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Study on inherent neutron sources in MSR 被引量:1

Study on inherent neutron sources in MSR
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摘要 The molten salt reactor(MSR) has received much recent attention. The presence of beryllium and the mixing of actinides with light nuclei in the fuel salt result in a relatively strong neutron source that can affect the surveillance at subcritical and transient characteristics during operation. In this study, we predict the inherent neutron sources based on a MSR model. The calculation shows that in the fresh core, the inherent neutron sources are mainly from alpha-induced neutrons. After power operation, the inherent neutron sources become remarkably stronger due to photoneutrons. Although being an insignificant part in the total neutron population during operation, the inherent neutron sources can be used as the installed neutron source after shutdown. If the MSR has continuously operated at full power(2 MWt) for 10 days,then there would be no need for the installed source within80 days after shutdown. After operating constantly for500 days, the installed neutron source can be eliminated within 2 years after shutdown. The molten salt reactor(MSR) has received much recent attention. The presence of beryllium and the mixing of actinides with light nuclei in the fuel salt result in a relatively strong neutron source that can affect the surveillance at subcritical and transient characteristics during operation. In this study, we predict the inherent neutron sources based on a MSR model. The calculation shows that in the fresh core, the inherent neutron sources are mainly from alpha-induced neutrons. After power operation, the inherent neutron sources become remarkably stronger due to photoneutrons. Although being an insignificant part in the total neutron population during operation, the inherent neutron sources can be used as the installed neutron source after shutdown. If the MSR has continuously operated at full power(2 MWt) for 10 days,then there would be no need for the installed source within80 days after shutdown. After operating constantly for500 days, the installed neutron source can be eliminated within 2 years after shutdown.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2018年第4期146-154,共9页 核技术(英文)
基金 supported by the Chinese TMSR Strategic Pioneer Science and Technology Project under Grant No.XDA02010000
关键词 MSR Fuel SALT Inherent NEUTRON source PHOTONEUTRON Alpha-induced NEUTRON MSR Fuel salt Inherent neutron source Photoneutron Alpha-induced neutron
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  • 1BRIESMEISTER J F. MCNP-A general Monte-Carlo code for N-particle transport code, LA-12625-M[R]. USA: LANL, 1997.
  • 2濮继龙.大亚湾核电站运行教程[M].北京:原子能出版社,1998,43-44.

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