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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
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.
