Ceramic breeder materials

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:5607501

Johnson, C E; Kummerer, K R; Roth, E

Ceramic materials are under investigation as potential breeder material in fusion reactors. This paper will review candidate materials with respect to fabrication routes and characterization, properties in as-fabricated and irradiated condition, and experimental results from laboratory and inpile investigations on tritium transport and release. Also discussed are the resources of beryllium, which is being considered as a neutron multiplier. The comparison of ceramic properties that is attempted here aims at the identification of the most-promising material for use in a tritium breeding blanket. 82 refs., 12 figs., 5 tabs.

• Research Organization: Argonne National Lab., IL (USA); Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.); CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5607501
• Report Number(s): CONF-871036-12; ON: DE88002966
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METAL COMPOUNDS
ALKALINE EARTH METALS
ALUMINIUM COMPOUNDS
BERYLLIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CERAMICS
CHEMICAL REACTIONS
COMPRESSION STRENGTH
CORROSION
CRACKING
CREEP
DECOMPOSITION
ELEMENTS
EXPANSION
FABRICATION
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
MATERIALS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
METALS
NUCLEI
ODD-EVEN NUCLEI
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
PYROLYSIS
RADIATION EFFECTS
RADIOISOTOPES
REACTOR COMPONENTS
STRESSES
THERMAL CONDUCTIVITY
THERMAL CRACKING
THERMAL EXPANSION
THERMAL STRESSES
THERMOCHEMICAL PROCESSES
THERMODYNAMIC PROPERTIES
THERMONUCLEAR REACTOR MATERIALS
TRITIUM
YEARS LIVING RADIOISOTOPES
YOUNG MODULUS