Published October 2011 | Version v1
Journal article

Tritium permeation, retention and release properties of beryllium pebbles

  • 1. Karlsruhe Institute of Technolog, Campus Nord, IMF I, P.O. Box 3640, 76021 Karlsruhe (Germany)
  • 2. Karlsruhe Institute of Technology, Campus Nord, IMF II, P.O. Box 3640, 76021 Karlsruhe (Germany)
  • 3. Instituto Technologico e Nuclear, 2686-953 Sacavem (Portugal)

Description

Beryllium pebbles of 1 mm diameter produced by Rotating Electrode Method (REM) were exposed to thermodesorption tests after preliminary loading of hydrogen/tritium gas mixture in the temperature range between 973 and 1373 K for 1-12 h. The aim of the work is to clarify the application of the used loading method for modeling of neutron irradiation from the point of view of tritium loading into beryllium samples with bulk uniformity. The formation of surface beryllium oxide layer on pebbles during the loading leads to limitation of tritium/hydrogen permeation into the loaded beryllium pebbles. The thickness of the oxide layers increases with the growth of loading temperature at the investigated temperature area. The optimal loading temperature for beryllium pebbles is supposed to be not higher than 973 K.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2011.01.091

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2011.01.091;
PII
S0920-3796(11)00103-7;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
86
Journal Issue
9-11
Journal Page Range
p. 2338-2342
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
26. symposium on fusion technology
Acronym
SOFT-26
Dates
27 Sep - 1 Oct 2010
Place
Porto (Portugal)

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.