The TRIO-01 experiment

Conference · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Technol./Fusion; (United States)

OSTI ID:6203740

Clemmer, R G; Malecha, R F

The TRIO-01 experiment is a comprehensive test of in-situ tritium recovery from a miniaturized solid breeder blanket assembly. Other solid breeder blanket performance factors such as thermal hydraulics, tritium permeation, and gas phase chemistry will be tested as well. The capsule assembly is irradiated in the A2 core position of the Oak Ridge Research Reactor (ORR). Tritium release and recovery is tested by passing a He sweep gas through the solid breeder capsule measuring and collecting the tritium in the sweep stream. The TRIO-01 experiment has extensive on-line monitoring including sweep gas analysis, temperatures, neutron flux, and tritium permeation.

• Research Organization: Argonne National Lab., 9700 South Cass Avenue, Argonne, IL 60439
• OSTI ID: 6203740
• Report Number(s): CONF-830406-
• Conference Information: Journal Name: Nucl. Technol./Fusion; (United States) Journal Volume: 4:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700206 -- Fusion Power Plant Technology-- Environmental Aspects
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
DESIGN
DIFFUSION
ELEMENTS
ENRICHED URANIUM REACTORS
FLUIDS
GAS ANALYSIS
GASES
HELIUM
HYDROGEN ISOTOPES
IRRADIATION
ISOTOPES
LIGHT NUCLEI
MONITORING
NEUTRON FLUX
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
ON-LINE MEASUREMENT SYSTEMS
ON-LINE SYSTEMS
ORR REACTOR
PERFORMANCE TESTING
RADIATION FLUX
RADIATION MONITORING
RADIOISOTOPES
RARE GASES
REACTOR COMPONENTS
REACTORS
RECOVERY
TANK TYPE REACTORS
TEMPERATURE MONITORING
TESTING
TRITIUM
TRITIUM RECOVERY
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES