Tritium recovery from some ceramic breeding materials-Reference-Cited by-同舟云学术

Tritium recovery from some ceramic breeding materials

Published:1989-01 Issue: Volume:8 Page:359-364
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Kwast H.,Kout A.,Muis R.P.,Stijkel M.P.,Flipot A.J.,Elen J.D.

Publisher

Elsevier BV

Subject

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

Reference16 articles.

1. In-pile tritium release from LiAlO2, Li2SiO3 and Li2O in EXOTIC Experiments 1 and 2;Kwast;J. Nucl. Mater,1986

2. Tritium release from various solid breeding materials;Kwast,1986

3. Tritium release from various solid breeder materials irradiated in EXOTIC experiments 1, 2 and 3;Kwast;J. Nucl. Mater.,1988

4. Relationship between fabrication parameters and structure characteristics of sintered lithium metasilicate;Flipot;J. Nucl. Mater.,1986

5. The preparation, characterization and properties of lithium oxide and lithium metazirconate specimens irradiated in HFR-Petten in the second and third EXOTIC experiments;Kennedy,1986

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1. Modeling and analysis of time-dependent tritium transport in lithium oxide;Journal of Nuclear Materials;1999-06

2. Ab initio Hartree–Fock study on surface desorption process in tritium release;Journal of Nuclear Materials;1998-10

3. Tritium desorption study from Li2O by ab initio calculation;Fusion Engineering and Design;1998-09

4. Advanced understanding of the tritium recovery process from the ceramic breeder blanket;Journal of Nuclear Materials;1997-09

5. Design Study of Sweep Gas System for Fusion Blanket Development in the JMTR;Fusion Technology;1995-10