Tritium handling systems for TFTR and PITR

Conference · Sat Dec 31 23:00:00 EST 1977

OSTI ID:6687980

Lind, K. E.; Yemin, L.; Rossmassler, R.; Phillips, H. O.; Youssef, N. S.; Levine, J. D.; Howe, H. J.; Pierce, C. W.

Operation of the Tokamak Fusion Test Reactor (TFTR) and the proposed Princeton Ignition Test Reactor (PITR) will involve the generation and burning of a deuterium-tritium plasma. Systems associated with both the TFTR and PITR will be designed to minimize the potential release of tritium and other radioisotopes under both routine operational and accidental conditions. Systems have been proposed for the control and processing of large tritium inventories.

• Research Organization: Ebasco Services, Inc., New York (USA); Princeton Univ., NJ (USA). Plasma Physics Lab.
• DOE Contract Number: EY-76-C-02-3073
• OSTI ID: 6687980
• Report Number(s): CONF-780508-34
• Country of Publication: United States
• Language: English

Related Subjects

060200 -- Fusion Fuels-- Processing-- (-1987)
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ACCIDENTS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CONTROL
DEUTERIUM
HYDROGEN ISOTOPES
ISOTOPES
LEAKS
LIGHT NUCLEI
MATERIALS HANDLING
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PROCESSING
RADIOISOTOPES
STABLE ISOTOPES
TFTR REACTORS
THERMONUCLEAR REACTORS
TNS REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES