Oxides as barriers to tritium permeation in steam generators and tritium content in CTR coolants

Conference · Thu Jan 01 04:00:00 EST 1976

OSTI ID:7331574

Bell, J T; Smith, F J; Redman, J D

The primary release of tritium from a fusion reactor complex into the environment is via the steam generator system. Tritium in the coolant can permeate through the heat exchanger into the steam cycle, and is trapped in the steam as HTO. Subsequent recovery of tritium from the steam is impractical. The amount of tritium that permeates into the steam cycle will depend on the concentration of tritium in the coolant, or more significantly the amount of tritium that can be allowed in the coolant will depend on the rate of tritium permeation that can be tolerated.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7331574
• Report Number(s): CONF-761101-4
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BOILERS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLANTS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
CROLOY
ELEMENTS
HASTELLOY N
HAZARDS
HEALTH HAZARDS
HEAT EXCHANGERS
HEAT RESISTING ALLOYS
HYDROGEN ISOTOPES
INCOLOY 800
INCOLOY ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
METALS
MOLYBDENUM
MOLYBDENUM ALLOYS
NICKEL
NICKEL ALLOYS
NICKEL BASE ALLOYS
NUCLEI
ODD-EVEN NUCLEI
PERMEABILITY
RADIATION HAZARDS
RADIOISOTOPES
RECOVERY
REFRACTORY METALS
REMOVAL
STAINLESS STEEL-304
STAINLESS STEELS
STEAM GENERATORS
STEELS
THERMONUCLEAR REACTOR COOLING SYSTEMS
TRANSITION ELEMENTS
TRITIUM
TRITIUM RECOVERY
VAPOR GENERATORS
YEARS LIVING RADIOISOTOPES