A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors
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| Názov: | A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors |
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| Autori: | Wallenius, Janne, 1968, Dehlin, Fredrik, 1994 |
| Zdroj: | Annals of Nuclear Energy. 219 |
| Predmety: | Station blackout, Passive heat removal, Primary vessel volume, Kärnenergiteknik, Nuclear Engineering |
| Popis: | 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. |
| Popis súboru: | |
| Prístupová URL adresa: | https://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-363056 https://doi.org/10.1016/j.anucene.2025.111414 |
| Databáza: | SwePub |
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Nájsť tento článok vo Web of Science | Abstrakt: | 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. |
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| ISSN: | 03064549 |
| DOI: | 10.1016/j.anucene.2025.111414 |