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Neutron and Thermal Embrittlement of RPV Steels: An Overview

机译:RPV钢的中子和热脆性:概述

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Because the reactor pressure vessel (RPV) represents the first structural line of defense against the release of radiation to the public, the design and fabrication of the RPV for any nuclear reactor facility is performed at very high standards in accordance with consensus codes that are based on mechanical and physical properties of the steels used to construct the vessel. Nuclear RPVs may weigh up to 800 tons with wall thicknesses up to approximately 330 mm and are clad on the inside with stainless-steel weld metal and given a final post-weld heat treatment. The RPV is a unique structural component in that it operates under high pressures and temperatures and is exposed to relatively high neutron radiation. Although typical RPV steels and welds have excellent fracture toughness at room temperature and above when put into service, the degrading effects of high-energy neutron irradiation can cause levels of irradiation-induced embrittlement in radiation-sensitive materials of concern for the structural integrity of the RPV. In recent decades, remarkable progress has been made in developing a mechanistic understanding of irradiation embrittlement. This progress includes developing physically based and statistically calibrated models of Charpy V-notch-indexed transition temperature shifts based on results from RPV surveillance programs complemented by significant results from comprehensive research experiments performed in test reactors. In addition, advances in elastic-plastic fracture mechanics allow for a relatively small number of relatively small specimens to characterize the fracture toughness of RPV steels with statistical confidence. This paper presents a review of the primary mechanical properties, test procedures, examples of applicable codes and standards, and specimen types used to characterize RPV steels and welds, the effects of neutron irradiation on those most relevant mechanical properties, and a brief review of the effects of thermal aging on RPV materials. The paper closes with a summary.
机译:因为反应器压力容器(RPV)代表对公众辐射释放的第一结构线,所以任何核反应堆设施的RPV的设计和制造按照基于的共识代码在非常高的标准下进行关于用于构建容器的钢的机械和物理性质。与壁厚高达约330毫米并包覆上与不锈钢焊接金属的内部和给定的最终焊后热处理核遥控飞行器的重量可高达800吨。 RPV是一种独特的结构部件,使其在高压和温度下操作,并且暴露于相对高的中子辐射。虽然典型的RPV钢和焊缝在室温和以上具有优异的骨折韧性时投入使用时,高能中子辐射的降低效果可引起辐射敏感材料的辐射诱导的脆性水平,这是对结构完整性的关注的辐射敏感性RPV。近几十年来,在制定对辐照脆化的机制理解方面取得了显着进展。该进度包括基于RPV监测程序的结果开发基于物理上和统计校准的转变温度换算,其由RPV监测程序的结果由在测试反应器中进行的综合研究实验中的显着结果辅成。另外,在弹性 - 塑性断裂力学的进步允许相对小数量的相对较小的试样以统计学置信表征RPV钢的断裂韧性。本文介绍了主要的机械性能的评价,测试程序的用于表征RPV钢和焊接,中子照射对那些最相关的机械性能的影响适用的法规和标准,标本类型的例子,和的一个简要回顾热老化对RPV材料的影响。纸质结束了摘要。

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