The computation of displacement damage cross sections of silicon, carbon and silicon carbide for high energy applications

被引:1
|
作者
Saha, Uttiyoarnab [1 ]
Devan, K. [1 ]
机构
[1] Indira Gandhi Ctr Atom Res, Homi Bhabha Natl Inst, Reactor Design Grp, Reactor Neutron Div, Kalpakkam 603102, Tamil Nadu, India
关键词
dpa cross section; damage efficiency; recoil; PKA; lattice displacement energy; sub-lattice interaction; IRRADIATION-INDUCED CRYSTALLINE; SIC SINGLE-CRYSTALS; AMORPHOUS TRANSITION; POLYATOMIC MATERIALS; COMPOSITES; TEMPERATURE; MICROSCOPY; SIMULATION; CASCADES; HELIUM;
D O I
10.1016/j.matpr.2018.06.003
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The polyatomic material SiC is being considered as a potential structural constituent for applications in advanced high temperature nuclear reactors. The radiation damage in these materials due to neutron irradiation requires to be assessed accurately to predict their residence time in these reactors. It is generally quantified by a parameter called displacement per atom (dpa). Knowledge of dpa cross section is essential to compute its dpa rate in a known neutron flux field. Nowadays methods like Monte Carlo and Molecular Dynamics are used to compute dpa cross sections. In fast reactors, the dpa model given by Norgett, Robinson and Torrens (NRT-dpa) is used for design studies. In this paper, we discuss the methodology of computing dpa cross sections of SiC by using the NRT model based dpa cross sections of constituent elements (Si and C) from a more recent evaluated nuclear data library called ENDF/B-VII.1. The contributions of all important partial reactions including radiative capture are considered for the calculation of NRT-dpa by developing an indigenous code. Our results are compared with the published values. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:16501 / 16508
页数:8
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