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2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Christmas Light
’Twas the night before Christmas when all through the house
No electrons were flowing through even my mouse.
All devices were plugged by the chimney with care
With the hope that St. Nikola Tesla would share.
M.C. Billone, C.C. Lin, H. Attaya, Y. Gohar
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 976-983
Blanket Technology | doi.org/10.13182/FST91-A29469
Articles are hosted by Taylor and Francis Online.
The U.S. design for the ITER tritium-breeding blanket consists of layers of Be multiplier, stainless steel cladding, and Li2O ceramic breeder. Tritium is recovered from the ceramic breeder by purging it with He + 0.2% H2. Models have been developed to describe the purge-flow thermal-hydraulics and gas reactions and the tritium retention/release due to lattice diffusion, desorption/adsorption, solubility/precipitation, and percolation through interconnected porosity. These have been incorporated into the steady-state code TIARA for the purpose of performing design calculations for Tritium Inventory and Release Analysis. Transient calculations for pulsed operation are done with a modified version of the DISPL code. The results of both steady-state and transient analyses for tritium retention and release are given for anticipated ITER operating conditions.
