NONDESTRUCTIVE ASSAY OF POWER REACTOR FUEL ASSEMBLIES.
作者： C. R. Weisbin , R. H. Augustson , J. S. Hendricks , A. E. Evans , G. D. Turner
DOI: 10.13182/NT72-A16042
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摘要: AbstractThe total 235U content of low enrichment power reactor fuel assemblies has been determined by interrogation with Li(p,n) neutrons (200 to 500 keV) produced a Van de Graaff proton accelerator and measurement fission-induced delayed neutrons. To extend the application this assay technique optimize its implementation, numerical calculations have performed using modified Monte Carlo approach. Experimental measurements from BWR-type assembly verified mathematical model employed. By incorporating results both calculation measurement, system is being designed elements an overall uncertainty within 2%. Using commercially available handling equipment, analysis time for entire element estimated be ∼30 min.
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