Előd Pázmán , Gábor Tolnai , Dávid Légrády , Luigi Mercatali , Gianfranco Huaccho , Victor Hugo Sanchez-Espinoza
{"title":"利用 GUARDYAN-SUBCHANFLOW 耦合代码系统对 SMART 类反应堆模型中的 HZP 和 HFP 棒喷射进行分析","authors":"Előd Pázmán , Gábor Tolnai , Dávid Légrády , Luigi Mercatali , Gianfranco Huaccho , Victor Hugo Sanchez-Espinoza","doi":"10.1016/j.anucene.2024.110988","DOIUrl":null,"url":null,"abstract":"<div><div>GUARDYAN is a dynamic 3D Monte Carlo reactor physics code with continuous energy handling developed for GPU hardware that has recently been coupled to the SUBCHANFLOW (SCF) subchannel thermal hydraulics solver. In this paper two control rod ejection accident scenarios will be presented in a Small Modular Reactor (SMR) geometry: a transient starting from Hot Zero Power (HZP), and one starting from Hot Full Power (HFP) conditions, both of them using Beginning of Cycle (BOC) material composition. Both the time dependent core-wise data and the node-wise data at certain times calculated by the GUARDYAN-SCF coupled code system exhibit the tendencies expected during such transients, with the thermal hydraulic properties mostly inside their safe limits. Relative variances estimated from 8 independent realisations suggest the results are credible. To further support our findings the HZP results are presented alongside data from PARCS-SCF and Serpent2-SCF calculations provided by Karlsruhe Institute of Technology (KIT), while for the HFP case we were able to compare some of the quantities to PARCS-SCF results.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-10-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"HZP and HFP rod ejection analysis in a SMART-like reactor model using the GUARDYAN-SUBCHANFLOW coupled code system\",\"authors\":\"Előd Pázmán , Gábor Tolnai , Dávid Légrády , Luigi Mercatali , Gianfranco Huaccho , Victor Hugo Sanchez-Espinoza\",\"doi\":\"10.1016/j.anucene.2024.110988\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>GUARDYAN is a dynamic 3D Monte Carlo reactor physics code with continuous energy handling developed for GPU hardware that has recently been coupled to the SUBCHANFLOW (SCF) subchannel thermal hydraulics solver. In this paper two control rod ejection accident scenarios will be presented in a Small Modular Reactor (SMR) geometry: a transient starting from Hot Zero Power (HZP), and one starting from Hot Full Power (HFP) conditions, both of them using Beginning of Cycle (BOC) material composition. Both the time dependent core-wise data and the node-wise data at certain times calculated by the GUARDYAN-SCF coupled code system exhibit the tendencies expected during such transients, with the thermal hydraulic properties mostly inside their safe limits. Relative variances estimated from 8 independent realisations suggest the results are credible. To further support our findings the HZP results are presented alongside data from PARCS-SCF and Serpent2-SCF calculations provided by Karlsruhe Institute of Technology (KIT), while for the HFP case we were able to compare some of the quantities to PARCS-SCF results.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-10-25\",\"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/S0306454924006510\",\"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/S0306454924006510","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}
HZP and HFP rod ejection analysis in a SMART-like reactor model using the GUARDYAN-SUBCHANFLOW coupled code system
GUARDYAN is a dynamic 3D Monte Carlo reactor physics code with continuous energy handling developed for GPU hardware that has recently been coupled to the SUBCHANFLOW (SCF) subchannel thermal hydraulics solver. In this paper two control rod ejection accident scenarios will be presented in a Small Modular Reactor (SMR) geometry: a transient starting from Hot Zero Power (HZP), and one starting from Hot Full Power (HFP) conditions, both of them using Beginning of Cycle (BOC) material composition. Both the time dependent core-wise data and the node-wise data at certain times calculated by the GUARDYAN-SCF coupled code system exhibit the tendencies expected during such transients, with the thermal hydraulic properties mostly inside their safe limits. Relative variances estimated from 8 independent realisations suggest the results are credible. To further support our findings the HZP results are presented alongside data from PARCS-SCF and Serpent2-SCF calculations provided by Karlsruhe Institute of Technology (KIT), while for the HFP case we were able to compare some of the quantities to PARCS-SCF results.
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.