3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion
Author:
Funder
FRAMATOME
EDF
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference69 articles.
1. “A review of pellet–clad interaction behavior in zirconium alloy fuel cladding;Piro,2017
2. Modelling of iodine-induced stress corrosion cracking in CANDU fuel;Lewis;J. Nucl. Mater.,2011
3. Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel;Piro;J. Nucl. Mater.,2013
4. Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel;Veshchunov;Nucl. Eng. Des.,2006
5. A model for evolution of oxygen potential and stoichiometry deviation in irradiated UO2 fuel;Ozrin;J. Nucl. Mater.,2011
Cited by 16 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. Modeling oxygen transport in Cr doped UO2 fuel with the TAF-ID during power transients;Journal of Nuclear Materials;2025-01
2. ALCYONE: the fuel performance code of the PLEIADES platform dedicated to PWR fuel rods behavior;Annals of Nuclear Energy;2024-11
3. First evidence of metallisation circle in a Chromium doped UO2 pellet submitted to a thermal gradient;Journal of Nuclear Materials;2024-08
4. Molecular dynamics modeling of thermodiffusion in solids with charged defects using uranium dioxide as the case study;Chemical Engineering Science;2023-11
5. Characterisation of 3000 ppm Cr2O3 doped UO2 and its precipitates;Journal of Raman Spectroscopy;2023-02-24
1.学者识别学者识别
2.学术分析学术分析
3.人才评估人才评估
"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370
www.globalauthorid.com
TOP
Copyright © 2019-2024 北京同舟云网络信息技术有限公司 京公网安备11010802033243号 京ICP备18003416号-3