Ion-gun tritium-permeation testing

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6553781

Longhurst, G R; Holland, D F; Miller, L G; Causey, R A

There is considerable uncertainty within the fusion community regarding the rate at which tritium will permeate fusion-reactor structures and coolant streams. Present estimates vary by several orders of magnitude. Experiments to resolve this uncertainty are in progress at several laboratories. Many of these experiments make use of ion sources to accomplish light-ion implantation, provide surface sputtering, and assist in diagnostic analyses. In one such experiment at the Idaho National Engineering Laboratory (INEL), deuterium was implanted into Type 304 stainless steel at 753 K. Measurements of the deuterium permeation rate showed that implantation effects strongly influence permeation of oxidized surfaces, but that continued implantation with its attendant surface modification resulted in diminution of implantation effects.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6553781
• Report Number(s): EGG-M-15482; CONF-821165-1; ON: DE83005587
• 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
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
COOLANTS
CORROSION RESISTANT ALLOYS
DEUTERIUM
DIFFUSION
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HYDROGEN ISOTOPES
ION IMPLANTATION
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
MATERIALS
NICKEL ALLOYS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PERMEABILITY
RADIOISOTOPES
STABLE ISOTOPES
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
TRITIUM
YEARS LIVING RADIOISOTOPES