THE RESEARCH REACTORS USED BY THE CEA. A BRIEF REPORT ON THE REACTOR CHARACTERISTICS AND INDICATIONS ON THE GENERAL PROGRAM FOR USE. 3. THE REACTOR TRITON

Journal Article · Thu Aug 01 04:00:00 EDT 1963 · Bull. Inform. Sci. Tech. (Paris)

OSTI ID:4123066

Gilbert, J; Beauge, R

Triton I is a 2-Mw swimming-pool reactor, fueled with MTR type elements, and located at Fontenay-aux-Roses. For experimental purposes, it offers 4 horizontal channels and numerous vertical spaces on the core grid: two are inside the core with a fast neutrons flux of over 10/sup 13/ n/cm/sup 2//sec and nearly twenty are on the core periphery, with a fast neutrons flux of 3 x 10/sup 12/ n/ cm/sup 2//sec and a thermal neutrons flux of 2 x 10/sup 13/ n/cm/sup 2//sec. High-fast andd epithermal neutron fluxes are used especially for structural materials and graphite irradiations. Easy shielding and handling also allow irradiations of short duration and in variable fluxes, either in the liquid nitrogen loop or on andother grid. This reactor also proulces radioisotopes. (auth)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-18-004865
• OSTI ID: 4123066
• Journal Information: Bull. Inform. Sci. Tech. (Paris), Journal Name: Bull. Inform. Sci. Tech. (Paris) Vol. Vol: No. 75
• Country of Publication: Country unknown/Code not available
• Language: French

Related Subjects

CONFIGURATION
DISTRIBUTION
EFFICIENCY
EPITHERMAL NEUTRONS
FAST NEUTRONS
FUEL ELEMENTS
GRAPHITE
IN PILE LOOPS
IRRADIATION
LIQUIDS
LOW TEMPERATURE
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
METALLURGY
MTR
NEUTRON BEAMS
NEUTRON FLUX
NITROGEN
PLANNING
PRODUCTION
RADIATION EFFECTS
RADIOISOTOPES
REACTOR CORE
REACTOR TECHNOLOGY
REMOTE HANDLING
RESEARCH REACTORS
SHIELDING
SPECTRA
THERMAL NEUTRONS
TRITON
TUBES
WATER COOLANT
WATER MODERATOR