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. |
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| 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] |
| Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.) | |
| Database: | Engineering Source |
| FullText | Text: Availability: 0 |
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| Header | DbId: egs DbLabel: Engineering Source An: 189789990 AccessLevel: 6 PubType: Academic Journal PubTypeId: academicJournal PreciseRelevancyScore: 0 |
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| Items | – Name: Title Label: Title Group: Ti Data: Modeling of the molten salt fast reactor transient behavior based on the modified point reactor kinetics model. – Name: Author Label: Authors Group: Au Data: <searchLink fieldCode="AR" term="%22Nguyen%2C+Thanh+Hung%22">Nguyen, Thanh Hung</searchLink><relatesTo>1,2</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Chen%2C+Yitung%22">Chen, Yitung</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> yitung.chen@unlv.edu</i> – Name: TitleSource Label: Source Group: Src Data: <searchLink fieldCode="JN" term="%22Annals+of+Nuclear+Energy%22">Annals of Nuclear Energy</searchLink>. Feb2026:Part A, Vol. 227, pN.PAG-N.PAG. 1p. – Name: Subject Label: Subjects Group: Su Data: <searchLink fieldCode="DE" term="%22Molten+salt+reactors%22">Molten salt reactors</searchLink><br /><searchLink fieldCode="DE" term="%22Delayed+neutrons%22">Delayed neutrons</searchLink><br /><searchLink fieldCode="DE" term="%22Model+validation%22">Model validation</searchLink><br /><searchLink fieldCode="DE" term="%22Monte+Carlo+method%22">Monte Carlo method</searchLink><br /><searchLink fieldCode="DE" term="%22Transients+%28Dynamics%29%22">Transients (Dynamics)</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactor+safety+measures%22">Nuclear reactor safety measures</searchLink> – Name: Abstract Label: Abstract Group: Ab Data: • 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] – Name: AbstractSuppliedCopyright Label: Group: Ab Data: <i>Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.) |
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| RecordInfo | BibRecord: BibEntity: Identifiers: – Type: doi Value: 10.1016/j.anucene.2025.111968 Languages: – Code: eng Text: English PhysicalDescription: Pagination: PageCount: 1 StartPage: N.PAG Subjects: – SubjectFull: Molten salt reactors Type: general – SubjectFull: Delayed neutrons Type: general – SubjectFull: Model validation Type: general – SubjectFull: Monte Carlo method Type: general – SubjectFull: Transients (Dynamics) Type: general – SubjectFull: Nuclear reactor safety measures Type: general Titles: – TitleFull: Modeling of the molten salt fast reactor transient behavior based on the modified point reactor kinetics model. Type: main BibRelationships: HasContributorRelationships: – PersonEntity: Name: NameFull: Nguyen, Thanh Hung – PersonEntity: Name: NameFull: Chen, Yitung IsPartOfRelationships: – BibEntity: Dates: – D: 10 M: 02 Text: Feb2026:Part A Type: published Y: 2026 Identifiers: – Type: issn-print Value: 03064549 Numbering: – Type: volume Value: 227 Titles: – TitleFull: Annals of Nuclear Energy Type: main |
| ResultId | 1 |
