1. Nondestructive Assay of Power Reactor Fuel Assemblies
- Author
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A.E. Evans, R. H. Augustson, John S. Hendricks, C. R. Weisbin, K. D. Böhnel, and G. D. Turner
- Subjects
Nuclear and High Energy Physics ,Chemistry ,020209 energy ,Nuclear engineering ,Monte Carlo method ,Analytical chemistry ,Particle accelerator ,02 engineering and technology ,Power reactor ,Condensed Matter Physics ,law.invention ,Thorium fuel cycle ,020303 mechanical engineering & transports ,0203 mechanical engineering ,Nuclear Energy and Engineering ,law ,0202 electrical engineering, electronic engineering, information engineering ,Van de Graaff generator ,Neutron ,Physics::Chemical Physics ,Nondestructive assay ,Delayed neutron - Abstract
The 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 by a Van de Graaff proton accelerator and by measurement of fission-induced delayed neutrons. To extend the application of this assay technique and to optimize its implementation, numerical calculations have been performed using a modified Monte Carlo approach. Experimental measurements from a BWR-type fuel assembly have verified the mathematical model employed. By incorporating results from both calculation and measurement, a system is being designed to assay the total 235U content of power reactor fuel elements with an overall uncertainty within 2%. Using commercially available fuel handling equipment, the analysis time for the entire element is estimated to be ∼30 min.
- Published
- 1972
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