Effect of the self-pumped limiter concept on the tritium fuel cycle
Conference
·
· Fusion Technol.; (United States)
OSTI ID:5699692
The self-pumped limiter concept was the impurity control system for the reactor in the Tokamak Power Systems Study (TPSS). The use of a self-pumped limiter had a major impact on the design of the tritium systems of the TPSS fusion reactor. The self-pumped limiter functions by depositing the helium ash under a layer of metal (vanadium). The majority of the hydrogen species are recycled at the plasma edge; a small fraction permeates to the blanket/coolant which was lithium in TPSS. Use of the self-pumped limiter results in the elimination of the plasma processing system. Thus, the blanket tritium processing system becomes the major tritium system. The main advantages achieved for the tritium systems with a self-pumped limiter are a reduction in the capital cost of tritium processing equipment as well as a reduction in building space, a reduced tritium inventory for processing and for reserve storage, an increase in the inherent safety of the fusion plant and an improvement in economics for a fusion world economy.
- Research Organization:
- Argonne National Lab., IL (USA)
- OSTI ID:
- 5699692
- Report Number(s):
- CONF-880505-
- Conference Information:
- Journal Name: Fusion Technol.; (United States) Journal Volume: 14:2
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
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Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5577191
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Conference
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·
OSTI ID:6832965
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700204 -- Fusion Power Plant Technology-- Cooling Systems
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700206 -- Fusion Power Plant Technology-- Environmental Aspects
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
CONTROL SYSTEMS
COOLING SYSTEMS
COST
DESIGN
ECONOMICS
ELEMENTS
ENERGY SYSTEMS
EQUIPMENT
HYDROGEN
IMPURITIES
INDUSTRIAL PLANTS
INVENTORIES
ISOTOPE SEPARATION PLANTS
LIMITERS
LITHIUM
METALS
NONMETALS
NUCLEAR FACILITIES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
RECYCLING
SAFETY
TRANSITION ELEMENTS
TRITIUM EXTRACTION PLANT
VANADIUM
700204 -- Fusion Power Plant Technology-- Cooling Systems
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700206 -- Fusion Power Plant Technology-- Environmental Aspects
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
CONTROL SYSTEMS
COOLING SYSTEMS
COST
DESIGN
ECONOMICS
ELEMENTS
ENERGY SYSTEMS
EQUIPMENT
HYDROGEN
IMPURITIES
INDUSTRIAL PLANTS
INVENTORIES
ISOTOPE SEPARATION PLANTS
LIMITERS
LITHIUM
METALS
NONMETALS
NUCLEAR FACILITIES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
RECYCLING
SAFETY
TRANSITION ELEMENTS
TRITIUM EXTRACTION PLANT
VANADIUM