Engineering design of a liquid metal cooled self-pumped limiter for a tokamak reactor
Conference
·
OSTI ID:5701660
A lithium cooled self-pumped limiter has been designed as the impurity control system for the TPSS high-..beta.. power reactor conceptual design. The limiter removes helium by trapping impinging helium ions in freshly deposited vanadium surface layers in a slot region. No hydrogen is removed and no pumps or vacuum penetrations are used, thereby eliminating penetration shielding and reducing tritium handling. The limiter is composed of a vanadium alloy structure with a 2mm tungsten cladding on the front face and leading edges for sputtering control. Up to approx.3cm of vanadium trapping material is deposited in the slot region during 5 years of operation. A key design feature is the use of a calcium oxide electrical insulator which coats the limiter coolant channels to reduce MHD pressure drops. A combination of high lithium coolant velocity, made possible by the insulator, and mid-limiter manifolding has been used to obtain acceptable material temperatures with moderately high heat fluxes (3 to 5 mw/m/sup 2/). Overall, a limiter lifetime of approx.5 years is predicted by stress and lifetime analysis. This would permit maintenance free impurity control operation between first wall/blanket replacement periods. 4 refs., 3 figs., 1 tab.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5701660
- Report Number(s):
- CONF-871007-67; ON: DE88002845
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700204 -- Fusion Power Plant Technology-- Cooling Systems
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
ALLOYS
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
FIRST WALL
FLUIDS
HEAT FLUX
HEAT TRANSFER
INSOLATION
LIMITERS
LIQUID METALS
LIQUIDS
LITHIUM
METALS
PUMPED LIMITERS
STRESS ANALYSIS
THERMAL ANALYSIS
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VANADIUM ALLOYS
700204 -- Fusion Power Plant Technology-- Cooling Systems
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALKALI METALS
ALLOYS
COOLING SYSTEMS
DESIGN
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
FIRST WALL
FLUIDS
HEAT FLUX
HEAT TRANSFER
INSOLATION
LIMITERS
LIQUID METALS
LIQUIDS
LITHIUM
METALS
PUMPED LIMITERS
STRESS ANALYSIS
THERMAL ANALYSIS
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
VANADIUM ALLOYS