Blanket materials for DT fusion reactors

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:6360820

Smith, D L

This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of blanket technology are summarized. The candidate materials are listed for the different blanket components, e.g., breeder, coolant, structure and neutron multiplier. Three blanket concepts that appear to offer the most potential are: (1) liquid-metal breeder/coolant, (2) liquid-metal breeder/separate coolant, and (3) solid breeder/separate coolant. The major uncertainties associated with each of the design concepts are discussed and the key materials R and D requirements for each concept are identified.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6360820
• Report Number(s): CONF-810831-105; ON: DE83009029
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
COOLANTS
COST
ELEMENTS
FABRICATION
FLUIDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LIQUID METALS
LIQUIDS
LITHIUM
MAINTENANCE
MATERIALS
MATERIALS TESTING
METALS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES