Development of Ceramic-Coated Lithium Particles for Tritium Production Tests in High Temperature Engineering Test Reactor.
Author:
Publisher
Atomic Energy Society of Japan
Subject
Nuclear Energy and Engineering
Cited by 6 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. Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors;Nuclear Materials and Energy;2016-12
2. Evaluation of Tritium Confinement Performance of Alumina and Zirconium for Tritium Production in a High-Temperature Gas-Cooled Reactor for Fusion Reactors;Fusion Science and Technology;2015-10
3. Study on a method for loading a Li compound to produce tritium using high-temperature gas-cooled reactor;Nuclear Engineering and Design;2015-10
4. Evaluation of tritium production rate in a gas-cooled reactor with continuous tritium recovery system for fusion reactors;Fusion Engineering and Design;2013-10
5. Performance of high-temperature gas-cooled reactor as a tritium production device for fusion reactors;Nuclear Engineering and Design;2012-02
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