THE EFFECT OF REFLECTORS MADE OF VARIOUS MATERIALS ON THE INCREASE OF THE NEUTRON CAPTURE WITHIN THE URANIUM SHIELD OF A FAST-NEUTRON REACTOR

Journal Article · Sun Sep 01 00:00:00 EDT 1963 · At. Energ. (USSR)

OSTI ID:4125533

Golubev, V I; Zvonarev, A V; Nikolaev, M N; Orlov, M Yu

It was found expedient to surround the fertile region of a fast-breeder reactor with a supplementary reflector, in order to reduce the neutron leakage. The material of this reflector must have a high scattering cross section and a relatively low absorption cross section while possessing satisfactory moderating and technical properties, without being unduly expensive. The problem was experimentally investigated with the BR-I reactor. The changes in the number of neutron captures in the fertile zone as the supplementary reflector attached to the depleted U shield was changed were determined. The effect of the various materials was compared at the so-called asymptotic spectrum'' region (A. I. Leipunskii, Atomn. Energ., 5: 277 (1958)). Layers of various thicknesses of Ni, Fe, Cu, stainless steel, Be, and water were placed next to the 57-cm thick U/sup 238/ shield and the radiative neutron capture density near the boundary was determined by the BETA activity of U/sup 239/; the decay and fission products were removed chemically before the measurements. It was found that Fe is the least suitable material because of the deep interference dips in its cross section curve in the resonance energy range. Addition of other elements to the Fe, as in the case of stainless steel, results in the coalescence of the dips, making the alloy more suitable for use as a supplementary reflector. Ni and H/ sub 2/O were found to be satisfactory, as they reduced the leakage by a factor of 2. As expected, Be was found to be the best material, but its high cost is a limiting factor. (TTT)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-18-004700
• OSTI ID: 4125533
• Journal Information: At. Energ. (USSR), Vol. Vol: 15; Other Information: Orig. Receipt Date: 31-DEC-64
• Country of Publication: Country unknown/Code not available
• Language: Russian

Related Subjects

REACTOR TECHNOLOGY
ABSORPTION
ALLOYS
BERYLLIUM
BETA DECAY
BLANKETS
BR-1
BREEDING
BUCKLING
CAPTURE
CHEMICAL REACTIONS
CONFIGURATION
COPPER
CROSS SECTIONS
DISTRIBUTION
ECONOMICS
EFFICIENCY
ENERGY
ENERGY RANGE
FAST NEUTRONS
FERTILE MATERIALS
FISSION PRODUCTS
INTERACTIONS
IRON
LAYERS
LOSSES
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MODERATORS
NEUTRON FLUX
NICKEL
POWER PLANTS
PRODUCTION
RADIOACTIVITY
REACTOR CORE
REFLECTORS
RESEARCH REACTORS
RESONANCE NEUTRONS
SCATTERING
SEPARATION PROCESSES
SLOWDOWN
SPECTRA
STAINLESS STEELS
THICKNESS
URANIUM
URANIUM 238
URANIUM 239
VARIATIONS
WATER
ZONES