Tungsten erosion under plasma heat loads typical for ITER type I ELMs and disruptions-Reference-Cited by-同舟云学术

Tungsten erosion under plasma heat loads typical for ITER type I ELMs and disruptions

Published:2005-03 Issue: Volume:337-339 Page:707-711
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Garkusha I.E.,Bandura A.N.,Byrka O.V.,Chebotarev V.V.,Landman I.S.,Makhlaj V.A.,Marchenko A.K.,Solyakov D.G.,Tereshin V.I.,Trubchaninov S.A.,Tsarenko A.V.

Publisher

Elsevier BV

Subject

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

Reference11 articles.

1. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

2. Material erosion and erosion products in disruption simulation experiments at the MK-200 UG facility

3. Macroscopic erosion of divertor and first wall armour in future tokamaks

4. I. Landman et al., these Proceedings. doi:10.1016/j.jnucmat.2004.10.083

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