Development of Neutron Kinetic Code for Molten Salt Reactors

Zhuang Kun; Cao Liangzhi; ZhenG Youqi; Wu Hongchun

doi:10.13832/j.jnpe.2014.S2.0183

Volume 35 Issue S2

Feb. 2025

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Zhuang Kun, Cao Liangzhi, ZhenG Youqi, Wu Hongchun. Development of Neutron Kinetic Code for Molten Salt Reactors[J]. Nuclear Power Engineering, 2014, 35(S2): 183-185. doi: 10.13832/j.jnpe.2014.S2.0183

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Zhuang Kun, Cao Liangzhi, ZhenG Youqi, Wu Hongchun. Development of Neutron Kinetic Code for Molten Salt Reactors[J]. Nuclear Power Engineering, 2014, 35(S2): 183-185. doi: 10.13832/j.jnpe.2014.S2.0183

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Development of Neutron Kinetic Code for Molten Salt Reactors

doi: 10.13832/j.jnpe.2014.S2.0183

School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China

Received Date: 2014-10-27
Rev Recd Date: 2014-11-19

Available Online: 2025-02-15

Abstract

Abstract

This study establishes the suitable dynamic models for molten salt reactors considering the effects of fuel flow on the distribution of delayed neutron precursors and then develops a new code named MOREL. Some MSRE experimental data from Oak Ridge National Laboratory（ORNL） are chosen to verify the code, especially the DNP model, and the numerical results indicate that MOREL can be used for the analysis of the molten salt reactors.
- Molten salt reactor,
- Reactivity loss,
- Neutron kinetics

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