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材料在微纳米尺度的环境损伤与核电站关键设备的服役安全性
韩恩厚
2012-11-02
Conference Name第16届全国疲劳与断裂学术会议
Source Publication第16届全国疲劳与断裂学术会议论文集
Conference Date2012-11-02
Conference Place厦门
Abstract核电站的核心部分由反应堆及相关构件组成.目前商用核电站主要采用轻水核反应堆,约占核反应堆总数的85%,分为沸水堆(290℃、8 MPa)和压水堆(PWR,320℃、16-17 MPa)两种.加之重水堆(315℃、9.9 MPa)占8%,全世界约有93%的核电站材料工作在高温高压水中.
description.department中国科学院金属研究所
Funding Organization中国力学学会;中国腐蚀与防护学会;中国机械工程学会;中国航空学会;中国金属学会;中国材料研究学会
Language中文
Document Type会议论文
Identifierhttp://ir.imr.ac.cn/handle/321006/71135
Collection中国科学院金属研究所
Recommended Citation
GB/T 7714
韩恩厚. 材料在微纳米尺度的环境损伤与核电站关键设备的服役安全性[C],2012.
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