Conceptual design of tritium breeding blanket for INTOR
The paper describes the U.S. reference design for the tritium breeding blanket for INTOR. Details of the blanket conceptual mechanical design are presented, together with a discussion of thermal, structural, and mechanical aspects and the rationale for selection of key design features. The INTOR design was required to use a solid tritium breeding compound, Li/sub 2/SiO/sub 3/; a solid lead neutron multiplier; low temperature, low pressure water coolant; helium purge gas for tritium removal; and Type 316 austenitic stainless steel. A key feature of the U.S. design is the minimization of tritium inventory, obtained through the use of a graphite neutron moderator to reduce the required amount of breeder, and the use of tailored gap conductance values to keep the breeder in the optimum temperature range for tritium release.
- Research Organization:
- McDonnell Douglas Astronaut Co, St. Louis, MO, USA
- OSTI ID:
- 6482155
- Report Number(s):
- CONF-811040-
- Journal Information:
- Proc. Symp. Eng. Probl. Fusion Res.; (United States), Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States); ISSN PSERD
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360103 -- Metals & Alloys-- Mechanical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
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ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DESIGN
ELEMENTS
FIRST WALL
FLUIDS
GASES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM
INTOR TOKAMAK
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
RARE GASES
REACTOR COMPONENTS
RECOVERY
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM RECOVERY