反应堆用典型金属工程材料辐照损伤机理的蒙特卡罗模拟研究
首发时间:2015-05-27
摘要:核反应堆极端辐射环境下核工程材料的安全与可靠性对保障核能产业可持续发展具有重大意义。本文采用蒙特卡罗程序包Geant4建立了反应堆辐照环境下的材料损伤模型,从材料的位移损伤率和杂质沉积等方面研究了CLAM钢、F82H钢、α-Fe三种反应堆用典型金属工程材料分别在中子、质子、重离子轰击下的辐照损伤机理。研究表明:中子对材料的辐照损伤主要为位移损伤;质子和重离子对材料造成的位移损伤呈Bragg峰曲线分布,且损伤区域与粒子射程均集中在材料表层,其中14.67 MeV质子射程为512 μm,0.82 MeV 3He离子射程仅为2.1 μm。本文系统分析了反应堆极端辐照环境下金属工程材料的损伤形成机理,为进一步研究材料受辐照后宏观性能与微观结构变化提供了理论依据。
关键词: 核技术及应用 蒙特卡罗方法 金属工程材料 位移损伤率 杂质沉积
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Monte Carlo simulation research on damage mechanism of typical metal engineering materials in nuclear reactor under irradiation
Abstract:Maintaining the safety and reliability of nuclear engineering materials under a neutron irradiation environment is significant. In this paper, the model of material damage under irradiation of reactor was established using the Monte Carlo package Geant4. The irradiation damage mechanisms of CLAM, F82H and α-Fe under the bombardment of neutrons, protons and heavy ions were studied respectively with the aspects of material displacement damage rate and impurities deposition. The results have shown that irradiation damage caused by neutrons was mainly displacement damage. The distribution of displacement damage caused by protons and heavy ions corresponded to Bragg peak curve, whose incident depth and damage area were concentrated in the surface of material. 14.67 MeV protons had an incident depth of 512 μm while 0.82 MeV 3He ions were 2.1 μm only. The damage forming mechanism of metal engineering materials under extreme irradiation environment was systematically analyzed, which provided a theoretical basis for further research of material changes in macroscopic properties and microstructure after irradiation.
Keywords: nuclear technology and application Monte Carlo method metal engineering materials displacement damage rate impurities deposition
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No.4644489106101214****
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反应堆用典型金属工程材料辐照损伤机理的蒙特卡罗模拟研究
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