Thermo-mechanical coupling behavior analysis for a U-10Mo/Al monolithic fuel assembly

被引：5

作者：

Mao, Xiaoxiao ^{[1
]}

Jian, Xiaobin ^{[1
]}

Wang, Haoyu ^{[2
]}

Zhang, Jingyu ^{[1
]}

Zhang, Jibin ^{[2
]}

Yan, Feng ^{[1
]}

Wei, Hongyang ^{[1
]}

Ding, Shurong ^{[1
]}

Li, Yuanming ^{[2
]}

机构：

[1] Fudan Univ, Dept Aeronaut & Astronaut, Inst Mech & Computat Engn, Shanghai 200433, Peoples R China

[2] Nucl Power Inst China, Sci & Technol Reactor Syst Design Technol Lab, Chengdu 610213, Peoples R China

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2021年 / 53卷 / 09期

基金：

中国国家自然科学基金;

关键词：

U-10Mo; Al monolithic fuel assembly; Thermo-mechanical coupling; Three-dimensional finite element model; Irradiation swelling; Irradiation creep; PLATE-TYPE FUEL; MECHANICAL-PROPERTIES; IRRADIATION CREEP; EVOLUTION; PERFORMANCE; SIMULATION; NEUTRONICS; MODEL; SIZE;

D O I：

10.1016/j.net.2021.03.003

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：

A typical three-dimensional finite element model for a fuel assembly is established, which is composed of 16 monolithic U-10Mo fuel plates and Al alloy frame. The distribution and evolution results of temperature, displacement and stresses/strains in all the parts are numerically obtained and analyzed with a self-developed code of FUELTM. The simulation results indicate that (1) the out-of-plane displacements of Al alloy side plates are mainly attributed to the bending deformations; (2) enhanced out of-plane displacements appear in fuel plates adjacent to the outside Al plates, which results from the occurred bending deformations due to the applied constraints of outside Al plates; (3) an intense interaction of fuel foil with the cladding occurs near the foil edge, which appears more heavily in the fuel plates adjacent to the outside Al plates. The maximum first principal stresses in the fuel foil are similar for all the fuel plates and appear near the fuel foil edge; while, the through-thickness creep strains of fuel foil in the fuel plate near the central region of fuel assembly are larger, and the induced creep damage might weaken the fuel skeleton strength and raise the fuel failure risk. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

引用

页码：2937 / 2952

页数：16

共 46 条

[1] A study of reduction in fuel requirement and enhancement of neutron flux in typical MTR type research reactors [J].