The heat removal capability of actively cooled plasma-facing components for the ITER divertor
Author:
Publisher
IOP Publishing
Subject
Condensed Matter Physics,Mathematical Physics,Atomic and Molecular Physics, and Optics
Link
http://stacks.iop.org/1402-4896/2011/i=T145/a=014080/pdf
Reference10 articles.
1. Testing of high heat flux components manufactured by ENEA for ITER divertor
2. Characteristics of an optimized active metal cast joint between copper and C/C
3. Fatigue lifetime of repaired high heat flux components for ITER divertor
4. Results and analysis of high heat flux tests on a full-scale vertical target prototype of ITER divertor
5. Recent development toward the use of infrared thermography as a non destructive technique for defect detection in tungsten plasma facing components
Cited by 10 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. Sustained W-melting experiments on actively cooled ITER-like plasma facing unit in WEST;Physica Scripta;2021-11-08
2. Qualification and post-mortem investigation of actively cooled tungsten flat-tile mock-ups for WEST divertor;Fusion Engineering and Design;2018-11
3. Tungsten covered graphite and copper elements and ITER-like actively cooled tungsten divertor plasma facing units for the WEST project;Physica Scripta;2016-01-21
4. Elaboration and thermomechanical characterization of W/Cu functionally graded materials produced by Spark Plasma Sintering for plasma facing components;Fusion Engineering and Design;2015-10
5. The WEST project: Current status of the ITER-like tungsten divertor;Fusion Engineering and Design;2014-10
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