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Neutron and Thermal Embrittlement of RPV Steels: An Overview

机译:RPV钢的中子和热脆化: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:由于反应堆压力容器(RPV)代表了防止向公众释放辐射的第一道结构防线,因此,任何核反应堆设施的RPV的设计和制造都必须按照非常高的标准,并依据用来建造容器的钢材的机械和物理性能核RPV可重达800吨,壁厚可达330毫米,并在内部包裹不锈钢焊接金属,并进行最终的焊后热处理。 RPV是一种独特的结构组件,因为它在高压和高温下运行,并暴露于相对较高的中子辐射下。尽管典型的RPV钢和焊缝在投入使用时在室温及更高温度下均具有出色的断裂韧性,但高能中子辐照的降解作用可能导致辐射敏感材料中辐照引起的脆化程度,这是由于其结构完整性而引起的。 RPV。近几十年来,在发展对辐照脆化的机械理解方面已经取得了显着进展。这项进展包括根据RPV监视程序的结果,再加上在测试反应堆中进行的综合研究实验得出的重要结果,开发基于物理和统计校准的夏比V型缺口索引的过渡温度变化模型。另外,弹塑性断裂力学的进步允许相对少量的相对较小的试样以统计学上的可信度表征RPV钢的断裂韧性。本文概述了主要的机械性能,测试程序,适用规范和标准的示例以及用于表征RPV钢和焊缝的样品类型,中子辐照对那些最相关的机械性能的影响以及对这些性能的简要概述。热老化对RPV材料的影响。本文以总结结尾。

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