Ezequiel Fogliatto, Ivor Clifford, Alexander Vasiliev, Abdelhamid Dokhane, Ferroukhi Hakim
{"title":"MSLB事件模拟的实用建模方法验证:对CFD的贡献","authors":"Ezequiel Fogliatto, Ivor Clifford, Alexander Vasiliev, Abdelhamid Dokhane, Ferroukhi Hakim","doi":"10.1016/j.anucene.2025.111572","DOIUrl":null,"url":null,"abstract":"<div><div>This article describes the development and application of a Computational Fluid Dynamics (CFD) model to simulate the fluid flow, heat transfer, and boron distribution during a Main Steam Line Break (MSLB) event in a three-loop pre-Konvoi Nuclear Power Plant. The CFD simulations were used to produce time-varying flow maps at the core inlet, which were integrated into a transient SIMULATE-3 K core model using a loose-coupling methodology. The simulations predict complex flow patterns within the reactor pressure vessel, characterized by pronounced temperature stratification in the downcomer and a well-defined cold plume descending directly from the affected cold leg. This coolant behavior significantly influences flow and boron distributions, with notable deviations at the core inlet compared to traditional static mixing assumptions. Transient reactivity calculations conducted with SIMULATE-3 K, utilizing mixing maps derived from the CFD simulations and an in-house mixing tool, show a larger margin to recriticality than traditional static homogeneous mixing maps.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"222 ","pages":"Article 111572"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Verification of practical modeling approaches of an MSLB event simulation: A CFD contribution\",\"authors\":\"Ezequiel Fogliatto, Ivor Clifford, Alexander Vasiliev, Abdelhamid Dokhane, Ferroukhi Hakim\",\"doi\":\"10.1016/j.anucene.2025.111572\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This article describes the development and application of a Computational Fluid Dynamics (CFD) model to simulate the fluid flow, heat transfer, and boron distribution during a Main Steam Line Break (MSLB) event in a three-loop pre-Konvoi Nuclear Power Plant. The CFD simulations were used to produce time-varying flow maps at the core inlet, which were integrated into a transient SIMULATE-3 K core model using a loose-coupling methodology. The simulations predict complex flow patterns within the reactor pressure vessel, characterized by pronounced temperature stratification in the downcomer and a well-defined cold plume descending directly from the affected cold leg. This coolant behavior significantly influences flow and boron distributions, with notable deviations at the core inlet compared to traditional static mixing assumptions. Transient reactivity calculations conducted with SIMULATE-3 K, utilizing mixing maps derived from the CFD simulations and an in-house mixing tool, show a larger margin to recriticality than traditional static homogeneous mixing maps.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"222 \",\"pages\":\"Article 111572\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-27\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454925003895\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925003895","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Verification of practical modeling approaches of an MSLB event simulation: A CFD contribution
This article describes the development and application of a Computational Fluid Dynamics (CFD) model to simulate the fluid flow, heat transfer, and boron distribution during a Main Steam Line Break (MSLB) event in a three-loop pre-Konvoi Nuclear Power Plant. The CFD simulations were used to produce time-varying flow maps at the core inlet, which were integrated into a transient SIMULATE-3 K core model using a loose-coupling methodology. The simulations predict complex flow patterns within the reactor pressure vessel, characterized by pronounced temperature stratification in the downcomer and a well-defined cold plume descending directly from the affected cold leg. This coolant behavior significantly influences flow and boron distributions, with notable deviations at the core inlet compared to traditional static mixing assumptions. Transient reactivity calculations conducted with SIMULATE-3 K, utilizing mixing maps derived from the CFD simulations and an in-house mixing tool, show a larger margin to recriticality than traditional static homogeneous mixing maps.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.