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核反应堆压力容器的辐照脆化与延寿评估

  • 吕铮
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  • 东北大学材料各向异性与织构教育部重点实验室, 沈阳 110819
吕铮, 男, 1970年生, 教授

收稿日期: 2011-04-25

  修回日期: 2011-05-03

  网络出版日期: 2011-07-11

基金资助

国家自然科学基金项目50971033和91026013, 国家重点基础研究发展计划项目2011CB610405, 中央高校基本科研业务费N100402001及教育部新世纪优秀人才支持计划项目NCET-10-0302资助

RADIATION-NDUCED EMBRITTLEMENT AND LIFE EVALUATION OF REACTOR PRESSURE VESSELS

  • LV Zheng
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  • Key Laboratory for Anisotropy and Texture of Materials, Ministry of Education, Northeastern University, Shenyang 110819

Received date: 2011-04-25

  Revised date: 2011-05-03

  Online published: 2011-07-11

Supported by

Supported by National Natural Science Foundation of China (Nos.50971033 and 91026013), National Basic Research Program of China (No.2011CB610405), Fundamental Research Funds for the Central Universities (No.N100402001) and Program for New Century Excellent Talents in University (No.NCET-10-0302)

摘要

核反应堆中辐照导致压力容器钢脆化使韧脆转变温度(DBTT)升高, 从而危及压力容器安全运行, 最终导致反应堆寿命终止. 本文简要介绍了压力容器钢辐照脆化机制、在役反应堆的安全性监测、模拟预测DBTT的升高和反应堆延寿评估.

本文引用格式

吕铮 . 核反应堆压力容器的辐照脆化与延寿评估[J]. 金属学报, 2011 , 47(7) : 777 -783 . DOI: 10.3724/SP.J.1037.2011.00265

Abstract

Neutron irradiation can lead to the embrittlement and the shift of ductile-brittle transition temperature (DBTT) of the reactor pressure vessel (RPV) steels, which is the potential threat to the safe operation of reactors. Surveillance program for RPVs, irradiation damage and embrittlement of RPV steels and safe evaluation of RPVs were reviewed in this paper.

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