Abstract:

Removal of Tritium from the Molten Salt Breeder Reactor Fuel 

Authors:

 M.D. Shapiro and C.M. Reed

Consultant:

R.B. Korsmeyer

November 8th, 1970 

Molten Salt Breeder Reactors will produce large quantities of tritium which can permeate most metals at elevated temperatures and thereby contaminate the environment. In this project it was assumed that the tritium can be removed from the salt stream by a hydrogen helium purge and that the helium can be separated for recycle with a palladium membrane. Several systems for concentrating and storing the tritium were conceptualized, designed, and economically evaluated.

Cryogenic distillation of liquid hydrogen appears to be the most economical system. A cryogenic system with a capacity of 4630 gmoles of hydrogen per hour at a 1000-fold tritium enrichment has an estimated capital cost of $328,000 and an estimated annual operating cost of $81,000 (excluding depreciation).

http://egeneration.org/wp-content/Repository/MoltenSalt%20Info/ORNL-MIT-117.pdf

 

Dec 5, 2014   2287   egeneration    Molten Salt Info
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