Jason Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William Hanson, Nicholas Ullum, Jeffrey J. Giglio, James I. Cole
{"title":"Mechanical Properties of Irradiated U-10wt%Mo Alloy Degraded by Porosity Development","authors":"Jason Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William Hanson, Nicholas Ullum, Jeffrey J. Giglio, James I. Cole","doi":"10.1115/1.4064779","DOIUrl":null,"url":null,"abstract":"\n A plate-type nuclear fuel consisting of a solid monolithic foil of U-10wt%Mo is under development for use in the United States' high performance research reactors. In support of developing this fuel, the fuel has been fabricated for the first time by a commercial fuel vendor and subsequently irradiated in a test reactor. This provides an opportunity to evaluate post-irradiation mechanical properties of the commercially fabricated fuel. Four-point bend testing was conducted on the irradiated U-10Mo samples to generate the fuel material properties, including the modulus of elasticity and the bending strength. Although the material behaves in a brittle manner due to the accumulated porosity, a general trend of strength and modulus reduction were found as fission density increases. The data produced was evaluated using both Weibull statistics and a modulus degradation model with recommendations provided.","PeriodicalId":16756,"journal":{"name":"Journal of Nuclear Engineering and Radiation Science","volume":null,"pages":null},"PeriodicalIF":0.5000,"publicationDate":"2024-02-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Engineering and Radiation Science","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/1.4064779","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
A plate-type nuclear fuel consisting of a solid monolithic foil of U-10wt%Mo is under development for use in the United States' high performance research reactors. In support of developing this fuel, the fuel has been fabricated for the first time by a commercial fuel vendor and subsequently irradiated in a test reactor. This provides an opportunity to evaluate post-irradiation mechanical properties of the commercially fabricated fuel. Four-point bend testing was conducted on the irradiated U-10Mo samples to generate the fuel material properties, including the modulus of elasticity and the bending strength. Although the material behaves in a brittle manner due to the accumulated porosity, a general trend of strength and modulus reduction were found as fission density increases. The data produced was evaluated using both Weibull statistics and a modulus degradation model with recommendations provided.
期刊介绍:
The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.