Application of Monte Carlo method to calculate the effective delayed neutron fraction in molten salt reactor

Delayed neutron loss is an important parameter in the safety analysis of molten salt reactors. In this study, to obtain the effective delayed neutron fraction under flow condition, a delayed neutron precursor transport was implemented in the Monte Carlo code MCNP. The molten-salt reactor experiment...

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Veröffentlicht in:	Nuclear science and techniques 2019-02, Vol.30 (2), p.136-145, Article 34
Hauptverfasser:	Zhu, Gui-Feng, Yan, Rui, Peng, Hong-Hua, Ji, Rui-Min, Yu, Shi-He, Liu, Ya-Fen, Tian, Jian, Xu, Bo
Format:	Artikel
Sprache:	eng
Schlagworte:	Energy Hadrons Heavy Ions Nuclear Energy Nuclear Physics
Online-Zugang:	Volltext
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