Implantation measurements to determine tritium permeation in first wall structures

Conference · Thu Sep 01 00:00:00 EDT 1983 · Nucl. Technol./Fusion; (United States)

OSTI ID:6263729

Holland, D F; Causey, R A

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./Fusion Technology, P.O. Box 1625, Idaho Falls, ID 83415
• OSTI ID: 6263729
• Report Number(s): CONF-830406-
• Journal Information: Nucl. Technol./Fusion; (United States), Journal Name: Nucl. Technol./Fusion; (United States) Vol. 4:2; ISSN NTFUD
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ABSORPTION
ACCELERATORS
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHARGED PARTICLES
CHROMIUM ALLOYS
COMPUTER CODES
CORROSION RESISTANT ALLOYS
D-T REACTORS
DEUTERIUM IONS
DIFFUSION
ENERGY ABSORPTION
FIRST WALL
HYDROGEN ISOTOPES
ION IMPLANTATION
IONS
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LIGHT NUCLEI
LOSSES
MEASURING METHODS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
SIMULATION
STAINLESS STEELS
STEELS
T CODES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES