A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors

A semi-analytical method for modelling station blackout performance in liquid metal reactors is developed, permitting to identify key factors determining peak temperatures during the transient, and hence to design associated passive safety systems. It is shown that integrity of the fuel cladding during this transient can be ensured by adequate dimensioning of coolant channels, the primary system and the vessel air cooling circuit. These dimensions are determined using algebraic equations and postulated values for a minimum/maximum permissible Reynolds number, dimensionless parameters for the fuel cladding tube geometry and heat sink elevation, a guard vessel height, the nominal core power, permitted temperature gradients in the vessel air cooling system and the air cooling system chimney height. The model suggests that the required coolant volume is a rapidly growing function of core power, and that this volume needs to be 40% larger in a sodium-cooled reactor than in a lead-cooled reactor. • A semi-analytical method for modelling of station blackout transients has been developed. • Passive safety systems are dimensioned using a small set of boundary conditions. • The coolant volume required to accommodate decay heat grows rapidly with core power

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Publication Details

Journal
Annals of Nuclear Energy
Published
2025-04-14
DOI
https://doi.org/10.1016/j.anucene.2025.111414
Citations
1
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
4.99

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article

A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors

Fredrik Dehlin, Janne Wallenius
1 citations
Annals of Nuclear Energy
Nuclear reactor physics and engineering
4.99
article

A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors

Fredrik Dehlin, Janne Wallenius
article en
1 citations

Abstract

A semi-analytical method for modelling station blackout performance in liquid metal reactors is developed, permitting to identify key factors determining peak temperatures during the transient, and hence to design associated passive safety systems. It is shown that integrity of the fuel cladding during this transient can be ensured by adequate dimensioning of coolant channels, the primary system and the vessel air cooling circuit. These dimensions are determined using algebraic equations and postulated values for a minimum/maximum permissible Reynolds number, dimensionless parameters for the fuel cladding tube geometry and heat sink elevation, a guard vessel height, the nominal core power, permitted temperature gradients in the vessel air cooling system and the air cooling system chimney height. The model suggests that the required coolant volume is a rapidly growing function of core power, and that this volume needs to be 40% larger in a sodium-cooled reactor than in a lead-cooled reactor. • A semi-analytical method for modelling of station blackout transients has been developed. • Passive safety systems are dimensioned using a small set of boundary conditions. • The coolant volume required to accommodate decay heat grows rapidly with core power

Annals of Nuclear EnergyVol. 219
AlbaNova (SE)
Stiftelsen för Strategisk Forskning
Openalex Percentile: Top 7%
Nuclear reactor physics and engineering
4.99
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