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ELSEXIER Journal of Nuclear Materials 212-215 (1994) 961-965 Modeling of tritium release from beryllium in fusion
 

Summary: ELSEXIER Journal of Nuclear Materials 212-215 (1994) 961-965
Modeling of tritium release from beryllium in fusion
blanket applications
S. Cho, A.R. Raffray, M.A. Abdou
Mechanical, Aerospace, and Nuclear Engineering Department, University of California, Los Angeles, CA 90024-1597, USA
Abstract
Only limited data are available on tritium release from irradiated Be. Few models have been suggested for tritium
release from beryllium. Simple diffusion/desorption models have been proposed, but lack the capability of
accounting for important phenomena such as burst release through interconnected porosity and the effect of the
Be0 impurity layer.
This paper describes the application of a new model for tritium release from Be, BETTY, to the analysis of
recent experimental data. The model includes diffusion through Be and BeO, surface desorption and diffusion
through interconnected porosity (as-fabricated or irradiation-induced). Tritium diffusion and desorption coefficients
for Be and Be0 are estimated from the analysis and compared to previously estimated values.
1. Introduction
Beryllium is considered as both a neutron multiplier
material and a plasma-facing component material for
fusion reactors. Only limited data [l-3] are available
on tritium release from irradiated Be. The data show
that most of the tritium generated is retained in the

  

Source: Abdou, Mohamed - Fusion Science and Technology Center, University of California at Los Angeles
Raffray, A. René - Center for Energy Research, University of California at San Diego

 

Collections: Plasma Physics and Fusion