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Modeling of the molten salt fast reactor transient behavior based on the modified point reactor kinetics model.

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Title: Modeling of the molten salt fast reactor transient behavior based on the modified point reactor kinetics model.
Authors: Nguyen, Thanh Hung1,2 (AUTHOR), Chen, Yitung1 (AUTHOR) yitung.chen@unlv.edu
Source: Annals of Nuclear Energy. Feb2026:Part A, Vol. 227, pN.PAG-N.PAG. 1p.
Subjects: Molten salt reactors, Delayed neutrons, Model validation, Monte Carlo method, Transients (Dynamics), Nuclear reactor safety measures
Abstract: • Developing a modified point reactor kinetics model for a molten salt fast reactor. • Coupling the modified point reactor kinetics model with FLUENT. • Validating the model through benchmarking against TUDelft model and PROTEUS-NODAL code. • Demonstrating the model's reliability for molten salt fast reactor transient analysis. In this study, a modified point reactor kinetics model is developed to account for the advection of delayed neutron precursors (DNPs) in a molten salt fast reactor (MSFR). Accurately capturing the behavior of delayed neutrons is crucial for MSFR transient analysis, as they have a significant impact on reactor control and overall stability. The point kinetics parameters, including prompt neutron generation time and the effective delayed neutron fraction, are calculated using an extended Monte Carlo N-Particle (MCNP) code. This version of the code is specifically modified to incorporate the effects of fuel circulation, which is a unique characteristic of molten salt reactors compared to traditional solid-fuel reactors. The kinetics model is coupled with FLUENT via a user-defined function (UDF) to simulate different transient scenarios, including unprotected transient over power (UTOP), unprotected loss of flow (ULOF), unprotected fuel salt overcooling (UFSOC), and unprotected pump overspeed (UPOS). These scenarios assume a failure of the reactor protection system. Model accuracy is validated through benchmarking against an independent model developed by the Technical University of Delft (TUDelft) and the PROTEUS-NODAL code, showing good agreement and confirming the model's reliability for MSFR transient analysis. [ABSTRACT FROM AUTHOR]
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Database: Engineering Source
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Abstract:• Developing a modified point reactor kinetics model for a molten salt fast reactor. • Coupling the modified point reactor kinetics model with FLUENT. • Validating the model through benchmarking against TUDelft model and PROTEUS-NODAL code. • Demonstrating the model's reliability for molten salt fast reactor transient analysis. In this study, a modified point reactor kinetics model is developed to account for the advection of delayed neutron precursors (DNPs) in a molten salt fast reactor (MSFR). Accurately capturing the behavior of delayed neutrons is crucial for MSFR transient analysis, as they have a significant impact on reactor control and overall stability. The point kinetics parameters, including prompt neutron generation time and the effective delayed neutron fraction, are calculated using an extended Monte Carlo N-Particle (MCNP) code. This version of the code is specifically modified to incorporate the effects of fuel circulation, which is a unique characteristic of molten salt reactors compared to traditional solid-fuel reactors. The kinetics model is coupled with FLUENT via a user-defined function (UDF) to simulate different transient scenarios, including unprotected transient over power (UTOP), unprotected loss of flow (ULOF), unprotected fuel salt overcooling (UFSOC), and unprotected pump overspeed (UPOS). These scenarios assume a failure of the reactor protection system. Model accuracy is validated through benchmarking against an independent model developed by the Technical University of Delft (TUDelft) and the PROTEUS-NODAL code, showing good agreement and confirming the model's reliability for MSFR transient analysis. [ABSTRACT FROM AUTHOR]
ISSN:03064549
DOI:10.1016/j.anucene.2025.111968