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首页> 外文会议>PVP2011;ASME Pressure Vessels and Piping conference >MECHANISTIC INSIGHTS INTO RISK-INFORMED REVISION OF ASME SECTION XI -APPENDIX G
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MECHANISTIC INSIGHTS INTO RISK-INFORMED REVISION OF ASME SECTION XI -APPENDIX G

机译：对ASME第XI节-附录G进行风险管理的修订的机械观点

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摘要

The current regulations, as set forth by the United States Nuclear Regulatory Commission (NRC), to insure that light-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity, throughout their operating life, when subjected to planned normal reactor startup (heat-up) and shutdown (cool-down) transients are specified in Appendix G to 10 CFR Part 50, which incorporates by reference Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Code. The technical basis for these regulations are generally considered to be conservative and some plants are finding it operationally difficult to heat-up and cool-down within the accepted limits. Consequently, the nuclear industry has developed, and submitted to the ASME Code for approval, an alternative risk-informed methodology that reduces the conservatism and is consistent with methods previously used to develop a risk-informed revision to the regulations for accidental transients such as pressurized thermal shock (PTS). The objective of the alternative methodology is to increase operational flexibility while continuing to provide reasonable assurance of adequate protection to public health and safety. The NRC and its contractor at Oak Ridge National Laboratory (ORNL) are reviewing the industry proposed risk-informed methodology. Previous results of this review, have been reported at PVP, and a NRC report summarizing all results is currently in preparation. The objective of this paper is to discuss and illustrate mechanistic insights into trends shown previously associated with normal cool-down.
机译：美国核监管委员会（NRC）制定的现行法规，旨在确保轻水核反应堆压力容器（RPV）在计划中的正常反应堆启动（热）过程中，在其整个使用寿命中保持其结构完整性。 10 CFR第50部分的附录G中指定了升压和停机（冷却）瞬变，该参考文献通过引用纳入了美国机械工程师学会（ASME）法规第XI节的附录G。这些法规的技术基础通常被认为是保守的，一些工厂发现在可接受的范围内进行加热和冷却非常困难。因此，核工业已经开发出另一种风险知情的方法，并已提交ASME规则以供批准，该方法可降低保守性，并与以前用于对意外瞬变法规（如加压法）进行风险知情的修订的方法相一致。热冲击（PTS）。替代方法的目的是在增加运营灵活性的同时，继续为合理保护公众健康和安全提供合理保证。 NRC及其在橡树岭国家实验室（ORNL）的承包商正在审查行业提出的风险知情方法。 PVP已报告了该审查的先前结果，目前正在准备一份NRC报告，其中总结了所有结果。本文的目的是讨论和说明对以前与正常冷却有关的趋势的机械见解。

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