TFTR tritium handling concepts

Technical Report · Mon Sep 01 04:00:00 EDT 1975

OSTI ID:5237919

Garber, H J

The Tokamak Fusion Test Reactor, to be located on the Princeton Forrestal Campus, is expected to operate with 1 to 2.5 MA tritium-deuterium plasmas, with the pulses involving injection of 50 to 200 Ci (5 to 21 mg) of tritium. Attainment of fusion conditions is based on generation of an approximately 1 keV tritium plasma by ohmic heating and conversion to a moderately hot tritium-deuterium ion plasma by injection of a ''preheating'' deuterium neutral beam (40 to 80 keV), followed by injection of a ''reacting'' beam of high energy neutral deuterium (120 to 150 keV). Additionally, compressions accompany the beam injections. Environmental, safety and cost considerations led to the decision to limit the amount of tritium gas on-site to that required for an experiment, maintaining all other tritium in ''solidified'' form. The form of the tritium supply is as uranium tritide, while the spent tritium and other hydrogen isotopes are getter-trapped by zirconium-aluminum alloy. The issues treated include: (1) design concepts for the tritium generator and its purification, dispensing, replenishment, containment, and containment-cleanup systems; (2) features of the spent plasma trapping system, particularly the regenerable absorption cartridges, their integration into the vacuum system, and the handling of non-getterables; (3) tritium permeationthrough the equipment and the anticipated releases to the environment; (4) overview of the tritium related ventilation systems; and (5) design bases for the facility's tritium cleanup systems.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
• DOE Contract Number: EY-76-C-02-3073
• OSTI ID: 5237919
• Report Number(s): WFPS-TME-005
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CLEANING
CONTAINMENT
COST
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS HANDLING
NUCLEI
ODD-EVEN NUCLEI
PERMEABILITY
RADIOISOTOPES
RECOVERY
SAFETY
TFTR REACTOR
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
TRITIUM RECOVERY
VENTILATION
YEARS LIVING RADIOISOTOPES