Conceptual evaluation of nondestructive assay of /sup 233/UO/sub 2/--ThO/sub 2/ fuel rods (LWBR Development Program)

Technical Report · Mon Jan 01 04:00:00 EST 1979

OSTI ID:6441333

Stooksberry, R W; Emert, C J; Milani, S; Basinger, G J

Measurements have been undertaken at the Bettis Atomic Power Laboratory to determine the potential of the delayed neutron assay method for precision end-of-life fuel rod assay. A pre-pilot system has been built using a /sup 252/Cf spontaneous fission neutron source to provide two different interrogating neutron spectra for assay of unirradiated /sup 233/UO/sub 2/--ThO/sub 2/ fuel rods. A thermal neutron interrogating spectrum produced the largest number of delayed neutron counts per single rod assay. Neutron self-shielding in the fuel can be taken into account using a flux dip technique. An epithermal system using an indium cadmium liner exhibited a linear system response as a function of fuel rod loading.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, PA (USA)
• DOE Contract Number: EY-76-C-11-0014
• OSTI ID: 6441333
• Report Number(s): WAPD-TM-1256
• Country of Publication: United States
• Language: English

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