Novel divertor design to mitigate neutron irradiation in the helical reactor FFHR-d1
Author:
Funder
National Institute for Fusion Science
MEXT
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference12 articles.
1. Design activities on helical DEMO reactor FFHR-d1;Sagara;Fusion Eng. Des.,2012
2. Helical reactor design FFHR-d1 and c1 for steady state DEMO;Sagara;Fusion Eng. Des.,2014
3. The torsatron without toroidal field coils as a solution of the divertor problem;Gourdon;Nucl. Fusion,1971
4. Analysis of radiation environment at divertor in helical reactor FFHR-d1;Tanaka;Fusion Eng. Des.,2014
5. Irradiation performance of oxide dispersion strengthened copper alloys to 150dpa at 415°C;Edwards;J. Nucl. Mater.,1992
Cited by 11 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. Visualization of plasma shape in the LHD-type helical fusion reactor, FFHR, by a deep learning technique;Journal of Visualization;2021-08-18
2. Application of the Advanced Multi-Step Brazing for fabrication of the high heat flux component;Journal of Nuclear Materials;2020-09
3. Leak tight joint procedures for ODS-Cu/ODS-Cu by the advanced brazing technique;Fusion Engineering and Design;2019-11
4. Deformation and fracture behavior of the W/ODS-Cu joint fabricated by the advanced brazing technique;Fusion Engineering and Design;2019-09
5. Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1;Journal of Fusion Energy;2018-10-04
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