Calculations for isotopically tailored ceramics in fission and fusion reactors
Journal Article
·
· Advanced Ceramic Materials; (USA)
- Los Alamos National Lab., NM (USA)
Ceramics in the 14-MeV neutron environment of a fusion reactor will experience irradiation effects not only from displacement events but also from accumulation of the transmutation gases He and H. Combined damage effects from these sources can be approximated by irradiation testing of isotopically tailored ceramics in a mixed-spectrum fission reactor, where fast neutrons will produce the displacements and thermal neutrons will induce the gas-producing reactions {sup 17}O(n,{alpha}){sup 14}C and {sup 14}N(n,p){sup 14}C. To aid in the design of such an experiment, calculations have been made to determine the amount of the isotopes {sup 17}O and {sup 15}N (the latter to reduce excess production of H) needed in the test ceramic Si{sub 3}Al{sub 3}O{sub 3}N{sub 5} and {sup 17}O (for generation of He only) needed in Al{sub 2}O{sub 3}. Reference irradiation sources were the STARFIRE fusion reactor and the HFIR fission reactor. Results indicate that the desired ratios of gas to displacement energy can be obtained by incorporating 57% {sup 17}O and 90.6% {sup 15}N into sialon, and 17.9% {sup 17}O into alumina.
- OSTI ID:
- 5924095
- Journal Information:
- Advanced Ceramic Materials; (USA), Journal Name: Advanced Ceramic Materials; (USA) Vol. 3:4; ISSN 0883-5551; ISSN ACEME
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALUMINIUM COMPOUNDS
ALUMINIUM NITRIDES
ALUMINIUM OXIDES
CALCULATION METHODS
CHALCOGENIDES
ENERGY RANGE
ENRICHED URANIUM REACTORS
FIRST WALL
HFIR REACTOR
IRRADIATION REACTORS
ISOTOPE ENRICHED MATERIALS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MEV RANGE
MEV RANGE 10-100
NITRIDES
NITROGEN COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
PNICTIDES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SILICON COMPOUNDS
SILICON NITRIDES
STARFIRE TOKAMAK
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALUMINIUM COMPOUNDS
ALUMINIUM NITRIDES
ALUMINIUM OXIDES
CALCULATION METHODS
CHALCOGENIDES
ENERGY RANGE
ENRICHED URANIUM REACTORS
FIRST WALL
HFIR REACTOR
IRRADIATION REACTORS
ISOTOPE ENRICHED MATERIALS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MEV RANGE
MEV RANGE 10-100
NITRIDES
NITROGEN COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
PNICTIDES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SILICON COMPOUNDS
SILICON NITRIDES
STARFIRE TOKAMAK
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS