金属学报  2011, Vol. 47 Issue (7): 777-783    DOI: 10.3724/SP.J.1037.2011.00265

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核反应堆压力容器的辐照脆化与延寿评估

吕铮

东北大学材料各向异性与织构教育部重点实验室, 沈阳 110819

RADIATION-NDUCED EMBRITTLEMENT AND LIFE EVALUATION OF REACTOR PRESSURE VESSELS

LU Zheng

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

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.
. RADIATION-NDUCED EMBRITTLEMENT AND LIFE EVALUATION OF REACTOR PRESSURE VESSELS[J]. Acta Metall Sin, 2011, 47(7): 777-783.

摘要 参考文献 相关文章 Metrics 全文: PDF(925 KB)   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. 关键词 ： 反应堆压力容器,  辐照损伤,  DBTT升高,  寿命评估     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. Key words： reactor pressure vessel    irradiation damage    DBTT shift    life evaluation 收稿日期: 2011-04-25      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 作者简介: 吕铮, 男, 1970年生, 教授 服务 把本文推荐给朋友 加入引用管理器 E-mail Alert RSS 作者相关文章 吕铮 44.8K 链接本文: https://www.ams.org.cn/CN/10.3724/SP.J.1037.2011.00265      或      https://www.ams.org.cn/CN/Y2011/V47/I7/777 [1] Odette G R, Lucas G E. JOM, 2001; 53: 18 [2] Little E A. Proc EUROMAT 96, Conf Materials and Nuclear Power, London: Institute of Materials, 1996: 29 [3] Nanstad R K, Sokolov M A, McCabe D E. J ASTM Int, 2008; 5: JAI101346 [4] Steele L E. In: Steele L E, ed., Status of USA Nuclear Reactor Pressure Vessel Surveillance for Radiation Effects, ASTM STP 784, Philadelphia, PA: American Society for Testing and Materials, 1983: 277 [5] Wallin K. Eng Fract Mech, 2002; 69: 451 [6] Little E A. 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