Development of water-cooled blanket concept with pressure tightness against in-box LOCA for JA DEMO
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference12 articles.
1. Simplification of blanket system for SlimCS fusion DEMO reactor
2. Design study of blanket structure based on a water-cooled solid breeder for DEMO
3. Compatibility test between Be12Ti and Li2TiO3
4. Cooling water system design of Japan's DEMO for fusion power production
5. Design Strategy and Recent Design Activity on Japan’s DEMO
Cited by 34 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. Deuterium retention properties of vanadium beryllide (Be12V) for advanced neutron multiplier applications;Fusion Engineering and Design;2024-04
2. Development of water-cooled cylindrical blanket in JA DEMO;Nuclear Fusion;2024-03-06
3. Conceptual design of poloidal horseshoe limiter layout for JA DEMO;Fusion Engineering and Design;2024-02
4. Study on the Li Mass Loss From LTZO in the Blanket;IEEE Transactions on Plasma Science;2024
5. Study on Tritium Permeation from the Primary to the Secondary Water Coolant for Fusion Reactors;Fusion Science and Technology;2023-11-09
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