{"title":"Systematic generation of effective thermophysical and thermo-mechanical properties for reduced-order modeling of TRISO fuel pellets","authors":"Samuel Heflin , Vedant Mehta , Dan Kotlyar","doi":"10.1016/j.anucene.2025.111487","DOIUrl":null,"url":null,"abstract":"<div><div>This work presents a detailed methodology for generating effective material properties of tri-structural isotropic (TRISO) fuel pellets for use in reduced-order homogenized thermal and/or mechanical calculations. This is achieved by use of the finite-element (FE) method to perform simulations of explicitly modeled TRISO fuel pellets, in conjunction with derivation of analytical equations for analogous homogenous pellets which preserve a particular parameter of interest. This method is applied to several properties including thermal conductivity, specific heat capacity, thermal expansion coefficient, Young’s Modulus and Poisson’s Ratio. The properties generated are a function of temperature and packing fraction. It is demonstrated that the state-of-the-art for homogenizing thermal conductivity may be inadequate for realistic TRISO pellets, while for other properties existing homogenization standards are scarce in the literature. Finally, a multi-physics application of the reduced-order properties is demonstrated, which involves coupling neutronics with thermo-mechanical calculations. The fission power distribution is obtained from neutronic analysis, and then temperature, displacement and stress–strain distributions from the explicit finite-element model are compared with those from the homogenous calculations. For the finite-element simulations, the commercial software Abaqus (<span><span>ABAQUS, 2014</span></span>) is used, and the Monte Carlo code MCNP is used for neutronics to obtain the power distributions.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111487"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-16","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/S0306454925003044","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
This work presents a detailed methodology for generating effective material properties of tri-structural isotropic (TRISO) fuel pellets for use in reduced-order homogenized thermal and/or mechanical calculations. This is achieved by use of the finite-element (FE) method to perform simulations of explicitly modeled TRISO fuel pellets, in conjunction with derivation of analytical equations for analogous homogenous pellets which preserve a particular parameter of interest. This method is applied to several properties including thermal conductivity, specific heat capacity, thermal expansion coefficient, Young’s Modulus and Poisson’s Ratio. The properties generated are a function of temperature and packing fraction. It is demonstrated that the state-of-the-art for homogenizing thermal conductivity may be inadequate for realistic TRISO pellets, while for other properties existing homogenization standards are scarce in the literature. Finally, a multi-physics application of the reduced-order properties is demonstrated, which involves coupling neutronics with thermo-mechanical calculations. The fission power distribution is obtained from neutronic analysis, and then temperature, displacement and stress–strain distributions from the explicit finite-element model are compared with those from the homogenous calculations. For the finite-element simulations, the commercial software Abaqus (ABAQUS, 2014) is used, and the Monte Carlo code MCNP is used for neutronics to obtain the power distributions.
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.