Tritium inventory and permeation in the ITER breeding blanket

Citation
V. Violante et al., Tritium inventory and permeation in the ITER breeding blanket, FUSION ENG, 49, 2000, pp. 697-701
Citations number
7
Categorie Soggetti
Nuclear Emgineering
Journal title
FUSION ENGINEERING AND DESIGN
ISSN journal
09203796 → ACNP
Volume
49
Year of publication
2000
Pages
697 - 701
Database
ISI
SICI code
0920-3796(200011)49:<697:TIAPIT>2.0.ZU;2-F
Abstract
A model has allowed us to perform the analysis of the tritium inventory and permeation in the international thermonuclear experimental reactor (ITER) breeding blanket under the hypothesis of steady state conditions. Li2ZrO3 ( reference) and Li2TiO3 (alternative) have been studied as breeding material s. The total breeder inventory assessed is 7.64 g for the Li2ZrO3 at refere nce temperature. The model has also been used for a parametric analysis of the tritium permeation. At reference temperature and purge helium velocity of 0.01 m/s, the HT partial pressure is ranging from 10 to 30 Pa in the bre eder and 1.5 x 10(-3) Pa in the beryllium. At 0.1 mis of purge helium veloc ity, the HT partial pressure is reduced of one order by magnitude in the br eeder and becomes 5 x 10(-5) Pa in the beryllium. The tritium permeation in to the coolant for the whole blanket is ranging from 100 to 250 mCi per day for purge helium velocity of 0.01 mis. The analysis of the tritium invento ry and permeation for the alternative Li2TiO3 breeding material has been ca rried out too;The tritium inventory in the breeder is in the range from 6 t o 375 g larger than in Li2ZrO3 by about a factor 5; the tritium permeation into coolant is comparable to the Li2ZrO3 one. This analysis provides indic ations on the influence of the operating parameters on the tritium control in the ITER breeding blanket; particularly the control of the tritium inven tory by the temperature and the tritium permeation by the purge gas velocit y. (C) 2000 Elsevier Science B.V. All rights reserved.