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浏览/检索结果: 共6条，第1-6条 帮助 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 Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment 期刊论文 Progress in Nuclear Energy, 2019, 卷号: 111, 页码: 174-182 作者:  Feng, Tangtao;  Tian, Wenxi;  Song, Ping;  Wang, Jun;  Wang, Mingjun 收藏  |  浏览/下载：113/0  |  提交时间：2019/11/19 CORA  Experiment condition  International standards  MELCOR  Mitigation measures  Numerical analysis models  Peak temperatures  Spatial temperature distribution   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   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: Vol.110, 页码: 213-223 作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing 收藏  |  浏览/下载：7/0  |  提交时间：2019/12/13 Code development  Decay heat removal  Design and optimization  Fast breeder reactors  Numerical approaches  Reactor vessel cooling  Transient characteristic  Transient thermal-hydraulic   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: Vol.110, 页码: 213-223 作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing 收藏  |  浏览/下载：7/0  |  提交时间：2019/12/13 Reactor  vessel  cooling  system  Code  development  Sodium-cooled  fast  reactor  Sensitivity  analysis   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: Vol.110, 页码: 213-223 作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing 收藏  |  浏览/下载：5/0  |  提交时间：2019/12/13 NUCLEAR  reactors  *PRESSURE  vessels  *COOLING  systems  *SENSITIVITY  analysis  *SODIUM  cooled  reactors   Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5 期刊论文 ANNALS OF NUCLEAR ENERGY, 2017, 卷号: 109, 页码: 318-326 作者:  Feng, Tangtao;  Zhang, Dalin;  Song, Ping;  Tian, Wenxi;  Li, Wei 收藏  |  浏览/下载：5/0  |  提交时间：2019/11/26 Coupling scheme  Water hammer  Valve close  Pump startup  Column separation