Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

The tritium system for a tokamak with a self-pumped limiter

Conference · · Fusion Technol.; (United States)
OSTI ID:6832965
;
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-
Conference Information:
Journal Name: Fusion Technol.; (United States) Journal Volume: 10:3
Country of Publication:
United States
Language:
English

Similar Records

Tritium system for a tokamak reactor with a self-pumped limiter
Conference · Tue Dec 31 23:00:00 EST 1985 · OSTI ID:5442294
Tritium system for a tokamak reactor with a self-pumped limiter
Conference · Tue Dec 31 23:00:00 EST 1985 · Trans. Am. Nucl. Soc.; (United States) · OSTI ID:5577191
Self-pumping impurity by in-situ metal deposition
Conference · Fri Jul 01 00:00:00 EDT 1983 · OSTI ID:5588459

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CIRCULATING SYSTEMS
COATINGS
CONTROL
COOLANTS
DIFFUSION
DIVERTORS
ELEMENTS
FLUIDS
GASES
HELIUM
HYDROGEN ISOTOPES
IMPURITIES
INVENTORIES
ISOTOPES
LAYERS
LIGHT NUCLEI
LIMITERS
MATERIALS
METALS
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
PLASMA
RADIOISOTOPES
RARE GASES
RECYCLING
SELF-PUMPING SYSTEMS
SURFACES
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRAPPING
TRITIUM
VANADIUM ALLOYS
YEARS LIVING RADIOISOTOPES