BR-2 THE BELGIAN MATERIALS AND ENGINEERING TEST REACTOR

Technical Report · Sat Oct 31 04:00:00 EST 1959

OSTI ID:4256548

Dopchie, H; Planquart, J

The BR-2 reactor, which should become critical around the end of 1959, will be light-water-cooled and -moderated, fueled with uranium enriched to 90%. Its cylindrical fuel elements, imbedded in a beryllium matrix, constitute a nest in the form of an hyperboloid of revolution. The reactor has been designed to facititate the manipulation of the fuel elements and the experiments. Besides fuel elements, control rods, beryllium plugs, and experiments can occupy any position in the matrix. The reactor is described, and the reasons for the choice of its type are given. Its characteristics and experimental facilities are discussed. The research and development necessitated by its new design and described. Its safely is examined. (auth)

• Research Organization: Centre d'Etude de l'Energie Nucleaire, Brussels
• NSA Number: NSA-13-007161
• OSTI ID: 4256548
• Report Number(s): A/CONF.15/P/1679
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BERYLLIUM
BR-2
CONFIGURATION
CONTROL ELEMENTS
CYLINDERS
EFFICIENCY
FUEL ELEMENTS
IRRADIATION
MATERIALS TESTING
MEASURED VALUES
MECHANICAL STRUCTURES
NEUTRON BEAMS
NEUTRON FLUX
PLANNING
REACTOR CORE
REACTOR FUELING
REACTOR SAFETY
REACTORS
RESEARCH REACTORS
RODS
STARTUP
URANIUM
WATER COOLANT
WATER MODERATOR
ZONES