Studies of tritium desorption from beryllium and characterization of erosion products under plasma–beryllium interaction-Reference-Cited by-同舟云学术

Studies of tritium desorption from beryllium and characterization of erosion products under plasma–beryllium interaction

Published:1998-09 Issue: Volume:39-40 Page:465-475
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Andreev D.V.,Biryukov A.Yu.,Danelyan L.S.,Elistratov N.G.,Gureev V.M.,Guseva M.I.,Kolbasov B.N.,Kurochkin Yu.Ya.,Nevzorov V.N.,Stativkina O.V.,Zimin A.M.

Publisher

Elsevier BV

Subject

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

Reference8 articles.

1. A.G. Zaluzhnyj, V.N. Sokurskij, V.N. Tebus, Helium in reactor materials, Energoatomizdat, Moscow, 1988, in Russian.

2. Tritium release from irradiated beryllium at elevated temperatures

3. Post-irradiation studies of beryllium reflector of fission reactor examination of gas release, swelling and structure of beryllium under annealing

4. Diffusion/desorption of tritium from irradiated beryllium

5. An improved equation of state for inert gases at high pressures

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