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静默式海洋热管堆堆芯三维热力耦合研究 被引量:1

Coupled Three-dimensional Thermal-Mechanical Analysis of Silent Marine Heat Pipe Cooled Reactor
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摘要 热管冷却反应堆的固态堆芯属性使得热管堆的热膨胀效应较为显著,其堆芯传热与结构力学特性耦合的特点与传统堆芯存在较大差异。为针对静默式海洋热管冷却反应堆NUclear Silence ThermoElectric Reactor(NUSTER)的堆芯设计方案进行优化和安全评估,研究采用完全热力耦合的分析方法,应用有限元分析软件ABAQUS针对NUSTER堆芯功率密度最高的发热单元开展热、力学及安全特性分析。结果表明堆芯组件间气隙等参数设计对堆芯温度、应力场有较大影响;与本文提出的热管堆堆芯安全限值相比,NUSTER堆芯设计的热、力学特征参数均具有较大安全裕量。 The solid core of the heat pipe cooled reactor(HPR)makes the thermal expansion effect significant.The coupling characteristics of the heat transfer and structural mechanical behavior are different between the HPR and traditional reactor cores.In order to optimize and evaluate the core design of the silent marine heat pipe cooled reactor called NUclear Silence ThermoElectric Reactor(NUSTER),a fully thermal-mechanical coupling was used to conduct thermal-stress and safety analysis on the hot channel with highest power density,chosen from the NUSTER core design,using finite element software ABAQUS.It can be found that the air gap between the core components has a great influence on the temperature and stress distribution.Large safety margin is left for the thermal-mechanical parameters of the NUSTER reactor core,compared to the HPR reactor core safety limits proposed in this paper.
作者 刘博 高新力 刘利民 丛腾龙 肖瑶 顾汉洋 LIU Bo;GAO Xinli;LIU Limin;CONG Tenglong;XIAO Yao;GU Hanyang(School of Nuclear Science and engineering,Shanghai Jiao Tong University,Shanghai 200240,China;Nuclear and Radiation Safety Center,Ministry of Environmental Protection,Beijing 102488,China)
出处 《核科学与工程》 CAS CSCD 北大核心 2022年第5期1222-1233,共12页 Nuclear Science and Engineering
基金 国家重点研发计划资助(2019YFB190110) “未来能源计划联合科研基金-先进固态热管堆关键分析软件研发及试验研究” 中国船舶集团-上海交通大学海洋装备前瞻创新联合基金资助项目。
关键词 热管冷却反应堆 热力耦合分析 安全评估 Heat pipe cooled reactor Thermal-mechanical coupling analysis Core safety assessment
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