CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors

Published:2019 Issue: Volume: Page:755-800
ISSN:
Container-title:Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment
language:
Short-container-title:

Author:

Rousseau Pieter G.,Du Toit Charl G.,Van Antwerpen Herman J.

Publisher

Elsevier

Reference105 articles.

1. A technology roadmap for generation IV nuclear energy systems;GIF,2002

2. Generation IV nuclear reactors;World Nuclear Association,2017

3. Technology roadmap update for generation IV nuclear energy systems;GIF,2014

4. Molten salt reactors;World Nuclear Association,2017

5. Fluoride Salt-Cooled, High-Temperature Reactor (FHR) Methods and Experiments Program White Paper;Cisneros,2013

Cited by 4 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. Application of flow and heat transfer network analysis method to the core of a prismatic gas-cooled micro reactor;Frontiers in Energy Research;2024-08-21

2. Analysis of forced convection in the HTTU experiment using numerical codes;Nuclear Engineering and Technology;2023-12

3. A review of neutronics and thermal hydraulics–based screening methods applied to accelerated nuclear fuel qualification;Progress in Nuclear Energy;2023-08

4. Reactivity Effects in a Very-High-Temperature Pebble-Bed Reactor;Atom Indonesia;2021-04-19

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