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核热推进反应堆燃料元件热工应力安全分析

周之帆 章静 巫英伟 贺亚男 郭凯伦 王明军 苏光辉 秋穗正 田文喜

火箭推进2024,Vol.50Issue(4):83-93,11.
火箭推进2024,Vol.50Issue(4):83-93,11.DOI:10.3969/j.issn.1672-9374.2024.04.008

核热推进反应堆燃料元件热工应力安全分析

Thermal stress safety analysis of nuclear thermal propulsion reactor fuel elements

周之帆 1章静 1巫英伟 1贺亚男 1郭凯伦 1王明军 1苏光辉 1秋穗正 1田文喜1

作者信息

  • 1. 西安交通大学 核科学与技术学院,陕西 西安 710049
  • 折叠

摘要

Abstract

In nuclear thermal propulsion,the very-high-temperature gas-cooled reactor core operates under challenging service conditions including high heat flux,steep power gradients,significant temperature difference,and intense coolant flow erosion.In this environment,there is a risk of structural failure due to stress concentration in the hexagonal fuel elements,which can potentially impact the safety performance of the nuclear reactor fuel elements.To explore the thermal stress behavior and thermal safety boundaries of nuclear thermal propulsion fuel elements,with a focus on NERVA-type nuclear thermal propulsion reactors,a symmetrical model is established using the basic unit of densely packed fuel components inside the reactor,which is conducted for(U,Zr)C graphite-based composite fuel elements within the reactor,under high-temperature,high-flow hydrogen propulsion conditions,evaluating the risk of high-temperature melting and structural failure.The research findings indicate that under the operating conditions of nuclear thermal propulsion reactors,fuel elements experience non-uniform internal heat distribution due to the arrangement of their coolant channels and the cooling effects of connecting pipe elements.The accumulation of radial temperature differences leading to different thermal expansion along the axial direction is the primary cause of structural failure in fuel elements.Combining the analysis of temperature-stress field distribution within the fuel elements and the factors influencing it,this research can provide optimization ideas and guidelines for the safety design of nuclear thermal propulsion systems.

关键词

核热推进/燃料元件/热工应力/流固耦合/安全分析

Key words

nuclear thermal propulsion/fuel element/thermal stress/fluid-structure interaction/safety analysis

分类

能源科技

引用本文复制引用

周之帆,章静,巫英伟,贺亚男,郭凯伦,王明军,苏光辉,秋穗正,田文喜..核热推进反应堆燃料元件热工应力安全分析[J].火箭推进,2024,50(4):83-93,11.

基金项目

中核集团青年英才项目 ()

中国科协青年托举人才工程 ()

火箭推进

OA北大核心CSTPCD

1672-9374

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