The tritium system for a tokamak with a self-pumped limiter
The self-pumping concept was proposed as a means of simplifying the impurity control system in a fusion reactor. The idea is to remove helium in-situ by trapping in freshly deposited metal surface layers of a limiter or divertor. Trapping material is added to the plasma scrape-off or edge region where it is transported to the wall. Some of the key issues for this concept are the tritium inventory in the trapping material and the permeation of protium and recycling of tritium. These quantities are shown to be acceptable for the reference design. The tritium issues for a helium-cooled solid breeder reactor design with vanadium alloy as a structural material are also examined. Models are presented for tritium permeation and inventory calculation for structure materials with the effect of a thin layer of coating material.
- Research Organization:
- Argonne National Lab., 9700 South Cass Avenue, FPP-205, Argonne, IL 60439-4837
- OSTI ID:
- 6832965
- Report Number(s):
- CONF-860652-
- Journal Information:
- Fusion Technol.; (United States), Vol. 10:3; Conference: 7. topical meeting on the technology of fusion energy, Reno, NV, USA, 15 Jun 1986
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tritium system for a tokamak reactor with a self-pumped limiter
Physics and technology considerations for the deuterium–tritium fuel cycle and conditions for tritium fuel self sufficiency
Related Subjects
IMPURITIES
CONTROL
LIMITERS
SELF-PUMPING SYSTEMS
TOKAMAK TYPE REACTORS
TRITIUM
DIFFUSION
INVENTORIES
RECYCLING
COATINGS
COOLANTS
DIVERTORS
HELIUM
LAYERS
METALS
PLASMA
SURFACES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TRAPPING
VANADIUM ALLOYS
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CIRCULATING SYSTEMS
ELEMENTS
FLUIDS
GASES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATERIALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
RARE GASES
THERMONUCLEAR REACTORS
YEARS LIVING RADIOISOTOPES
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems
700209 - Fusion Power Plant Technology- Component Development & Materials Testing