COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores

Published:1976-03-01 Issue: Volume: Page:
ISSN:
Container-title:
language:
Short-container-title:

Author:

Wheeler C.L.,Stewart C.W.,Cena R.J.,Rowe D.S.,Sutey A.M.

Publisher

Office of Scientific and Technical Information (OSTI)

Cited by 57 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. Multiscale analysis of the boron dilution sequence in the NuScale reactor using TRACE and SUBCHANFLOW;Nuclear Engineering and Design;2023-12

2. Thermal hydraulic review of light water reactor based on subchannel code CTF;Nuclear Engineering and Design;2023-11

3. Modeling hot channel two-phase flow of PWR NPPs during abnormal condition, using Python;Nuclear Engineering and Design;2023-08

4. FEATURES OF THERMAL HYDRAULICS OF ACTIVE ZONES OF FAST LOW-POWER AND HIGH-POWER SODIUM PRODUCTION REACTORS FOR A CLOSED FUEL CYCLE SYSTEM;PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS;2021-12-26

5. Subchannel analysis – Current practice and development for the future;Nuclear Engineering and Design;2021-12

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