of Reactor Coolant Pressure Boundary 32 Reactor Coolant Makeup 33 Residual Heat Removal 34 Emergency Core Cooling 35 Inspection of Emergency Core Cooling System 36 Testing of Emergency Core Cooling System 37 Containment Heat Removal 38 Inspection of Containment Heat Removal System 39 Testing of Containment Heat Removal System 40 Containment Atmosphere Cleanup 41 Inspection of Containment Atmosphere Cleanup Systems 42 Testi