Piotr Konarski, Alexey Cherezov, Cedric Cozzo, Grigori Khvostov, Hakim Ferroukhi
{"title":"为干储存分析寻找限制棒","authors":"Piotr Konarski, Alexey Cherezov, Cedric Cozzo, Grigori Khvostov, Hakim Ferroukhi","doi":"10.1016/j.anucene.2024.111043","DOIUrl":null,"url":null,"abstract":"<div><div>Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"212 ","pages":"Article 111043"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Finding limiting rods for dry storage analyses\",\"authors\":\"Piotr Konarski, Alexey Cherezov, Cedric Cozzo, Grigori Khvostov, Hakim Ferroukhi\",\"doi\":\"10.1016/j.anucene.2024.111043\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"212 \",\"pages\":\"Article 111043\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-11-13\",\"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/S0306454924007060\",\"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/S0306454924007060","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}
Fuel rod status during reactor operation must be numerically modeled before dry storage analyses. Simulating all the rods ever irradiated in Switzerland with state-of-the-art best estimate tools would be too time consuming. The goal of this study is to develop a methodology for identifying limiting BWR rods, where the criterion of limiting is the rod internal pressure. Limiting rods are those whose parameters may challenge rod integrity during dry storage, subsequent transport, or handling. The presence of radial hydrides is of particular importance. The precipitation of radially oriented hydrides is associated with strong tensile hoop stress of the cladding. This can be a consequence of high rod internal pressure which has been chosen the limiting parameter. In the first step, the 3D core simulators provide irradiation data. Then, the core simulator results along with rod geometrical parameters are submitted to the principal component analysis. The multidimensional datasets are reduced to 2D and processed by a clustering algorithm or not, depending on the assembly design. The limiting rods are identified for each batch or cluster and simulated with the fuel performance code Falcon and the hydrogen behavior code HYPE.
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.