Study on Neutronic/Thermal-Mechanical Coupling Calculation Method for Fast-neutron Pulse Reactor with Metallic Nuclear Fuel

被引：0

作者：

Guo S. ^{[1
,2
]}

Chen Z. ^{[1
]}

Jiang X. ^{[2
]}

Li D. ^{[2
]}

Zhang X. ^{[2
]}

Wang L. ^{[2
]}

Hu T. ^{[2
]}

Xie J. ^{[1
]}

Yu T. ^{[1
]}

机构：

[1] School of Nuclear Science and Technology, University of South China, Hunan, Hengyang

[2] Northwest Institute of Nuclear Technology State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Xi’an

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2022年 / 43卷 / 04期

关键词：

ANSYS; Neutronic/thermal-mechanical coupling; Pulse reactor; Transient analysis;

D O I：

10.13832/j.jnpe.2022.04.0031

中图分类号：

学科分类号：

摘要：

In order to ensure the operational safety of the fast-neutron pulse reactor and prevent the supercritical pulse from causing physical damage to the material, it is necessary to simulate and analyze the pulse operating conditions of the fast-neutron pulse reactor. In this study, for the fast-neutron pulse reactor with metallic nuclear fuel, the neutronic/thermal-mechanical coupling calculation and analysis of Godiva-I pulse reactor are carried out based on the point reactor dynamics method, Monte Carlo method and finite element mechanics method. The calculation results show that the reactivity temperature coefficient and fission rate are in good agreement with the experimental values, and the reactivity, temperature rise, surface displacement and surface stress are consistent with the actual situation. Therefore, the "neutronic/thermal-mechanical" coupling calculation method established in this paper can be applied to the analysis and calculation of the fast-neutron pulse reactor with metallic nuclear fuel, and has certain reliability. © 2022 Yuan Zi Neng Chuban She. All rights reserved.

引用

页码：31 / 37

页数：6

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