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Tritium detectors employed at the Tokamak Fusion Test Reactor

Journal Article · · Fusion Technol.; (United States)
OSTI ID:6033855
In preparation for deuterium-tritium operations at the Tokamak Fusion Test Reactor (TFTR) in 1991, Princeton University, Plasma Physics Laboratory has developed a real-time tritium monitoring system. The system employs a variety of different monitors, the purpose of which is to provide tritium concentration levels for personnel protection, process streams, and stack effluent monitoring.
Research Organization:
Princeton Univ., Plasma Physics Lab., Princeton, NJ (US)
OSTI ID:
6033855
Journal Information:
Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 14:2; ISSN FUSTE
Country of Publication:
United States
Language:
English

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Related Subjects

61 RADIATION PROTECTION AND DOSIMETRY
655001 -- Medical Physics-- Radiation Protection Standards
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
700206 -- Fusion Power Plant Technology-- Environmental Aspects
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DEUTERIUM
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNETIC SHIELDING
MONITORING
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PERSONNEL
PHYSICS
PLASMA
RADIATION PROTECTION
RADIOISOTOPES
REAL TIME SYSTEMS
SHIELDING
STABLE ISOTOPES
TFTR TOKAMAK
THERMAL EFFLUENTS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES