Conceptual evaluation of nondestructive assay of 233UO2--ThO2 fuel rods (LWBR Development Program)
Description
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 252Cf spontaneous fission neutron source to provide two different interrogating neutron spectra for assay of unirradiated 233UO2--ThO2 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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 43 p.
- Report number
- WAPD-TM--1256
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10473990
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DELAYED NEUTRONS; FUEL ELEMENTS; FUEL SCANNING; LWBR TYPE REACTORS; NONDESTRUCTIVE TESTING; SHIPPINGPORT REACTOR
- Descriptors DEC
- BARYONS; BREEDER REACTORS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; FISSION NEUTRONS; HADRONS; MATERIALS TESTING; NEUTRONS; NUCLEONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS