Irradiation experiment design for in-situ tritium recovery for Li sub 2 O and Li sub 2 ZrO sub 3 -BEATRIX-II, Phase 2

Conference · Wed May 01 00:00:00 EDT 1991

OSTI ID:5710449

Slagle, O D ^[1]; Takahashi, T ^[2]; Sullivan, J D ^[3]; Knight, R C ^[4]

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1. Pacific Northwest Lab., Richland, WA (USA)
2. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
3. Atomic Energy of Canada Ltd., Chalk River, ON (Canada)
4. Westinghouse Hanford Co., Richland, WA (USA)

BEATRIX-II is an irradiation experiment designed to study the in situ tritium release behavior from selected ceramic solid breeder materials. The second irradiation cycle of the experiment, Phase 2, will include a temperature change capsule with a ring specimen of Li{sub 2}O and a temperature gradient capsule with Li{sub 2}ZrO{sub 3} spheres. The temperature change capsule is designed to achieve temperatures in the range from 485 to 650{degrees}C while the temperature gradient capsule will include a temperature range from 450 to 1200{degrees}C. The effect of specimen temperature, sweep gas composition, and sweep gas flow rate on the tritium recovery behavior will be determined in a fast neutron flux to burnups of 8%. 15 refs., 8 figs., 2 tabs.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 5710449
• Report Number(s): PNL-SA-19030; CONF-910430-5; ON: DE91012878
• Resource Relation: Conference: 93. annual meeting and exposition of the American Ceramic Society (ACerS), Cincinnati, OH (USA), 28 Apr - 2 May 1991
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TRITIUM RECOVERY
EXPERIMENT PLANNING
BREEDING BLANKETS
IRRADIATION CAPSULES
LITHIUM OXIDES
TEMPERATURE GRADIENTS
THERMONUCLEAR REACTOR MATERIALS
ALKALI METAL COMPOUNDS
CHALCOGENIDES
LITHIUM COMPOUNDS
MATERIALS
OXIDES
OXYGEN COMPOUNDS
PLANNING
REACTOR COMPONENTS
RECOVERY
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