Effect of the self-pumped limiter concept on the tritium fuel cycle

Conference · Thu Sep 01 00:00:00 EDT 1988 · Fusion Technol.; (United States)

OSTI ID:5699692

Finn, P A; Sze, D K; Hassanein, A

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-
• Journal Information: Fusion Technol.; (United States), Vol. 14:2; Conference: 3. topical meeting on tritium technology in fission, fusion and isotopic applications, Toronto, Canada, 1-6 May 1988
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
LIMITERS
DESIGN
TRITIUM EXTRACTION PLANT
CONTROL SYSTEMS
COST
ECONOMICS
EQUIPMENT
HYDROGEN
IMPURITIES
INVENTORIES
LITHIUM
REACTOR COOLING SYSTEMS
RECYCLING
SAFETY
VANADIUM
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
INDUSTRIAL PLANTS
ISOTOPE SEPARATION PLANTS
METALS
NONMETALS
NUCLEAR FACILITIES
REACTOR COMPONENTS
TRANSITION ELEMENTS
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems
700209 - Fusion Power Plant Technology- Component Development & Materials Testing
700206 - Fusion Power Plant Technology- Environmental Aspects
700204 - Fusion Power Plant Technology- Cooling Systems