Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl

被引：59

作者：

Chen, Shengli ^{[1
]}

Yuan, Cenxi ^{[1
]}

机构：

[1] Sun Yat Sen Univ, Sinofrench Inst Nucl Engn & Technol, Zhuhai 519082, Guangdong, Peoples R China

来源：

SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS | 2017年 / 2017卷

基金：

中国国家自然科学基金;

关键词：

NORMAL OPERATION; PERFORMANCE; ALLOYS;

D O I：

10.1155/2017/3146985

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Neutronic performance is investigated for a potential accident tolerant fuel (ATF), which consists of U3Si2 fuel and FeCrAl cladding. In comparison with current UO2-Zr system, FeCrAl has a better oxidation resistance but a larger thermal neutron absorption cross section. U3Si2 has a higher thermal conductivity and a higher uranium density, which can compensate the reactivity suppressed by FeCrAl. Based on neutronic investigations, a possible U3Si2-FeCrAl fuel-cladding system is taken into consideration. Fundamental properties of the suggested fuel-cladding combination are investigated in a fuel assembly. These properties include moderator and fuel temperature coefficients, control rods worth, radial power distribution (in a fuel rod), and different void reactivity coefficients. The present work proves that the new combination has less reactivity variation during its service lifetime. Although, compared with the current system, it has a little larger deviation on power distribution and a little less negative temperature coefficient and void reactivity coefficient and its control rods worth is less important, variations of these parameters are less important during the service lifetime of fuel. Hence, U3Si2-FeCrAl system is a potential ATF candidate from a neutronic view.

引用

页数：12

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