Thermal-hydraulic performance and safety assessment of an LBE-cooled reactor under steady-state and unprotected transients-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

Thermal-hydraulic performance and safety assessment of an LBE-cooled reactor under steady-state and unprotected transients

Published:2024-12 Issue: Volume:209 Page:110833
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Hashim Muhammad,Cao Liangzhi,Wu Hongchun,Jia Xiaoqian,Wang Jinshun,Ahmad Raza Sohail,Fan Haoyu

Publisher

Elsevier BV

Reference32 articles.

1. Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator;Bortot;Nucl. Eng. Des.,2011

2. Safety analysis of representative accidental transients for a 100 MWe small modular LBE-cooled reactor;Chen;Front. Energy Res.,2023

3. PASCAR: long burning small modular reactor based on natural circulation;Choi;Nucl. Eng. Des.,2011

4. Lead-cooled fast reactor (LFR) design: safety, neutronics, thermal hydraulics, structural mechanics, fuel, core, and plant design;Cinotti,2010

5. Cinotti, L., 2009. Lead-Cooled Fast Reactor (LFR) Overview and Perspectives.

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