Integral thermo-mechanical performance analysis of helium-cooled T-tube divertor
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering
Reference18 articles.
1. Creep fatigue analysis of DEMO divertor components following the RCC-MRx design code;Muscat;Fusion Eng. Des.,2023
2. Divertor conceptual designs for a fusion power plant;Norajitra;Fusion Eng. Des.,2008
3. European development of he-cooled divertors for fusion power plants;Norajitra;Nucl. Fusion,2005
4. Recent improvements of the helium-cooled w-based divertor for fusion power plants;Wang;Fusion Eng. Des.,2012
5. Elastic–plastic analysis of the steel-to-tungsten transition joint for a high performance divertor;Navaei;Fusion Eng. Des.,2013
Cited by 1 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. The applicability of high-frequency ultrasonic testing for the inspection of the bonded interface between a divertor's mono-block and screw pipe;Fusion Engineering and Design;2024-08
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