中国科学院机构知识库网格系统: 检索

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	Critical Heat Flux (CHF) Correlations for Subcooled Water Flow Boiling at High Pressure and High Heat Flux 期刊论文 OAI收割 JOURNAL OF THERMAL SCIENCE, 2021, 卷号: 30 作者: Liu, Ping; Guo, Yusheng; Ding, Wenlong; Tang, Mingyun; Song, Yuntao \| 收藏 \| 浏览/下载：45/0 \| 提交时间：2021/03/15 reactor divertor correlations subcooled water flow boiling critical heat flux (CHF) high heat flux high pressure
	Preliminary Analysis on DNB in the First Wall of WCCB Blanket for CFETR 期刊论文 OAI收割 IEEE TRANSACTIONS ON PLASMA SCIENCE, 2018, 卷号: 46, 期号: 6, 页码: 2318-2323 作者: Jiang, Kecheng; Li, Min; Bao, Hui; Lin, Shuang; Huang, Kai \| 收藏 \| 浏览/下载：29/0 \| 提交时间：2019/11/12 Chinese Fusion Engineering Reactor (CFETR) departure from nuclear boiling (DNB) vapor fraction water-cooled ceramic breeder blanket (WCCB)
	Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations 期刊论文 OAI收割 Journal of Nuclear Science and Technology, 2015, 卷号: 52, 期号: 1, 页码: 96-103 Y. K.; Lu Li, S. P.; Li, D. Z.; Kaji, Y. 收藏 \| 浏览/下载：15/0 \| 提交时间：2015/05/08 stress corrosion cracking boiling water reactor life prediction 316L stainless steel finite element methods core shroud