中文版 | English

在结果中检索

IMR OpenIR

浏览/检索结果: 共6条，第1-6条 帮助

已选(0)清除 条数/页：   排序方式：
Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 13
作者:  Lin, Zihao;  Zhang, Ziyu;  Tan, Jibo;  Wu, Xinqiang
收藏  |  浏览/下载：1/0  |  提交时间：2025/04/27
Crud deposition  Fuel cladding tube  Coolant pH  Subcooled nucleate boiling  Solubility  
Effects of coolant pH on crud deposition behavior on fuel cladding tube under subcooled nucleate boiling condition in high temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 13
作者:  Lin, Zihao;  Zhang, Ziyu;  Tan, Jibo;  Wu, Xinqiang
收藏  |  浏览/下载：3/0  |  提交时间：2025/04/27
Crud deposition  Fuel cladding tube  Coolant pH  Subcooled nucleate boiling  Solubility  
Casting process design and practice for coolant pump impeller in AP1000 nuclear power station 期刊论文
CHINA FOUNDRY, 2020, 卷号: 17, 期号: 2, 页码: 173-177
作者:  Zhao, Ping;  Liu, Zhong-li;  Wang, Gui-quan;  Liu, Peng
收藏  |  浏览/下载：114/0  |  提交时间：2021/02/02
AP1000  coolant pump impeller  casting process  TG142  71  A  
Casting process design and practice for coolant pump impeller in AP1000 nuclear power station 期刊论文
CHINA FOUNDRY, 2020, 卷号: 17, 期号: 2, 页码: 173-177
作者:  Zhao, Ping;  Liu, Zhong-li;  Wang, Gui-quan;  Liu, Peng
收藏  |  浏览/下载：107/0  |  提交时间：2021/02/02
AP1000  coolant pump impeller  casting process  TG142  71  A  
Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment 期刊论文
CORROSION SCIENCE, 2018, 卷号: 132, 页码: 9-20
作者:  Dong, LJ;  Peng, QJ;  Xue, H;  Han, EH;  Ke, W;  Wang, L;  Peng, QJ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China.
收藏  |  浏览/下载：200/0  |  提交时间：2018/06/05
Low-alloy Steel  High-temperature Water  Heat-affected Zone  Bwr Coolant Environments  Grain-boundary  Metal Weld  Assisted Cracking  Stainless-steel  Chromium Depletion  Residual-stress  
Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment 期刊论文
Journal of Nuclear Materials, 2014, 卷号: 446, 期号: 1-3, 页码: 15-26
作者:  L. T. Zhang;  J. Q. Wang
收藏  |  浏览/下载：117/0  |  提交时间：2014/04/18
High-temperature Water  Assisted Cracking  Alloy 690tt  Pure Water  Growth  Behavior  Dependence  Chemistry  Coolant  Model