A historical review of WWER RPV embrittlement issues

M. Brumovsky, V. Nikolaev
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Abstract

The paper tries to describe the history of the radiation effects study in WWER type reactor pressure vessels – from their design, manufacturing and operation point of view. The paper shows the time evolution and also institutions that were and are included in this research and development study. Main effort has been concentrated on development and realisation of steels and welding joint with low susceptibility to radiation damage as neutron fluences on reactor pressure wall in WWER type reactors are relatively high.
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二战期间RPV脆化问题的历史回顾
本文试图从WWER型反应堆压力容器的设计、制造和运行的角度描述其辐射效应研究的历史。本文介绍了这一研究与发展研究的时间演变,以及过去和现在所包括的机构。由于WWER型反应堆压力壁上的中子影响比较大,因此主要致力于开发和实现低辐射损伤敏感性的钢材和焊接接头。
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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