Chenghao Cao, Junyi Chen, Jingang Liang, Chuan Li, Jianzhu Cao
{"title":"Advanced full-core modeling of fission product release in pebble-bed high-temperature gas-cooled reactors","authors":"Chenghao Cao, Junyi Chen, Jingang Liang, Chuan Li, Jianzhu Cao","doi":"10.1016/j.anucene.2025.111240","DOIUrl":null,"url":null,"abstract":"<div><div>Accurate modeling of fission product release is essential for the safety of pebble-bed high-temperature gas-cooled reactors. Traditional models oversimplify by neglecting non-uniform temperature fields, variable nuclide production rates, and the randomness of pebble flow. This study introduces an enhanced diffusion calculation method that incorporates variable production rates from the burnup equation and non-uniform temperature profiles from steady-state heat conduction models. A rapid full-core release calculation refined to individual pebble dynamics is developed to better capture equilibrium core behavior. Comparing the refined model to traditional methods, results show stepwise accumulation of concentrations, reduced release rates from particles and pebbles, and increased concentration gradients within the graphite matrix. Release rate distributions for short-lived nuclides are influenced by both core temperature and neutron flux distributions, while those for long-lived nuclides are primarily temperature-dependent. The variable-temperature model indicates that, compared to uniform particle temperature models, a greater diffusion distance is required for nuclide release.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"215 ","pages":"Article 111240"},"PeriodicalIF":1.9000,"publicationDate":"2025-02-11","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/S030645492500057X","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
Accurate modeling of fission product release is essential for the safety of pebble-bed high-temperature gas-cooled reactors. Traditional models oversimplify by neglecting non-uniform temperature fields, variable nuclide production rates, and the randomness of pebble flow. This study introduces an enhanced diffusion calculation method that incorporates variable production rates from the burnup equation and non-uniform temperature profiles from steady-state heat conduction models. A rapid full-core release calculation refined to individual pebble dynamics is developed to better capture equilibrium core behavior. Comparing the refined model to traditional methods, results show stepwise accumulation of concentrations, reduced release rates from particles and pebbles, and increased concentration gradients within the graphite matrix. Release rate distributions for short-lived nuclides are influenced by both core temperature and neutron flux distributions, while those for long-lived nuclides are primarily temperature-dependent. The variable-temperature model indicates that, compared to uniform particle temperature models, a greater diffusion distance is required for nuclide release.
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.