Wenwen Zhang, Wenli Guo, Wentao Hao, Hao Luo, Ding She
{"title":"Numerical study on the effective thermophysical properties of U3Si2/Al dispersion fuel with interaction layer growth","authors":"Wenwen Zhang, Wenli Guo, Wentao Hao, Hao Luo, Ding She","doi":"10.1016/j.pnucene.2025.105988","DOIUrl":null,"url":null,"abstract":"<div><div>U<sub>3</sub>Si<sub>2</sub>/Al dispersion fuel has been widely used in research reactors due to its high uranium density and excellent thermal conductivity. The thermophysical properties of the fuel meat, primarily effective thermal conductivity and specific heat capacity, directly affect the heat dissipation performance and in-core behavior of the fuel. In this study, a refined Representative Volume Element (RVE) model coupled with the Finite Element Method (FEM) is employed to systematically investigate the thermophysical properties of U<sub>3</sub>Si<sub>2</sub>/Al dispersion fuel with four different uranium densities. The model incorporates the effects of fuel particle distribution, Interaction Layer (IL) growth, and matrix porosity. The influence of temperature, fuel particle volume fraction, matrix porosity, and IL thickness on the effective thermal conductivity and specific heat capacity is explored. The accuracy of the proposed numerical method is validated by comparison with results from literature-based code and experimentally summarized data. The results indicate that increases in both fuel particle volume fraction and matrix porosity significantly alter the effective thermal conductivity and specific heat. Notably, the growth of the interaction layer reduces the thermal conductivity and modifies the distribution of specific heat capacity. This work provides a theoretical basis for predicting the thermophysical behavior of U<sub>3</sub>Si<sub>2</sub>/Al dispersion fuel and offers new insights into fuel design and performance optimization.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105988"},"PeriodicalIF":3.2000,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025003865","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
U3Si2/Al dispersion fuel has been widely used in research reactors due to its high uranium density and excellent thermal conductivity. The thermophysical properties of the fuel meat, primarily effective thermal conductivity and specific heat capacity, directly affect the heat dissipation performance and in-core behavior of the fuel. In this study, a refined Representative Volume Element (RVE) model coupled with the Finite Element Method (FEM) is employed to systematically investigate the thermophysical properties of U3Si2/Al dispersion fuel with four different uranium densities. The model incorporates the effects of fuel particle distribution, Interaction Layer (IL) growth, and matrix porosity. The influence of temperature, fuel particle volume fraction, matrix porosity, and IL thickness on the effective thermal conductivity and specific heat capacity is explored. The accuracy of the proposed numerical method is validated by comparison with results from literature-based code and experimentally summarized data. The results indicate that increases in both fuel particle volume fraction and matrix porosity significantly alter the effective thermal conductivity and specific heat. Notably, the growth of the interaction layer reduces the thermal conductivity and modifies the distribution of specific heat capacity. This work provides a theoretical basis for predicting the thermophysical behavior of U3Si2/Al dispersion fuel and offers new insights into fuel design and performance optimization.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.