Simulation of neutron diffusion and transient analysis of MSR
文献类型：期刊论文
| 作者 | Zhu, L ; Pu, P ; Du, S ; Han, DD |
| 刊名 | NUCLEAR SCIENCE AND TECHNIQUES
 |
| 出版日期 | 2014 |
| 卷号 | 25期号:2 |
| 关键词 | MOLTEN-SALT REACTORS FLUID-FUEL SYSTEMS DYNAMICS CODE PHYSICS LAW |
| ISSN号 | 1001-8042 |
| 通讯作者 | ddhan@ee.ecnu.edu.cn |
| 英文摘要 | Molten salt reactor (MSR) is a potential nuclear power reactor of Generation IV. The working process of the primary loop of an MSR is studied in this paper. A physical model is established to describe the coupled heat transfer for the MSR core channels, the temperature negative feedback and the neutron characteristics. The simulation code, NDP1D, has been developed with the object-oriented method, conducting the neutron diffusion and transient analysis in a parallel way. The simulation data and diagrams of neutron, power, flow rate and temperature can be obtained via graphical user interface. The simulation results can be used for further study on MSRs of larger dimensions and more complicated geometry. |
| 收录类别 | SCI |
| 语种 | 英语 |
| WOS记录号 | WOS:000337120700017 |
| 公开日期 | 2015-03-13 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/14395]  |
| 专题 | 上海应用物理研究所_中科院上海应用物理研究所2011-2017年 |
| 推荐引用方式 GB/T 7714 | Zhu, L,Pu, P,Du, S,et al. Simulation of neutron diffusion and transient analysis of MSR[J]. NUCLEAR SCIENCE AND TECHNIQUES,2014,25(2). |
| APA | Zhu, L,Pu, P,Du, S,&Han, DD.(2014).Simulation of neutron diffusion and transient analysis of MSR.NUCLEAR SCIENCE AND TECHNIQUES,25(2). |
| MLA | Zhu, L,et al."Simulation of neutron diffusion and transient analysis of MSR".NUCLEAR SCIENCE AND TECHNIQUES 25.2(2014). |
入库方式： OAI收割
来源：上海应用物理研究所
浏览0
下载0
收藏0
其他版本
除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。