Process and system for removing tritium

Details Process and system for removing tritium Process and system for removing tritium

1973-10-31

1976-02-10

Pendegrass, Verlin R.

Compositions

Radioactive compositions

Nuclear reactor fuel

176 37, 176 54, 55 68, 2523011W, G21C 1700

Patent

active

039376494

ABSTRACT:
A process and system for removing tritium, particularly from high temperature gas cooled atomic reactors (HTGR), is disclosed. Portions of the reactor coolant, which is permeated with the pervasive tritium atom, are processed to remove the tritium. Under conditions of elevated temperature and pressure, the reactor coolant is combined with gaseous oxygen, resulting in the formation of tritiated water vapor from the tritium in the reactor coolant and the gaseous oxygen. The tritiated water vapor and the remaining gaseous oxygen are then successively removed by fractional liquefaction steps. The reactor coolant is then re-circulated to the reactor.

REFERENCES:
patent: 3208200 (1965-09-01), Gant et al.
patent: 3400048 (1968-09-01), Boardman et al.
patent: 3679366 (1972-07-01), Benson et al.
patent: R27598 (1973-03-01), Wright
Monitoring Reactor Effluents For Tritium: Problems & Possibilities, Osborne, Chalk River Nucl. Labs, Chalk River, Ontario, Canada, Sept., 1971.

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