Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Nondestructive assay of spent fuel for determination of residual fissile content

Conference · · Nucl. Mater. Manage.; (United States)
OSTI ID:7247218
A study to determine the feasibility of nondestructive assay (NDA) for residual fissile content in spent fuel assembly was conducted. The conclusion is that a direct NDA of LWR spent fuel assemblies is indeed feasible. The technique is based on inducing fissions in the material and the detection of the former by measurements of the prompt and possibly delayed neutrons. In order to achieve the latter, the fission inducing source has to be removed. Two isotopic sources are readily available with the required intensities--/sup 252/Cf and /sup 124/Sb-Be. For the prompt-neutron technique, less than 100 ..mu..g of /sup 252/Cf or 10 Ci of /sup 124/Sb-Be will be needed. For the delayed neutrons, because of the much poorer signal to background, sources a hundred times stronger are required. Typical measuring time for a LWR assembly would be a couple of hours and the estimated measurement error--mostly due to neutron self-shielding--could be less than 5 percent.
Research Organization:
Science Applications, Inc., Palo Alto, CA
OSTI ID:
7247218
Conference Information:
Journal Name: Nucl. Mater. Manage.; (United States) Journal Volume: 5:3
Country of Publication:
United States
Language:
English

Similar Records

An Evaluation of a Neutron Time Correlated Interrogation Method for Measurement of Fissile Content in Research Reactor Spent Fuel Assemblies
Technical Report · Mon Nov 16 23:00:00 EST 2020 · OSTI ID:1716775

Determining plutonium mass in spent fuel using Cf-252 interrogation with prompt neutron detection
Journal Article · Thu Dec 31 23:00:00 EST 2009 · OSTI ID:1017476

Nondestructive assay methods for irradiated nuclear fuels
Technical Report · Sat Dec 31 23:00:00 EST 1977 · OSTI ID:5153553