Scoping studies of tritium handling in a tokamak experimental power reactor
Conference
·
OSTI ID:4155277
Tritium handling techniques in an experimental fusion power reactor (EPR) are evaluated to determine the requirements of the system and to compare different equipment and techniques for meeting those requirements. Tritium process equipment is needed to (1) evacuate and maintain a vacuum in the plasma vessel and the neutral beam injectors, (2) purify and recycle tritium and deuterium for the plasma fuel cycle, (3) recover tritium from experimental breeding modules, and (4) provide tritium containment and atmospheric cleanup. A development program is outlined to develop and demonstrate the required techniques and equipment and to permit confident design of an EPR for operation by the mid-1980s. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- NSA Number:
- NSA-33-007100
- OSTI ID:
- 4155277
- Report Number(s):
- CONF-751125--46
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*THERMONUCLEAR REACTORS-- TRITIUM RECOVERY
700206* --Fusion Energy--Fusion Power Plant Technology-- Tritium Processing
Environment & Safety
DESIGN
DEUTERIUM
N70800* --Physics--Controlled Thermonuclear Research-- Thermonuclear Engineering & Equipment
NEUTRAL ATOM BEAM INJECTION
OPERATION
TRITIUM
700206* --Fusion Energy--Fusion Power Plant Technology-- Tritium Processing
Environment & Safety
DESIGN
DEUTERIUM
N70800* --Physics--Controlled Thermonuclear Research-- Thermonuclear Engineering & Equipment
NEUTRAL ATOM BEAM INJECTION
OPERATION
TRITIUM