Blankets for tritium catalyzed deuterium (TCD) fusion reactors

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:7129383

Jung, J; Greenspan, E; Miley, G H

The TCD fusion fuel cycle - where the /sup 3/He from the D(D,n)/sup 3/He reaction is transmuted, by neutron capture in the blanket, into tritium which is fed back to the plasma - was recently recognized as being potentially more promising than the Catalyzed Deuterium (Cat-D) fuel cycle for tokamak power reactors. It is the purpose of the present work to assess the feasibility of, and to identify promising directions for designing blankets for TCD fusion reactors.

• Research Organization: Argonne National Lab., IL (USA); Illinois Univ., Urbana (USA). Fusion Studies Lab.
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7129383
• Report Number(s): CONF-840614-24; ON: DE84006443
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
BREEDING RATIO
CATALYSIS
COMPARATIVE EVALUATIONS
CONVERSION RATIO
DEUTERIUM
EVEN-ODD NUCLEI
FUELS
HELIUM 3
HELIUM ISOTOPES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
STABLE ISOTOPES
THERMONUCLEAR FUELS
TRITIUM
YEARS LIVING RADIOISOTOPES