CAS OpenIR  > 中科院上海应用物理研究所2011-2019年
Simulation of neutron diffusion and transient analysis of MSR
Zhu, L; Pu, P; Du, S; Han, DD; ddhan@ee.ecnu.edu.cn
2014
Source PublicationNUCLEAR SCIENCE AND TECHNIQUES
ISSN1001-8042
Volume25Issue:2
AbstractMolten 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.
KeywordMolten-salt Reactors Fluid-fuel Systems Dynamics Code Physics Law
Indexed BySCI
Language英语
WOS IDWOS:000337120700017
Citation statistics
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/14395
Collection中科院上海应用物理研究所2011-2019年
Corresponding Authorddhan@ee.ecnu.edu.cn
Recommended Citation
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,&ddhan@ee.ecnu.edu.cn.(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).
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