Behavior of divertor and first wall armour materials at plasma heat fluxes relevant to ITER ELMs and disruptions-Reference-Cited by-同舟云学术

Behavior of divertor and first wall armour materials at plasma heat fluxes relevant to ITER ELMs and disruptions

Published:2017-08 Issue: Volume:12 Page:156-163
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Kovalenko D.V.,Klimov N.S.,Podkovyrov V.L.,Kupriyanov I.B.,Poresanov N.P.,Zabirova N.E.,Bazaleev E.B.,Safronov V.M.,Muzichenko A.D.,Putrik A.B.,Zhitlukhin A.M.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference20 articles.

1. A full tungsten divertor for ITER: Physics issues and design status

2. Disruptions in ITER and strategies for their control and mitigation

3. Hydrogen isotope retention and recycling in fusion reactor plasma-facing components

4. Gas balance and fuel retention in fusion devices

5. Effects of ELMs on ITER divertor armour materials

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1. Comparative Analysis of Spectroscopic Studies of Tungsten and Carbon Deposits on Plasma-Facing Components in Thermonuclear Fusion Reactors;Symmetry;2023-03-01

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3. The structure and properties of modified surface carbon steel by compression plasma flow;Journal of Physics: Conference Series;2018-11

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