BEATRIX-II: In situ tritium test

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6473484

Baker, D E ^[1]; Kuraswa, T ^[2]; Miller, J M ^[3]; Slagle, O D ^[4]

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

The BEATRIX-II irradiation experiment is an in-situ tritium release experiment being carried out in the Fast Flux Test Facility (FFTF) reactor to evaluate the tritium release characteristics of fusion solid breeder materials. A sophisticated tritium gas handling system has been developed to continuously monitor the tritium recovery from the specimens and facilitate tritium removal from the experiment's sweep gas flow stream. The in-situ recovery experiment accommodates two different in-reactor specimen canisters with individual gas streams and temperature monitoring/control. Ionization chambers have been specifically designed to respond to the rapid changes in the tritium release rate at the anticipated tritium concentrations. Two ceramic electrolysis cells have proved effective in reducing the moisture in the gas streams to hydrogen/tritium. A tritium getter system, capable of reducing the tritium level by a factor greater than 4000, is used to reduce the tritium in the sweep gas to a level acceptable for release.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6473484
• Report Number(s): PNL-SA-18617; CONF-901007-30; ON: DE91005184; TRN: 91-000119
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TRITIUM RECOVERY
MONITORING
BREEDING BLANKETS
DESIGN
FFTF REACTOR
IONIZATION CHAMBERS
NEUTRON REACTIONS
OPERATION
THERMONUCLEAR REACTOR MATERIALS
BARYON REACTIONS
EPITHERMAL REACTORS
FAST REACTORS
HADRON REACTIONS
LIQUID METAL COOLED REACTORS
MATERIALS
MEASURING INSTRUMENTS
NUCLEAR REACTIONS
NUCLEON REACTIONS
RADIATION DETECTORS
REACTOR COMPONENTS
REACTORS
RECOVERY
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems
700209 - Fusion Power Plant Technology- Component Development & Materials Testing