PRELIMINARY DESIGN OF A HIGH FLUX, EPITHERMAL RESEARCH REACTOR FOR THE BROOKHAVEN NATIONAL LABORATORY

Technical Report · Fri Oct 31 04:00:00 EST 1958

OSTI ID:4307287

Auerbach, T; Cbernick, J; Juliens, J; Lellouche, G; Zinn, W

A parametric study of small high flux reactors for experimental purposes was carried out at BNL. Emphasis was placed in obtaining a high intermediate flux in the core and a high thermal flux in the reflector. D/sub 2/O was chosen as the moderator and coolant. The core size is sufficient to allow the simultaneous approach of several beam holes for neutron spectrometny work. The fuel elements are aluminum clad plates of enriched U-Al alloy of the MTR type. With this design and a D/sub 2/O or Be reflector it is expected to get an epithermal flux of about 10/sup 15/n/cm/sup 2/sec. in the core aad a thermal flux of about 10/sup 15/ n/cm/sup 2/sec. in the reflector at a total power ef 20 Mw. Parametric studies were made to determine the effect of varying D/sub 2/O/uranium ratios, H/sub 2/O contamination, varying reflector thickness and different reflector materials on the critical mass and the space and energy dependence of the flux. The effeot of xenon poisoning, as well as the effect of varying spatial distribution of uranium to eliminate the sharp power peak near the core- reflector boundary were also investigated. All calculations employed the multigroup diffusion method and were run on the Univac and the IBM 704. (auth)

• Research Organization: Brookhaven National Lab., Upton, N.Y.; Brussels. Centre d'Etudes pour les Applications de l'Energie Nucleaire.; North Carolina State Coll., Raleigh.; General Nuclear Engineering Corp., Dunedin, Fla.
• NSA Number: NSA-12-014992
• OSTI ID: 4307287
• Report Number(s): A/CONF.15/P/424
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ALUMINUM
ALUMINUM ALLOYS
BERYLLIUM
BROOKHAVEN NATIONAL LABORATOR
BUCKLING
CANNING
COMPUTERS
CONFERENCE
CONFIGURATION
CONTAMINATION
CRITICALITY
EPITHERMAL NEUTRONS
EQUATIONS
FAST NEUTRONS
FUEL ELEMENTS
GROUP THEORY
IBM 704
MASS
MODERATORS
NEUTRON BEAMS
NEUTRON FLUX
NEUTRON SPECTROMETERS
PHYSICS
PLANNING
PLATES
POISONING
PROGRAMMING
REACTIVITY
REACTOR CORE
REFLECTORS
RESEARCH REACTORS
RESONANCE ESCAPE PROBABILITY
THERMAL NEUTRONS
THERMAL UTILIZATION
THICKNESS
TRANSPORT THEORY
TUBES
UNIVAC
URANIUM
URANIUM ALLOYS
VOLUME
WATER
XENON
ZONES