Potential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components-Reference-Cited by-同舟云学术

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Potential approach of IR-analysis for high heat flux quality assessment of divertor tungsten monoblock components

Published:2017-11 Issue: Volume:124 Page:202-206
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Greuner Henri,Böswirth B.,Maier H.,Hirai T.,Panayotis S.,Crescenzi F.,Roccella S.,Visca E.,Missirlian M.,Richou M.

Funder

Euratom research and training programme

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference20 articles.

1. Overview and status of ITER internal components

2. The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER

3. Conceptual design studies for the European DEMO divertor: Rationale and first results

4. Status of technology R&D for the ITER tungsten divertor monoblock

5. J. Boscary, et al. Summary of the Production of the Divertor Target Elements of Wendelstein 7-X, this conference.

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. Armor Thickness Assessment for the Divertor Tokamak Test Facility (DTT) Divertor Targets;IEEE Transactions on Plasma Science;2024

2. An ITER Challenge Absolute Surface Temperature Measurements of Low and Varying Emissivity Tungsten Plasma-Facing Components;IEEE Transactions on Plasma Science;2020-07

3. Manufacturing and testing of ITER-like divertor plasma facing mock-ups for DEMO;Fusion Engineering and Design;2018-11

4. Effect of induction heating on flaw generation and expansion;Fusion Engineering and Design;2018-11

5. FEM and thermal fatigue testing comparison of ITER-like divertor PFUs mock-ups for DEMO;Fusion Engineering and Design;2018-11

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