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MaterialSELSEVIER Journal of Nuclear Materials 210(1994)143-160 Modeling of tritium transport in ceramic breeder single crystal
 

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MaterialSELSEVIER Journal of Nuclear Materials 210(1994)143-160
Modeling of tritium transport in ceramic breeder single crystal
A. RenC Raffray, Seungyon Cho, Mohamed A. Abdou
Mechanical, Aerospace and Nuclear Engineering Department, University of California, Los Angeles, CA 90024-1597, USA
(Received 2 August 1993;accepted 7 January 1994)
Abstract
Simple existing models were found not to adequately reproduce recent tritium release data for LiAlO, single
crystal, indicating the need for a more comprehensive model. To help understand and interpret the data, a new
model, MISTRAL-SC, was developed, incorporating bulk diffusion as well as the four major surface processes, and
allowing for the variation of surface activation energies with coverage and for the presence of H, in the purge. The
model is described in this paper and an analysis of the single crystal data presented. Based on the analysis a bulk
diffusion coefficient for tritium diffusing in LiAlO, is estimated and compared to previous estimated values from
past experiments. Discrepancies are discussed and recommendations are proposed for values of the diffusion
coefficient to be used in LiAlO, experiment and blanket analyses, and for future work.
1. Introduction
One of the key issues for ceramic breeder blankets

  

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