Effect of the self-pumped limiter concept on the tritium fuel cycle
Conference
·
OSTI ID:5115934
The self-pumped limiter concept for impurity control of the plasma of a fusion reactor has a major impact on the design of the tritium systems. To achieve a sustained burn, conventional limiters and divertors remove large quantities of unburnt tritium and deuterium from the plasma which must be then recycled using a plasma processing system. The self-pumped limiter which does not remove the hydrogen species, does not require any plasma processing equipment. The blanket system and the coolant processing systems acquire greater importance with the use of this unconventional impurity control system. 3 refs., 2 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5115934
- Report Number(s):
- CONF-880505-17; ON: DE88011237
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DESIGN
FUEL CYCLE
HYDROGEN ISOTOPES
IMPURITIES
ISOTOPES
LIGHT NUCLEI
LIMITERS
NUCLEI
ODD-EVEN NUCLEI
PUMPED LIMITERS
RADIOISOTOPES
THERMONUCLEAR REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DESIGN
FUEL CYCLE
HYDROGEN ISOTOPES
IMPURITIES
ISOTOPES
LIGHT NUCLEI
LIMITERS
NUCLEI
ODD-EVEN NUCLEI
PUMPED LIMITERS
RADIOISOTOPES
THERMONUCLEAR REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES