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Author Maksyutenko, B. P.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language Russian
Subject Keyword PHYSICS ♦ BORON FLUORIDES ♦ COUNTERS ♦ DECAY ♦ DELAYED NEUTRONS ♦ ENERGY RANGE ♦ FISSION ♦ HALF-LIFE ♦ IRRADIATION ♦ MEV RANGE ♦ NEUTRON BEAMS ♦ NEUTRON FLUX ♦ POLYETHYLENES ♦ THERMAL NEUTRONS ♦ URANIUM 233 ♦ URANIUM 235
Abstract A 3.63-g, 30-mm diameter U/sup 233/ specimen was irradiated in a 15-Mev neutron flux and placed on a polyethylene block containing 10 parallel-coupled BF/ sub 3/-filled counters; simultaneously, the high voltage was turned on. From the total decay curve corresponding to an irradiation of 300 seconds, the relative yields of all the groups were determined at the given half-life values. The thus- derived yield ratio of the first 2 groups was introduced into the equation system of the decay curve corresponding to an irradiation of 30 seconds; this allowed the relative yields of all the groups to be determined. The total yield of the delayed neutrons accompanying the fission of U/sup 233/ by 15.0-Mev neutrons was found to be 1.6 times larger than that of thermal and 3.8Mev neutrons, amounting to 0.780 plus or minus 0.066 of the total yield of delayed neutrons created by the fissioning of U/sup 235/ by thermal neutrons. (TTT)
Educational Use Research
Learning Resource Type Article
Publisher Date 1963-10-01
Journal At. Energ.
Volume Number 15


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