Knowledge survey based on published works in the area of WWER reactor pressure vessel steels microstructure

V. Slugen
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引用次数: 0

Abstract

The effects of intensive fluxes of neutrons, thermal ageing or other external factors result in considerable changes of material microstructures and properties. In particular, the development of the fine scale radiation-induced defects which impede the dislocation motion under the applied stress, known as the irradiation embrittlement, leads to mechanical properties degradation which can results to the partial loss of plasticity and to the increase of brittle fracture. Defects are formed from vacancies and interstitials created in collision cascaded processes. With the aim to reveal processes connected to WWER pressure vessel steel degradation, the importance of experimental microstructural studies was accented in many comprehensive works during the last 40 years. Many of these investigations resulted in valuable findings used worldwide. This paper is focused on the survey of knowledge extracted from relevant papers in area WWER steel microstructure selected by group of experts in frame of EC framework projects 'Nuclear Knowledge Preservation & Consolidation' coordinated by JRC Petten.
基于WWER反应堆压力容器钢微观结构领域已发表著作的知识调查
中子强通量、热老化或其他外部因素的影响会导致材料的微观结构和性能发生相当大的变化。特别是,在外加应力作用下,细小尺度的辐射缺陷阻碍了位错的运动,即辐照脆化的发展,导致力学性能退化,从而导致塑性的部分丧失和脆性断裂的增加。缺陷是由碰撞级联过程中产生的空位和间隙形成的。为了揭示与WWER压力容器钢降解有关的过程,在过去的40年里,许多综合研究都强调了实验微观结构研究的重要性。其中许多调查产生了在世界范围内使用的有价值的发现。本文的重点是在JRC Petten协调的EC框架项目“核知识保存与巩固”框架下,由专家组从WWER钢微观结构领域的相关论文中提取的知识的调查。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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