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新型热管反应堆堆芯热工安全分析

张文文 王成龙 田文喜 秋穗正 苏光辉 赵小林 刘汉刚

原子能科学技术2017,Vol.51Issue(5):822-827,6.
原子能科学技术2017,Vol.51Issue(5):822-827,6.DOI:10.7538/yzk.2017.51.05.0822

新型热管反应堆堆芯热工安全分析

Thermal Safety Analysis of New Type Heat Pipe Reactor Core

张文文 1王成龙 1田文喜 1秋穗正 1苏光辉 1赵小林 2刘汉刚2

作者信息

  • 1. 西安交通大学 核科学与技术学院,陕西 西安 710049
  • 2. 中国工程物理研究院,四川 绵阳 621900
  • 折叠

摘要

Abstract

The steady thermal characteristics of the new space heat pipe reactor were analyzed by applying the commercial CFD software FLUENT.According to the power distribution of core obtained by MCNP code calculation and selecting the three adjacent fuel elements with the highest power to analyze, seven normal working conditions with different control drum angles and single heat pipe failure accident condition were calculated and analyzed.The temperature distribution of each layer of the hottest fuel-heat pipe element was obtained.The temperature distribution of steam zone was calculated by the two-dimensional heat pipe analysis program and used as the temperature boundary of the three-dimensional model.The power distribution was added to the fuel by the user defined function (UDF).The results show that the heat pipe has sufficient heat transfer capacity to remove the fission power under the designed value 4.0 MW.Meanwhile, the material temperature of each layer is lower than the safety limits and has large safety margins.The core design meets the requirements.

关键词

热管反应堆/热工分析/数值模拟

Key words

heat pipe reactor/thermal analysis/numerical simulation

分类

能源科技

引用本文复制引用

张文文,王成龙,田文喜,秋穗正,苏光辉,赵小林,刘汉刚..新型热管反应堆堆芯热工安全分析[J].原子能科学技术,2017,51(5):822-827,6.

基金项目

中国工程物理研究院重点基金资助项目 ()

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

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