Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures-Reference-Cited by-同舟云学术

Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures

Published:2021-01 Issue: Volume:162 Page:112100
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Alimov V.Kh.,Torikai Y.,Hatano Y.,Schwarz-Selinger T.

Funder

Russian Science Foundation

Publisher

Elsevier BV

Subject

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

Reference34 articles.

1. the ASDEX upgrade team, deuterium inventory in the full-tungsten divertor of ASDEX upgrade;Sugiyama;Nucl. Eng.,2010

2. Key ITER plasma edge and plasma-material interaction issues;Federici;J. Nucl. Mater.,2003

3. Investigation of hydrogen recycling in long-duration discharges and its modification with a hot wall in the spherical tokamak QUEST;Hanada;Nucl. Eng.,2017

4. Failure study of helium-cooled tungsten divertor plasma-facing units tested at DEMO relevant steady-state heat loads;Ritz;Phys. Scr. T,2009

5. Neutron irradiation effects on plasma facing materials;Barabash;J. Nucl. Mater.,2000

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