中国科学院机构知识库网格系统: 检索

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	Editorial: Nuclear materials degradation 期刊论文 OAI收割 FRONTIERS IN MATERIALS, 2023, 卷号: 10, 页码: 2 作者: Ming, Hongliang; Zhang, Zhiming; Chen, Jian; Noel, James J. \| 收藏 \| 浏览/下载：5/0 \| 提交时间：2024/01/07 nuclear material corrosion stress corrosion cracking irradiation materials for advanced reactors
	Influence of non-ideal gas characteristics on working fluid properties and thermal cycle of space nuclear power generation system 期刊论文 OAI收割 ENERGY, 2021, 卷号: 222 作者: Xu, Chi; Kong, Fanli; Yu, Dali; Yu, Jie; Khan, Muhammad Salman \| 收藏 \| 浏览/下载：31/0 \| 提交时间：2021/05/06 CBC Helium-xenon Physical property parameters Non-ideal gas Space nuclear reactors
	Effect of CrF3 on the corrosion behaviour of Hastelloy-N and 316L stainless steel alloys in FLiNaK molten salt 期刊论文 OAI收割 CORROSION SCIENCE, 2018, 卷号: 131, 页码: 355-364 作者: Yin, HQ; Qiu, J; Liu, HJ; Liu, WG; Wang, Y \| 收藏 \| 浏览/下载：45/0 \| 提交时间：2018/09/06 Naf-kf Salt Nuclear-power Fe-cr Fluoride Reactors Flow
	Development and techno-economic analysis of small modular nuclear reactor and desalination system across Middle East and North Africa region 期刊论文 OAI收割 DESALINATION, 2017, 卷号: 406, 期号: 无, 页码: 51-59 作者: Khan, Salah Ud-Din; Khan, Shahab Ud-Din; Haider, Sajjad; El-Leathy, Abdelrahman; Rana, Usman Ali 收藏 \| 浏览/下载：29/0 \| 提交时间：2018/05/02 Nuclear Reactors Nuclear Desalination Systems Mena Region Kingdom Of Saudi Arabia Case Coupled Nuclear Desalination System Theoretical-computational Techniques Cost Analysis
	Behaviors of fine (IG-110) and ultra-fine (HPG-510) grain graphite irradiated by 7 MeV Xe26+ ions 期刊论文 OAI收割 NUCLEAR SCIENCE AND TECHNIQUES, 2017, 卷号: 28, 期号: 10, 页码: - 作者: Qi, W; He, ZT; Zhang, BL; He, XJ; Zhang, C \| 收藏 \| 浏览/下载：34/0 \| 提交时间：2018/08/30 Raman-spectroscopic Characterization Transmission Electron-microscopy Isotropic Nuclear Graphite Molten-salt Reactors Gas-cooled Reactor Neutron-irradiation Microstructural Changes Thermal-conductivity Carbon Performance
	Mechanical Properties and Microstructures of the HAZs of 11Cr F/M Steel for Gen-IV Nuclear Power Station 期刊论文 OAI收割 Journal of Materials Engineering and Performance, 2015, 卷号: 24, 期号: 2, 页码: 885-893 Y. K.; Wang Li, J.; Lu, S. P.; Rong, L. J.; Li, D. Z. 收藏 \| 浏览/下载：26/0 \| 提交时间：2015/05/08 11Cr F/M steel finite element method Gen-IV nuclear materials heat-affected zones thermal simulation heat-affected zone residual-stress reactors toughness
	Startup and burnup strategy for Th-U/U-Pu fuel cycles in an EM2 reactor 期刊论文 OAI收割 PROGRESS IN NUCLEAR ENERGY, 2015, 卷号: 85, 页码: 764—770 作者: Ma, YW; Li, XX; Cai, XZ; Yu, CG; Zou, CY 收藏 \| 浏览/下载：58/0 \| 提交时间：2016/03/04 SMALL MODULAR REACTORS NUCLEAR-ENERGY URANIUM FUEL THORIUM TECHNOLOGY TRANSMUTATION ECONOMICS PROSPECTS SYSTEMS DESIGNS
	Thermodynamic modeling of kf-crf3 binary system 期刊论文 OAI收割 Chemical research in chinese universities, 2015, 卷号: 31, 期号: 3, 页码: 461—465 作者: Yin, HQ; Wang, K; Xie, LD; Han, H; Wang, WF 收藏 \| 浏览/下载：13/0 \| 提交时间：2015/12/09 Nuclear-power Salt Reactors Cycle
	Effect of carbon and niobium on the microstructure and impact toughness of a high silicon 12% Cr ferritic/martensitic heat resistant steel 期刊论文 OAI收割 Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing, 2014, 卷号: 616, 页码: 12-19 Z. F. Ye; P. Wang; D. Z. Li; Y. T. Zhang; Y. Y. Li 收藏 \| 浏览/下载：60/0 \| 提交时间：2015/01/14 High silicon 12% Cr ferritic/martensitic steel Primary NbC Carbonitride Thermodynamic calculations Impact toughness ferritic martensitic steels si-enriched steels mechanical-properties lead-bismuth power-plant corrosion-resistance nuclear-reactors creep strength temperature precipitation