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

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:5115934

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

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
• Resource Relation: Conference: 3. topical meeting on tritium technology in fission, fusion and isotopic applications, Toronto, Canada, 1 May 1988
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
PUMPED LIMITERS
DESIGN
THERMONUCLEAR REACTORS
FUEL CYCLE
IMPURITIES
TRITIUM
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LIMITERS
NUCLEI
ODD-EVEN NUCLEI
RADIOISOTOPES
YEARS LIVING RADIOISOTOPES
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700205 - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems