Castellated structures for ITER: Differences of impurity deposition and fuel accumulation in the toroidal and poloidal gaps-Reference-Cited by-同舟云学术

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Castellated structures for ITER: Differences of impurity deposition and fuel accumulation in the toroidal and poloidal gaps

Published:2009-04 Issue: Volume:386-388 Page:809-812
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Litnovsky A.,Philipps V.,Wienhold P.,Krieger K.,Kirschner A.,Borodin D.,Sergienko G.,Schmitz O.,Kreter A.,Samm U.,Richter S.,Breuer U.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference18 articles.

1. A Review of ITER Technology R&D, Fus. Eng. Des. (special issue) 55 (2–3) 2001 (Chapters 3.3 and 3.4).

2. Status of fabrication development for plasma facing components in the EU

3. Tritium retention and clean-up in JET

4. Tritium Removal from Carbon Plasma Facing Components

5. In-Vessel Tritium Retention and Removal in ITER-FEAT

Cited by 7 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. Deposition of carbon inside gaps of castellated tungsten blocks with intrinsic misalignment;Nuclear Materials and Energy;2017-08

2. Optimization of tungsten castellated structures for the ITER divertor;Journal of Nuclear Materials;2015-08

3. Simulation of hydrogen isotope retention in the gap of tungsten divertor tiles;Journal of Nuclear Materials;2013-07

4. Investigations of the origins of deposited carbon species in gaps between divertor tiles using a kinetic code system;Fusion Engineering and Design;2012-08

5. A Kinetic Code System to Study Impurity Deposition and Fuel Retention in Gaps Between Divertor Tiles;Contributions to Plasma Physics;2012-05

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