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Why Historical Material Degradation Experience Might Not Represent Future Response

机译:为什么历史物质退化经验可能无法代表未来的反应

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Materials degradation in light water reactors, particularly of primary pressure boundary components, has had a significant effect on capacity factor. Early degradation issues developed within months of operation - such as bulk cold worked stainless steel in boiling water reactors (BWRs) - and were resolved. Subsequent problems tended to develop on a roughly geometric time scale (e.g., 1.5X), so that new generations of issues surfaced after 1.1, 1.7, 2.5, 3.8, 5.7, 8.5... years. In general, each problem resolution created a sense of optimism that all degradation problems were resolved, when in fact most problems were mitigated but not eliminated, and new problems emerged. In 2002, efforts to anticipate degradation were initiated at the Nuclear Regulatory Commission (NRC) and at the Electric Power Research Institute (EPRI) in the form of proactive materials degradation management, which relied on experience and expert judgment. The systematization of the vulnerabilities unfortunately led to steadily diminished research to address the many gaps. Additionally, the roughly geometric timescale between the appearance of new issues has led some to believe that if we haven't seen it yet, it probably won't happen - the same thinking that existed since the inception of light water reactor (LWR) operation. This paper highlights a variety of reasons why historical experience does not provide an adequate basis for anticipating future degradation, and encourages sustained expertise, laboratory capability and plant inspection so that future degradation can be identified and managed. This is especially important as extended lifetimes of 60 -100 years are considered.
机译:轻水反应堆中的材料降解,特别是主要压力边界组件的降解,对容量系数产生了重大影响。在运行的几个月内就出现了早期降解问题,例如沸水反应堆(BWR)中的散装冷加工不锈钢,这些问题已得到解决。随后的问题往往会在大约几何时间尺度上发展(例如1.5倍),因此新一代问题在1.1、1.7、2.5、3.8、5.7、8.5 ...年后浮出水面。通常,每个问题的解决方案都会产生一种乐观的感觉,即解决了所有降级问题,而实际上大多数问题已得到缓解但并未消除,并且出现了新的问题。 2002年,核监管委员会(NRC)和电力研究所(EPRI)采取了主动材料降级管理的形式,以期根据预期的经验和专家的判断来进行预期的降级工作。不幸的是,漏洞的系统化导致针对许多漏洞的研究稳步减少。此外,新问题出现之间的大致几何时间尺度使一些人相信,如果我们还未看到它,那么它很可能不会发生-自从轻水堆(LWR)运行开始以来就存在着同样的想法。 。本文着重介绍了历史经验不能为预期的未来退化提供充分依据的各种原因,并鼓励持续的专业知识,实验室能力和工厂检查,以便可以识别和管理未来的退化。考虑到60 -100年的延长使用寿命,这一点尤其重要。

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