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浏览/检索结果: 共9条，第1-9条 帮助 限定条件 专题：西安交通大学    第一署名单位    第一作者单位    通讯作者单位     已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Experimental study of liquid sodium flow and heat transfer characteristics along a hexagonal 7-rod bundle 期刊论文 Applied Thermal Engineering, 2019, 卷号: 149, 页码: 578-587 作者:  Hou, Yandong;  Wang, Liu;  Wang, Mingjun;  Zhang, Kui;  Zhang, Xisi 收藏  |  浏览/下载：35/0  |  提交时间：2019/11/19 Different geometry  Heat transfer data  Liquid sodium  Liquid sodium flows  Rod bundles  Single-phase liquids  Sodium cooled fast reactors (SFR)  Thermal hydraulics   Experimental study and optimized design on electromagnetic pump for liquid sodium 期刊论文 Annals of Nuclear Energy, 2019, 卷号: 124, 页码: 426-440 作者:  Wang, Liu;  Hou, Yandong;  Shi, Leitai;  Wu, Yingwei;  Tian, Wenxi 收藏  |  浏览/下载：12/0  |  提交时间：2019/11/19 Equivalent circuit method  Experimental research  Natural air cooling  Optimized designs  Performance analysis  Sodium cooled fast reactors (SFR)  Temperature limitation  Theoretical modeling   Numerical study on thermal deformation behaviors of the single subassembly in sodium-cooled fast reactors based on Euler-Bernoulli beam theory 期刊论文 NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 345, 页码: 28-39 作者:  Ma, Zhenhui;  Ma, Zehua;  Wu, Yingwei;  Wang, Mingjun;  Su, G. H. 收藏  |  浏览/下载：146/0  |  提交时间：2019/11/19 Sodium-cooled fast reactor  Thermal deformation  Subassembly  Deflection   Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors 期刊论文 Progress in Nuclear Energy, 2019, 卷号: 110, 页码: 213-223 作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing 收藏  |  浏览/下载：31/0  |  提交时间：2019/11/19 Code development  Decay heat removal  Design and optimization  Fast breeder reactors  Numerical approaches  Reactor vessel cooling  Transient characteristic  Transient thermal-hydraulic   Thermal-hydraulic analysis code development for sodium heated once-through steam generator 期刊论文 Annals of Nuclear Energy, 2019, 卷号: 127, 页码: 385-394 作者:  Xu, Rongshuan;  Zhang, Dalin;  Tian, Wenxi;  Qiu, Suizheng;  Su, G.H. 收藏  |  浏览/下载：11/0  |  提交时间：2019/11/19 China experiment fast reactor  Computer codes  Generate electricity  Once through steam generator  Sodium cooled fast reactors (SFR)  Thermal hydraulic modeling  Thermal hydraulic parameters  Thermal-hydraulic analysis   The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors 期刊论文 PROGRESS IN NUCLEAR ENERGY, 2018, 卷号: 108, 页码: 54-65 作者:  Yue, Nina;  Zhang, Dalin;  Chen, Jing;  Song, Ping;  Wang, Xin'an 收藏  |  浏览/下载：7/0  |  提交时间：2019/11/26 Sodium-cooled fast reactor  Code development  Sensitivity analyses  Inter-wrapper flow   Validation of a methodology for thermal stratification analysis in sodium-cooled fast reactors 期刊论文 INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 卷号: 42, 页码: 3803-3822 作者:  Wang, Shibao;  Zhang, Dalin;  Song, Ping;  Zhang, Yapei;  Wang, Mingjun 收藏  |  浏览/下载：13/0  |  提交时间：2019/11/26 turbulent model  program development  sodium-cooled fast reactors  thermal stratification   Development and Verification of Thermal-hydraulic System Analysis Code Based on RELAP5 MOD3.2 for SFRs 期刊论文 Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2017, 卷号: 51, 页码: 994-1001 作者:  Song, Jian;  Tan, Chao;  Tang, Si-Miao;  Liu, Li-Min;  Tian, Wen-Xi 收藏  |  浏览/下载：4/0  |  提交时间：2019/11/26 Argonne National Laboratory  Code development  RELAP5  Sodium cooled fast reactors (SFR)  Thermal hydraulic parameters  Thermal-hydraulic analysis  Thermal-hydraulic systems  Thermodynamic and transport properties   IMPLEMENTATION OF LIQUID METAL PROPERTIES IN RELAP5 MOD3.2 FOR SAFETY ANALYSIS OF SODIUM-COOLED FAST REACTORS 会议论文 作者:  Song, Jian;  Liu, Limin;  Tang, Simiao;  Wu, Yingwei;  Tian, Wenxi 收藏  |  浏览/下载：11/0  |  提交时间：2019/11/26