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Summary: TRITIUM ANALYSIS OF A WATER-COOLED SOLID
BREEDER BLANKET FOR ITER*
G. Federici, A.R. Raffray, M.A. Abdou
Mechanical,Aerospace and Nuclear Engineering Department
University of California, Los Angeles
Los Angeles, CA 90024-1597.
Mass,(lo6g)
Volume, (m3)
Thickness, (cm)
T. Gen. Rate, (g/day)
Abstract: This paper presents quantitativepredict,ionsfor
the tritium release and inventory in a water-cooled solid breeder
blanket for the InternationalThermonuclearExperimental Reac-
tor (ITER) obtained from the tritium transport code MISTRAL
[l]recently developed at UCLA. The blanket consists of a lay-
out assembly of solid breeder and beryllium multiplier, with two
layers of solid breeder in the outboard region and one layer in
the inboard region [2].The analysis includes steady-stateinven-
tory evaluations as well as transient calculations under assumed
ITER pulsed operation. Different scenarios were investigated
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