A safety enhanced sodium-cooled MOX fueled fast reactor core concept-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

A safety enhanced sodium-cooled MOX fueled fast reactor core concept

Published:2023-03-23 Issue:10 Volume:60 Page:1258-1269
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Fujimura Koji¹,Fuchita Sho¹,Fujimata Kazuhiro¹,Takeda Satoshi²^ORCID,Takeda Toshikazu³

Affiliation:

1. Nuclear Plant Engineering Department, Hitachi-GE Nuclear Energy, Ltd, Hitachi-shi, Ibaraki, Japan

2. Division of Sustainable Energy and Environmental Engineering, Graduate School of Engineering, Osaka University, Suita-shi, Osaka, Japan

3. Research Institute of Nuclear Engineering, University of Fukui, Tsuruga-shi, Fukui, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2023.2188268

Reference19 articles.

1. Generation IV International Forum (GIF), Safety design guidelines on safety approach and design conditions for Generation IV Sodium-cooled Fast Reactor Systems, 2016, https://www.gen-4.org/gif/jcms/c_93020/safety-design-criteria.

同舟云学术

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