Investigation of gamma and neutron fields around spent reactor fuel by 115In activation

✍ Scribed by L. Lakosi; Zs. Németh; I. Pavlicsek; Á. Veres

• Publisher: Elsevier Science
• Year: 1990
• Weight: 615 KB
• Volume: 41
• Category: Article
• ISSN: 0883-2889
• DOI: 10.1016/0883-2889(90)90097-z

✦ Synopsis

Activation methods based on (;I,?' ) and (n.7) processes have been developed for investigating hard ;' and thermal neutron radiation fields in the vicinity of spent fuel assemblies stored in water. Based on experiments and practical considerations "'In was suggested as a target material both for 'J and neutron activations.

Fission product and actinide content of irradiated fuel can be assayed by these methods. The use of (r,n) conversion in Be or D provides an additional tool for analyzing hard 7' components. The methods may find application in non-destructive fuel assay. Results suggest the suitability of the methods for reactor operational and nuclear material safeguard purposes