BEATRIX-II: In situ tritium recovery from Li[sub 2]O and Li[sub 2]ZrO[sub 3] irradiated in a fast neutron flux

Conference · Tue Sep 01 00:00:00 EDT 1992

OSTI ID:7173710

Slagle, O D; Hollenberg, G W ^[1]; Kurasawa, T ^[2]; Verrall, R A ^[3]

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1. Pacific Northwest Lab., Richland, WA (United States)
2. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research
3. Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Labs.

The BEATRIX-II irradiation experiment was an in situ, fast neutron, tritium release experiment to evaluate the performance of ceramic fusion solid breeders at extended burnups. The experiment consisted of two sequential irradiations: Phase I for 300 EFPD and Phase II for 200 EFPD that resulted in lithium burnups from 4[endash]6%. Thin-walled Li[sub 2]O ring specimens capable of temperature changes were irradiated in both Phase I and Phase II. Temperature changes were also used to determine the tritium inventory and to characterize the effect or irradiation history and sweep gas composition. Solid-cylindrical temperature-gradient specimens were irradiated to characterize their stability with respect to heat transport, lithium transport and physical integrity over the duration of the experiment. Phase I included a solid monolithic specimen of Li[sub 2]O while Phase II included a sphere bed of Li[sub 2]ZrO[sub 3].

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 7173710
• Report Number(s): PNL-SA-20872; CONF-920930-12; ON: DE93001560; TRN: 92-038328
• Resource Relation: Conference: 17. symposium on fusion technology, Rome (Italy), 14-18 Sep 1992
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Fu
Ma
BREEDING BLANKETS
PERFORMANCE TESTING
LITHIUM OXIDES
TRITIUM RECOVERY
THERMONUCLEAR REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
CERAMICS
IRRADIATION
NEUTRON FLUX
TEMPERATURE DEPENDENCE
TEMPERATURE GRADIENTS
ZIRCONIUM OXIDES
ALKALI METAL COMPOUNDS
CHALCOGENIDES
LITHIUM COMPOUNDS
MATERIALS
OXIDES
OXYGEN COMPOUNDS
RADIATION EFFECTS
RADIATION FLUX
REACTOR COMPONENTS
TESTING
TRANSITION ELEMENT COMPOUNDS
ZIRCONIUM COMPOUNDS
700450* - Fusion Technology- Blankets & Cooling Systems- (1992-)
700460 - Fusion Technology- Heating & Fueling Systems
Fuels- (1992)
700480 - Fusion Technology- Component Development
Materials Studies- (1992-)