Calculation of neutron-induced radiation damage to gold and lutetium-aluminium microstructures using MCNP6.2

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
S.T. Temaugee , L. Bedhesi , R.D. Mavunda , G.C. Daniels , S.H. Connell , I.T. Usman , E. Chinaka
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引用次数: 0

Abstract

Interaction of particles and photons with materials in extreme radiation environments like the nuclear reactor may lead to basic alterations in the microstructural properties of crystalline solids. These changes accumulate over time into defects on the macrostructure translating to changes in the material's physical and mechanical properties. Studying the level of damage in the materials requires a good prediction of damage using statistical approaches like Monte Carlo simulations. This study aims to calculate the level of damage to Gold (Au) and Lutetium-Aluminium (Lu-Al) due to neutron irradiation, owing to the applications of the materials in reactor technology and other extreme radiation environments. Neutron fluxes, displacement per atom (dpa) rates, and heat deposition expected during irradiation were calculated with Monte Carlo N-particle transport code, MCNP6.2, using the SAFARI-1 research reactor model. The total neutron flux incident on gold and Lutetium-Aluminium was 2.26×1011 n cm−2 s−1 and 6.94×1012 n cm−2 s−1 respectively, while the dpa rate in Au and Lu-Al was estimated to be 1.96×107 s−1 and 6.56×105 s−1. The calculated neutron dpa rates and fluence for the materials suggest an elevated level of damage to the microstructure of the materials.

利用MCNP6.2计算中子辐照对金和镥铝微结构的损伤
在核反应堆等极端辐射环境中,粒子和光子与材料的相互作用可能导致晶体固体微观结构特性的基本改变。随着时间的推移,这些变化积累成宏观结构上的缺陷,从而导致材料物理和机械性能的变化。研究材料的损伤程度需要使用像蒙特卡罗模拟这样的统计方法对损伤进行很好的预测。本研究旨在计算中子辐照对金(Au)和镥铝(Lu-Al)的损伤程度,因为这些材料在反应堆技术和其他极端辐射环境中的应用。利用SAFARI-1研究堆模型,利用蒙特卡罗n粒子输运程序MCNP6.2计算辐照过程中中子通量、每原子位移率(dpa)和预期热沉积。金和lutetium -铝的总中子通量分别为2.26×1011 n cm−2 s−1和6.94×1012 n cm−2 s−1,而Au和Lu-Al的dpa速率分别为1.96×10−7 s−1和6.56×10−5 s−1。计算出的中子dpa率和对材料的影响表明对材料微观结构的破坏程度有所提高。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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