Failure study of helium-cooled tungsten divertor plasma-facing units tested at DEMO relevant steady-state heat loads-Reference-Cited by-同舟云学术

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Failure study of helium-cooled tungsten divertor plasma-facing units tested at DEMO relevant steady-state heat loads

Published:2009-12 Issue: Volume:T138 Page:014064
ISSN:0031-8949
Container-title:Physica Scripta
language:
Short-container-title:Phys. Scr.

Author:

Ritz G,Hirai T,Norajitra P,Reiser J,Giniyatulin R,Makhankov A,Mazul I,Pintsuk G,Linke J

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Mathematical Physics,Atomic and Molecular Physics, and Optics

Link

http://stacks.iop.org/1402-4896/2009/i=T138/a=014064/pdf

Reference19 articles.

1. Modular He-cooled divertor for power plant application

2. Development of a helium-cooled divertor concept: design-related requirements on materials and fabrication technology

3. Development of fusion technology for DEMO in Forschungszentrum Karlsruhe

4. He-cooled divertor for DEMO: Experimental verification of the conceptual modular design

5. Fabrication of a He-cooled divertor module for DEMO reactor

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. Conceptual design and heat transfer performance of a flat-tile water-cooled divertor target;Plasma Science and Technology;2021-07-23

2. Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures;Fusion Engineering and Design;2021-01

3. Tungsten as a Plasma-Facing Material;Comprehensive Nuclear Materials;2020

4. Tungsten oxide thin film bombarded with a low energy He ion beam: evidence for a reduced erosion and W enrichment;Physica Scripta;2017-09-19

5. Tungsten oxide thin film exposed to low energy He plasma: Evidence for a thermal enhancement of the erosion yield;Journal of Nuclear Materials;2017-02

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