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首页> 外文会议>2002 ASME Pressure Vessels and Piping Conference, Aug 5-9, 2002, Vancouver, British Columbia, Canada >AGE-RELATED DEGRADATION OF STEAM GENERATOR INTERNALS BASED ON INDUSTRY RESPONSES TO GENERIC LETTER 97-06
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AGE-RELATED DEGRADATION OF STEAM GENERATOR INTERNALS BASED ON INDUSTRY RESPONSES TO GENERIC LETTER 97-06

机译：基于通用字母97-06的行业响应的蒸汽发生器内部的年龄相关降解

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This paper presents the results of an aging assessment of the nuclear power industry's responses to NRC Generic Letter 97-06 on the degradation of steam generator internals experienced at Electricite de Fiance (EdF) plants in France and at a United States pressurized water reactor (PWR). Westinghouse (W), Combustion Engineering (CE), and Babcock & Wilcox (B & W) steam generator models, currently in service at U.S. nuclear power plants, potentially could experience degradation similar to that found at EdF plants and the U.S. plant. The steam generators in many of the U.S. PWRs have been replaced with steam generators with improved designs and materials. These replacement steam generators have been manufactured in the U.S. and abroad. During this assessment, each of the three owners groups (W, CE, and B&W) identified for its steam generator models all the potential internal components that are vulnerable to degradation while in service. Each owners group developed inspection and monitoring guidance and recommendations for its particular steam generator models. The Nuclear Energy Institute incorporated in NEI 97-06, "Steam Generator Program Guidelines," a requirement to monitor secondary side steam generator components if their failure could prevent the steam generator from fulfilling its intended safety-related function. Licensees indicated that they implemented or planned to implement, as appropriate for their steam generators, their owners group recommendations to address the long-term effects of the potential degradation mechanisms associated with the steam generator internals.
机译：本文介绍了对法国电力公司（EdF）电厂和美国压水堆（PWR）发生的蒸汽发生器内部组件退化所产生的核电行业对NRC通用信函97-06的响应进行的老化评估结果。 ）。目前在美国核电厂运行的西屋（W），燃烧工程（CE）和巴布科克与威尔科克斯（B＆W）蒸汽发生器型号可能会经历与EdF工厂和美国工厂相似的降解。美国许多压水堆中的蒸汽发生器已被设计和材料得到改进的蒸汽发生器所取代。这些替代的蒸汽发生器已经在美国和国外制造。在评估过程中，三个所有者组（W，CE和B＆W）为其蒸汽发生器模型确定了所有潜在的内部组件，这些组件在使用中容易退化。每个所有者小组都针对其特定的蒸汽发生器型号制定了检查和监控指南以及建议。核能研究所纳入NEI 97-06，“蒸汽发生器计划指南”，该要求监视次级侧蒸汽发生器组件，如果它们的故障可能阻止蒸汽发生器履行其预期的安全相关功能。被许可人表示，他们已实施或计划实施适合其蒸汽发生器的所有者建议，以解决与蒸汽发生器内部相关的潜在降解机制的长期影响。

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