金属核燃料快中子脉冲堆核-热-力耦合计算方法研究  

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

作　　者：郭树伟 陈珍平[1] 江新标[2] 李达[2] 张信一[2] 王立鹏[2] 胡田亮 谢金森[1] 于涛[1] Guo Shuwei;Chen ZhenPing;Jiang Xinbiao;Li Da;Zhang Xinyi;Wang Lipeng;Hu Tianliang;Xie Jinsen;Yu Tao(School of Nuclear Science and Technology,University of South China,Hengyang,Hunan,421001,China;Northwest Institute of Nuclear Technology State Key Laboratory of Intense Pulsed Radiation Simulation and Effect,Xi’an,710024,China)

机构地区：[1]南华大学核科学技术学院,湖南衡阳421001 [2]西北核技术研究所强脉冲辐射环境模拟与效应国家重点实验室,西安710024

出　　处：《核动力工程》2022年第4期31-37,共7页Nuclear Power Engineering

基　　金：湖南省教育厅科学研究项目(19A422);湖南省科技人才托举工程项目(2020TJ-N02)。

摘　　要：为确保快中子脉冲堆的运行安全,防止超临界脉冲对材料造成物理损伤,需要对快中子脉冲堆脉冲工况进行模拟分析。本研究针对金属核燃料快中子脉冲堆,基于点堆动力学方法、蒙特卡罗方法和有限元力学方法,对Godiva-I脉冲堆开展了核热力耦合计算分析研究。计算结果表明,反应性温度系数和裂变率与实验值吻合良好,反应性、温升、表面位移、表面应力与实际情况相符合。因此,本文建立的“核-热-力”耦合计算方法可应用于金属核燃料快中子脉冲堆的分析计算,具有一定的可靠性。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.

关 键 词：脉冲堆 核热力耦合 ANSYS 瞬态分析 

分 类 号：TL364[核科学技术—核技术及应用]