High heat flux testing of mock-ups for a full tungsten ITER divertor-Reference-Cited by-同舟云学术

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High heat flux testing of mock-ups for a full tungsten ITER divertor

Published:2011-10 Issue:9-11 Volume:86 Page:1652-1655
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Gavila P.,Riccardi B.,Constans S.,Jouvelot J.L.,Vastra I. Bobin,Missirlian M.,Richou M.

Publisher

Elsevier BV

Subject

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

Reference7 articles.

1. M. Richou et al., this conference.

2. An operational non-destructive examination technique for ITER Divertor plasma facing components

3. Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components

4. Development of two-colour pyroreflectometry technique for temperature monitoring of tungsten plasma facing components

5. Critical heat flux of water subcooled flow in one-side heated swirl tubes

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1. Inside high-temperature ablation phenomenon and analysis of mechanism of a flat-type W–ZrC/Cu high heat flux mock-up;Fusion Engineering and Design;2024-10

2. Multiscale computational study to predict the irradiation-induced change in engineering properties of fusion reactor materials;Nuclear Materials and Energy;2024-06

3. Impact of creep-fatigue interaction on divertor tungsten under high heat flux;Nuclear Materials and Energy;2023-09

4. Recent progress in research on bonding technologies of W/Cu monoblocks as the divertor for nuclear fusion reactors;Nuclear Materials and Energy;2023-09

5. A new method for characterizing the heat transfer capacity of the divertor and high heat flux components;Nuclear Fusion;2023-07-28

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