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Annealing and Re-embrittlement of Reactor Pressure Vessel Materials - State of the Art Report

机译:反应堆压力容器材料的退火和再包裹化-最新技术报告

摘要

Annealing of a reactor pressure vessel embrittled by neutron irradiation constitutes the only known technique to restore the initial material properties, to an extent that depends on the annealing conditions and on the materials. This technique is used in WWER-440 type reactor pressure vessels. A very important related issue is the one of re-embrittlement behaviour of the material after the annealing. In this respect, there is an obvious link with radiation embrittlement understanding. This report compiles the vast amount of information on annealing and re-embrittlement, which is available in the European countries where such annealing operations have been performed. In addition this topic was also investigated in various TACIS-PHARE projects, and the conclusions are included here as well. To complete the state-of-the-art, the results from a number of annealing experiments carried out in US on Western type RPV steels have also been considered.
机译:被中子辐照脆化的反应堆压力容器的退火是恢复初始材料性能的唯一已知技术,其恢复程度取决于退火条件和材料。该技术用于WWER-440型反应堆压力容器。一个非常重要的相关问题是退火后材料的重新包裹行为。在这方面,与辐射脆性的理解有明显的联系。该报告汇编了有关退火和再编织的大量信息,在进行了这种退火操作的欧洲国家中可以找到这些信息。此外,在各个TACIS-PHARE项目中也对此主题进行了研究,结论也包括在这里。为了完成最新技术,还考虑了在美国对西方RPV钢进行的许多退火实验的结果。

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