Accession Number : AD0721076
Title : An Analytical Pulse Reactor Model with Delayed Neutrons.
Descriptive Note : Scientific rept.,
Corporate Author : ARMED FORCES RADIOBIOLOGY RESEARCH INST BETHESDA MD
Personal Author(s) : Leonard,B. E.
Report Date : DEC 1968
Pagination or Media Count : 71
Abstract : The Fuchs-Nordheim model is extended to develop an approximate solution to the point reactor equations of motion which includes delayed neutrons and nonadiabatic systems. Self-limiting reactor excursions are considered. Time-dependent relations for both reactor power and energy generated are obtained. The division of the time domain allows a superposition of the prompt burst and delayed neutron tail powers. The initial delayed neutron tail power is shown to be nearly independent of pulse size. Experimental measurements of TRIGA pulses from 1.00 x beta to 3.21 x beta show only a few percent deviation from theory for the prompt burst and delayed tail powers for pulses above 1.10 x beta. A 16 percent deviation is found for a 1.00 x beta pulse. The theoretical results are provided, with tables and figures, in such a form as to be easily applied to problems requiring self-limiting reactor excursion analysis. (Author)
Descriptors : (*REACTOR REACTIVITY, MATHEMATICAL MODELS), (*RESEARCH REACTORS, RADIOBIOLOGY), NEUTRON BEAMS, EQUATIONS OF MOTION, DIFFERENTIAL EQUATIONS, INTEGRALS, CRITICAL ASSEMBLIES
Subject Categories : Fission Reactor Physics
Distribution Statement : APPROVED FOR PUBLIC RELEASE