Tritium percolation, convection, and permeation in fusion solid-breeder blankets
Conference
·
· Fusion Technol.; (United States)
OSTI ID:6010998
Models are developed to describe the steadystate percolation of tritium through the solid-breeder interconnected porosity to the purge stream, convection of tritium by the helium purge stream, and permeation of tritium through the structural material to the primary coolant system. Important parameters in the models are tritium generation rate, breeder microstructure, tritium species in the gas phase, temperatures, tritium diffusivities and permeabilities, and effectiveness of oxide barriers. The models are used to perform calculations for fusion-blanket conceptual designs. The results indicate that for isotopic swamping of the purge stream with protium and relatively high oxide impedance factors 100 for nonbreeder-side surfaces) the leakage rate from the blanket can be limited to less than 100 Ci/day for reasonable purge flow rates and pressure drops. However, for lower impedance factors and/or for decreased protium partial pressure in the purge, problems do arise with limiting the tritium leakage.
- Research Organization:
- Fusion Power Program, Argonne National Laboratory, Argonne, IL
- OSTI ID:
- 6010998
- Report Number(s):
- CONF-850310-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 8:1
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CHALCOGENIDES
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
CONTAINMENT
CRYSTAL STRUCTURE
DIFFUSION
FLOW RATE
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MICROSTRUCTURE
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PERMEABILITY
POROSITY
PRESSURE DROP
RADIOISOTOPES
REACTOR COMPONENTS
SIMULATION
STEADY-STATE CONDITIONS
TRITIUM
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BREEDING BLANKETS
CHALCOGENIDES
COMPUTER-AIDED DESIGN
COMPUTERIZED SIMULATION
CONTAINMENT
CRYSTAL STRUCTURE
DIFFUSION
FLOW RATE
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MICROSTRUCTURE
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
PERMEABILITY
POROSITY
PRESSURE DROP
RADIOISOTOPES
REACTOR COMPONENTS
SIMULATION
STEADY-STATE CONDITIONS
TRITIUM
YEARS LIVING RADIOISOTOPES