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CX-011547: Categorical Exclusion Determination

Tritium Migration/Control for Advanced Reactor Systems
CX(s) Applied: B3.6
Date: 11/27/2013
Location(s): Ohio
Offices(s): Idaho Operations Office

The Ohio State University proposes to study the mitigation of tritium permeation in the coolant loops of a fluoride salt-cooled High-temperature Reactor (FHR) by proposing a two-loop FHR to eliminate the intermediate third loop.