Published September 1990 | Version v1
Journal article

MISTRAL: A comprehensive model for tritium transport in lithium-base ceramics. Pt. 2

  • 1. California Univ., Los Angeles (USA). Dept. of Mechanical, Aerospace and Nuclear Engineering

Description

A new tritium transport model called MISTRAL (Model for Investigative Studies of Tritium Release in Lithium Ceramics) has been developed to describe and predict the kinetics of tritium release in lithium ceramic materials for tritium breeding applications in fusion blankets. The model has transient capabilities and has been developed to analyze the full range of transient conditions produced in in-pile tritium recovery experiments and expected in fusion blankets. Calibration of the model against experiments has been done in parallel with its development in order to assess its predictive capabilities and to identify the ranges of potential applicability. The comparisons of the results available for lithium metasilicate and aluminate samples irradiated respectively in the two in-pile tritium recovery experiments LISA1 and MOZART are presented and discussed in this paper. They have been selected for the calibration of the codes as being good examples of various features relevant for tritium release analysis in ceramic breeders under different transient conditions such as change in temperature, purge gas composition and reactor power. (orig.)

Additional details

Additional titles

Subtitle (English)
Comparison of model predictions with experimental results

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
173
Journal Issue
2
Series
J. Nucl. Mater.
Journal Page Range
214-228
ISSN
0022-3115
CODEN
JNUMA

Optional Information

Contract/Grant/Project number
Grant DE-FG03-86ER52123