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ELSEVIER Journal of Nuclear Materials 212-215 (1994)1003-1009 An assessment of models for tritium release from ceramic

Summary: ELSEVIER Journal of Nuclear Materials 212-215 (1994)1003-1009
An assessment of models for tritium release from ceramic
breeders for blanket analysis applications
G. Federici a, A.R. Raffray b, M.C. Billone `, C.H. Wu a, S. Cho b, M.A. Abdou b
aThe NET Team, Max-Planck-Institut fiir Plasmaphysik, Boltzmannstrasse 2, 85748 Garching bei Miinchen, Germany
b Mechanical, Aerospace, and Nuclear Engineering Department, University of California, Los Angeles, Los Angeles,
CA 90024-1597, USA
'Energy Technology Division, Argonne National Laboratory, Argonne, IL 60439-4838, USA
Several models have been proposed and used to analyse the tritium release from ceramic breeder blankets. The
transient models range from single-mechanism types of models to comprehensive, fully integrated models over a
blanket spatial location, including all the key transport mechanisms, as well as local spatial temperature gradients.
This paper considers different models available for analysis of tritium transport in ceramic breeders and performs
a critical assessment of their applicability for blanket analysis and of their limits. Based on the analysis, the type of
model which would be best suited for blanket analysis is described. It combines the possibility of including to a
reasonable extent the effect of key transport mechanisms with the ease of integrating the computations over the
whole blanket space, and provides the capability for both steady state and transient analyses.
1. Introduction
An important aspect of the design and analysis of
ceramic fusion reactor blankets is the ability to predict


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