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压水反应堆的特殊核环境包括中子辐照和反应堆冷却剂系统的高温加压水。中子辐照引起材料的硬化,同时降低其韧性。对于在一定温度范围内,经历从韧性到脆性断裂转变过程的铁素体材料,这个影响是不能忽视的。本文叙述了辐照脆化机理的计算方法。中子积分通量辐照温度以及钢材的残留元素(铜、砱)的含量是控制韧性恶化程度的主要因素。本文提供了法国对反应堆压力壳铁素体钢环和焊缝所作的实验的最新成果。这些结果与以前报道过的数据极为吻合,设计计算显得保守。反应堆冷却剂系统的高温加压水对疲劳裂纹生长的影响由许多作者对铁素体和奥氏体钢作过调研。这些调研结果在本文中作了介绍。高温一次冷却水对铁素体钢(反应堆压力壳)的疲劳裂纹具有肯定的影响,但对奥氏体钢材(管道、泵、铸件……)则并无重大影响。
Special nuclear environments for pressurized water reactors include high temperature pressurized water for neutron irradiation and reactor coolant systems. Neutron irradiation causes the material to harden while reducing its toughness. This effect can not be ignored for ferritic materials that undergo a transition from ductile to brittle fracture over a range of temperatures. This article describes the calculation of radiation embrittlement mechanism. The flux of neutron flux and the content of residual elements (copper, gallium) in steel are the main factors that control the degree of toughness deterioration. This article provides the latest French research into reactor pressure hull ferritic rings and welds. These results are very consistent with the previously reported data, design calculations appear to be conservative. Effect of High Temperature Pressurized Water on Fatigue Crack Growth in Reactor Coolant Systems Ferrite and austenitic steels have been investigated by many authors. These findings are presented in this article. High temperature primary cooling water has a positive effect on fatigue cracks in ferritic steels (reactor pressure vessels), but has no significant effect on austenitic steels (pipes, pumps, castings ...).