Tritium permeation, retention and release properties of beryllium pebbles-Reference-Cited by-同舟云学术

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Tritium permeation, retention and release properties of beryllium pebbles

Published:2011-10 Issue:9-11 Volume:86 Page:2338-2342
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Chakin V.,Moeslang A.,Kurinskiy P.,Rolli R.,Schneider H.-C.,Alves E.,Alves L.C.

Publisher

Elsevier BV

Subject

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

Reference12 articles.

1. Development of fusion technology for DEMO in Forschungszentrum Karlsruhe

2. Hydrogen release from reactor-irradiated beryllium

3. Temperature-programmed desorption of tritium loaded into beryllium

4. Thermal and mechanical properties of beryllium pebbles

5. The role of beryllium deuteride in plasma-beryllium interactions

Cited by 9 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. New insights into microstructure of irradiated beryllium based on experiments and computer simulations;Scientific Reports;2020-05-15

2. Novel method for determination of tritium depth profiles in metallic samples;Nuclear Fusion;2019-08-16

3. Effect of heat treatment of titanium beryllide on tritium/hydrogen release;Fusion Engineering and Design;2018-12

4. Structure, tritium depth profile and desorption from ‘plasma-facing’ beryllium materials of ITER-Like-Wall at JET;Nuclear Materials and Energy;2017-08

5. Tritium release from advanced beryllium materials after loading by tritium/hydrogen gas mixture;Fusion Engineering and Design;2016-06

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