Material and Power-Handling Properties of Tungsten PFCs after Steady-State Melting and Additional Transient High-Heat-Flux Exposure-Reference-Cited by-同舟云学术

Material and Power-Handling Properties of Tungsten PFCs after Steady-State Melting and Additional Transient High-Heat-Flux Exposure

Published:2012-02 Issue:2 Volume:61 Page:129-135
ISSN:1536-1055
Container-title:Fusion Science and Technology
language:en
Short-container-title:Fusion Science and Technology

Author:

Coenen J. W.¹,Bazylev B.²,Brezinsek S.¹,Philipps V.¹,Hirai T.³,Kreter A.¹,Linke J.¹,Pintsuk G.¹,Sergienko G.¹,Pospieszczyk A.¹,Tanabe T.⁴,Ueda Y.⁵,Samm U.¹,Team The Textor¹

Affiliation:

1. Institute for Energy and Climate Research, Forschungszentrum Jülich, EURATOM Association Trilateral Euregio Cluster, Jülich, Germany

2. Institut für Hochleistungsimpuls und Mikrowellentechnik, Forschungszentrum Karlsruhe GmbH Association Euratom-FZK, Karlsruhe, Germany

3. ITER Organization, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance, France

4. Kyushu University, Interdisciplinary Graduate School of Engineering Science Hakozaki 6-10-1, Higashiku, Fukuoka 812-8581, Japan

5. Osaka University, Graduate School of Engineering, Osaka 565-0871, Japan

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST12-A13378

Reference23 articles.

1. Main chamber sources and edge transport of tungsten in H-mode plasmas at ASDEX Upgrade

2. Calculation and experimental test of the cooling factor of tungsten

3. Physics basis and design of the ITER plasma-facing components

4. Analysis of tungsten melt-layer motion and splashing under tokamak conditions at TEXTOR

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1. MEMOS 3D modelling of ELM-induced transient melt damage on an inclined tungsten surface in the ASDEX Upgrade outer divertor;Nuclear Materials and Energy;2018-12

2. Transient induced tungsten melting at the Joint European Torus (JET);Physica Scripta;2017-09-15

3. Material testing facilities and programs for plasma-facing component testing;Nuclear Fusion;2017-06-09

4. Baseline high heat flux and plasma facing materials for fusion;Nuclear Fusion;2017-06-09

5. Surface heat loads on the ITER divertor vertical targets;Nuclear Fusion;2017-03-08