Implantation measurements to determine tritium permeation in first-wall structures

Conference · Fri Dec 31 23:00:00 EST 1982

OSTI ID:6028712

Holland, D F; Causey, R A; Sattler, M L

A principal safety concern for a D-T burning fusion reactor is release of tritium during routine operation. Tritium implantation into first-wall structures, and subsequent permeation into coolants, is potentially an important source of tritium loss. This paper reports on an experiment in which an ion accelerator was used to implant deuterium atoms in a stainless steel disk to simulate tritium implantation in first-wall structures. The permeation rate was measured under various operating conditions. These results were used in the TMAP computer code to determine potential tritium loss rates for fusion reactors.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA); Virginia Univ., Charlottesville (USA). Dept. of Nuclear Engineering; Virginia Univ., Charlottesville (USA). Dept. of Materials Science
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6028712
• Report Number(s): EGG-M-23482; CONF-830406-70; ON: DE83013548
• 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
CORROSION RESISTANT ALLOYS
DIFFUSION
FIRST WALL
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
PERMEABILITY
RADIOISOTOPES
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
TRITIUM
YEARS LIVING RADIOISOTOPES