Fabrication, properties, and tritium recovery from solid breeder materials
Conference
·
OSTI ID:5710587
- Argonne National Lab., IL (USA)
- Japan Atomic Energy Research Inst., Tokyo (Japan)
- CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)
- Tokyo Univ. (Japan)
- Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.)
The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was recognized by the International Thermonuclear Experimental Reactor (ITER) design team in its selection of ceramics as the first option for the ITER breeder material. Blanket design studies have indicated properties in the candidate materials data base that need further investigation. Current studies are focusing on tritium release behavior at high burnup, changes in thermophysical properties with burnup, compatibility between the ceramic breeder and beryllium multiplier, and phase changes with burnup. Laboratory and in-reactor tests, some as part of an international collaboration for development of ceramic breeder materials, are underway. 133 refs., 1 fig.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5710587
- Report Number(s):
- ANL/CP-72923; CONF-910615--2; ON: DE91012478
- Country of Publication:
- United States
- Language:
- English
Similar Records
Ceramic breeder materials
Research and development status of ceramic breeder materials
Ceramic breeder materials
Conference
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:6745605
Research and development status of ceramic breeder materials
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:5215004
Ceramic breeder materials
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5607501
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BREEDING BLANKETS
CERAMICS
CHALCOGENIDES
DAMAGING NEUTRON FLUENCE
DESIGN
FABRICATION
LITHIUM COMPOUNDS
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
RECOVERY
SILICON COMPOUNDS
SILICON OXIDES
SOL-GEL PROCESS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENT COMPOUNDS
TRITIUM RECOVERY
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
ALKALI METAL COMPOUNDS
ALUMINIUM COMPOUNDS
ALUMINIUM OXIDES
BREEDING BLANKETS
CERAMICS
CHALCOGENIDES
DAMAGING NEUTRON FLUENCE
DESIGN
FABRICATION
LITHIUM COMPOUNDS
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
RECOVERY
SILICON COMPOUNDS
SILICON OXIDES
SOL-GEL PROCESS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRANSITION ELEMENT COMPOUNDS
TRITIUM RECOVERY
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES