Silicon Carbide Ceramic as Fast Neutron Detector of Fission and Fusion Reactions in Fusion-Fission Hybrid Reactors

被引：2

作者：

Teymoori Sendesi, Seyyed Mahdi ^{[1
]}

Ghasemizad, Abbas ^{[1
]}

Esmaeili, Seyyed Soheil ^{[1
]}

机构：

[1] Univ Guilan, Dept Phys, Fac Sci, Rasht 413351914, Iran

来源：

IRANIAN JOURNAL OF SCIENCE AND TECHNOLOGY TRANSACTION A-SCIENCE | 2021年 / 45卷 / 04期

关键词：

Silicon carbide; Fusion– fission hybrid reactor; MCNPX2; 7; 0; RESOLUTION; PROGRESS; DESIGN; SYSTEM;

D O I：

10.1007/s40995-021-01090-8

中图分类号：

O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];

学科分类号：

07 ; 0710 ; 09 ;

摘要：

Fast neutron (flow) response measurement with silicon carbide (SiC) is investigated in a typical fusion-fission hybrid reactor, using the most current Monte Carlo transport code (MCNPX2.7.0). Silicon carbide is used as the clad of the fissile fuel assemblies. The elastic scattering of Si-28(n,p)(28)A1, Si-28(n,alpha)Mg-25, C-12(n,alpha)Be-9, C-12(n,n ')3 alpha, Si-28(n, n ')Si-28, and C-12(n,n ')C-12 was calculated, and the results were validated using ENDF reaction cross sections. The results showed that the SiC layer of fuel assembly can be used as a detector for proton, alpha, and elastic scattering in fuel assemblies.

引用

页码：1475 / 1483

页数：9

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