...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Nuclear Engineering and Design >Summary report on new regulatory codes and criteria and guidelines: IAEA guidelines for WWER reactor coolant system integrity assessment
【24h】

Summary report on new regulatory codes and criteria and guidelines: IAEA guidelines for WWER reactor coolant system integrity assessment

机译：关于新法规和标准以及准则的摘要报告：IAEA WWER反应堆冷却剂系统完整性评估准则

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

In the frame of the nuclear safety programme to assist the countries of Central and Eastern Europe, the IAEA identified and ranked in total 263 safety issues for WWER-440/230, WWER-440/213 and WWER-1000/320 nuclear power plants, related to both design and operation. In the area of reactor coolant system integrity, 24 safety issues were identified and 15 of them ranked as of high safety significance. These include: reactor pressure-vessel integrity and related aspects, primary and secondary high-energy piping integrity, steam generator integrity and reliability of the non-destructive testing for in-service inspection. In addition to obtaining international consensus on possible solutions to address the safety issues identified and to reviewing completeness of proposed safety improvements, the IAEA initiated development of guidelines to address the issues of highest safety concern. In the area of the reactor coolant system integrity, guidelines for the leak before break concept application, for the pressurized thermal shock analysis and for the in-service inspection systems qualification were developed. Further activities of the IAEA were focused on the implementation of guidelines developed in the Member States concerned. With this objective, a Co-ordinated Research Programme 'Round-robin Exercise on WWER-440 Reactor Pressure Vessel Embrittlement, Annealing and Re-embrittlement', a 'WWER-440/213 Pressurized Thermal Shock Analysis Benchmark Exercise' and a pilot study to implement the qualification approach to a real power plant component have been initiated by the IAEA and are well under way at present. In this paper, an overview of these IAEA activities related to reactor coolant system integrity is provided and the main principles and elements of guidelines developed discussed.
机译：在协助中欧和东欧国家的核安全计划框架内，国际原子能机构确定并排定了WWER-440 / 230，WWER-440 / 213和WWER-1000 / 320核电厂的263个安全问题，与设计和操作有关。在反应堆冷却剂系统完整性方面，确定了24个安全问题，其中15个被列为具有高度安全意义。其中包括：反应堆压力容器的完整性和相关方面，一次和二次高能管道的完整性，蒸汽发生器的完整性以及在役检查的无损检测的可靠性。除了就解决已查明的安全问题的可能解决方案并审查拟议的安全改进的完整性达成国际共识外，国际原子能机构还着手制定准则，以解决最关注的安全问题。在反应堆冷却剂系统的完整性方面，制定了破裂概念应用前的泄漏，加压热冲击分析和运行中检查系统资格的准则。原子能机构的进一步活动集中于执行有关会员国制定的准则。为此目的，开展了一项协调研究计划“ WWER-440反应堆压力容器脆化，退火和再包裹化的轮循演习”，“ WWER-440 / 213加压热冲击分析基准演习”和一项初步研究。原子能机构已经发起了对实际发电厂组件进行资格评定的方法，目前进展顺利。本文对原子能机构与反应堆冷却剂系统完整性有关的这些活动进行了概述，并讨论了制定的主要原则和准则的内容。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2000年第1期|p.93-100|共8页
  • 作者

    Radim Havel;

  • 作者单位
  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号