Short-term irradiation behavior of low-density americium-doped uranium–plutonium mixed oxide fuels irradiated in a fast reactor
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference22 articles.
1. Design challenges for sodium cooled fast reactors
2. M. Ichimiya, T. Mizuno, M. Konomura, in: Proceedings of GLOBAL 2003, New Orleans, LA, USA, 16–20 November 2003, pp. 434–446 (on cd-rom).
3. Solidus and liquidus temperatures in the UO2–PuO2 system
4. Transmutation of neptunium and americium in a fast neutron flux: EPMA results and KORIGEN predictions for the superfact fuels
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. A science‐based mixed oxide property model for developing advanced oxide nuclear fuels;Journal of the American Ceramic Society;2023-12-17
2. Study on Actinide Burning Core Concepts for the Future Phaseout of a Fast Reactor Fuel Cycle;Nuclear Technology;2023-01-19
3. Post-irradiation characterization of a high burnup mixed oxide fuel rod with minor actinides;Journal of Nuclear Materials;2022-04
4. Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data;Journal of Nuclear Materials;2021-12
5. Oxygen potential measurement of (U,Pu,Am)O2±x and (U,Pu,Am,Np)O2±x;Journal of Nuclear Materials;2020-12
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