Instrumentation for measuring the burnup of spent nuclear fuel
1987; Springer Nature (Netherlands); Volume: 55; Linguagem: Inglês
ISSN
0003-018X
Autores Tópico(s)Nuclear Physics and Applications
ResumoMany different methods or procedures have been developed to measure reactivity of fissil materials. Few of these, however, have been designed specifically for light water reactor fuel or have actually been used to measure the reactivity of spent fuel. The methods that have been used to make measurements of related systems are the /sup 252/Cf source-driven noise analysis method, a noise analysis method using natural neutron sources, subcritical assembly measurements, and pulsed neutron techniques. Several different approaches to directly measuring burnup have been developed by various organizations. The experimental work on actual spent nuclear fuel utilizing reactivity measurement techniques is insufficient to provide conclusive evidence of the applicability of these techniques for verifying fuel burnup. The work with burnup meters indicates, however, that good correlations can be obtained with any of the systems. A burnup meter's primary function would be a secondary assurance that the administrative records are not grossly in error. Reactivity measurements provide information relating to the reactivity of the fuel only under the conditions measured. Criticality prevention design requirements will necessitate that casks accommodate a minimum burnup level for a given initial enrichment (i.e., a maximum reactivity). Direct measurement of the burnup will enable an easy determinationmore » of whether a particular fuel assembly can be shipped in a specific cask with a minimum number of additional correlations.« less
Referência(s)