L. Verma , I. Clifford , P. Konarski , A. Scolaro , H. Ferroukhi
{"title":"Analysing hydrogen behaviour in liner claddings using OFFBEAT fuel performance code","authors":"L. Verma , I. Clifford , P. Konarski , A. Scolaro , H. Ferroukhi","doi":"10.1016/j.anucene.2025.111559","DOIUrl":null,"url":null,"abstract":"<div><div>Hydrogen generated during the waterside corrosion of zirconium claddings can diffuse within the material, forming hydrides that alter the mechanical properties of the claddings. These hydrides may lead to detrimental effects such as delayed hydride cracking and embrittlement, compromising the integrity of the claddings. Liner claddings, which have been particularly used in Swiss reactors, have been shown to aid in minimizing these detrimental effects of hydrogen behaviour on zirconium claddings. In this paper, hydrogen behaviour models for liner claddings have been incorporated into the multi-dimensional, thermo-mechanical fuel performance code, OFFBEAT. Numerical analyses using OFFBEAT are then compared to out-of-pile experimental data on two liner cladding types commonly used in Swiss reactors. The findings indicate that OFFBEAT’s predictions closely align with experimental observations, demonstrating hydrogen migration toward the substrate-liner interface (SLI). This research confirms OFFBEAT’s capability to simulate hydrogen behavior in liner claddings, supporting further exploration of alternative cladding configurations moving forward towards more advanced technological fuels for nuclear safety.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"222 ","pages":"Article 111559"},"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/S0306454925003767","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}
引用次数: 0
Abstract
Hydrogen generated during the waterside corrosion of zirconium claddings can diffuse within the material, forming hydrides that alter the mechanical properties of the claddings. These hydrides may lead to detrimental effects such as delayed hydride cracking and embrittlement, compromising the integrity of the claddings. Liner claddings, which have been particularly used in Swiss reactors, have been shown to aid in minimizing these detrimental effects of hydrogen behaviour on zirconium claddings. In this paper, hydrogen behaviour models for liner claddings have been incorporated into the multi-dimensional, thermo-mechanical fuel performance code, OFFBEAT. Numerical analyses using OFFBEAT are then compared to out-of-pile experimental data on two liner cladding types commonly used in Swiss reactors. The findings indicate that OFFBEAT’s predictions closely align with experimental observations, demonstrating hydrogen migration toward the substrate-liner interface (SLI). This research confirms OFFBEAT’s capability to simulate hydrogen behavior in liner claddings, supporting further exploration of alternative cladding configurations moving forward towards more advanced technological fuels for nuclear safety.
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.