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Feasibility of Subcriticality and NDA Measurements for Spent Fuel by Frequency Analysis Techniques with 252Cf

Conference ·
OSTI ID:228510
 [1];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division, Measurement Science Section
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The 252Cf-source-driven frequency analysis method can be used for measuring the subcritical neutron multiplication factor of arrays of LWR fuel and as little as a single PWR fuel assembly. These measurements can be used to verify the criticality safety margins of spent LWR fuel configurations and thus could be a means of obtaining the information to justify burnup credit for spent LWR transportation/storage casks. In addition, the data can be used to validate calculational methods for criticality safety. These measurements provide parameters that have a higher sensitivity to changes in fissile mass than neutron multiplication factor and thus serve as a better test of calculational methods. The analysis has also shown that measurement of the cross power spectral density (CPSD) between detectors on one side of a single fuel assembly and an internal or external 252Cf source driving the fission chain multiplication process can be used for nondestructive assay of fissile mass along the length of the assembly. This CPSD is a smooth function of fissile mass and does not depend on the varying inherent source in the fuel assembly and thus is ideal for fissile mass assay.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division, Measurement Science Section
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AC05-96OR22464
OSTI ID:
228510
Report Number(s):
CONF-960521--6; ON: DE96009718
Country of Publication:
United States
Language:
English

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Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
CRITICALITY
Cross Power Spectral Density (CPSD)
Evaluated Nuclear Data File (ENDF)
FISSILE MATERIALS
FUEL STORAGE POOLS
Light Water Reactor (LWR)
MULTIPLICATION FACTORS
Monte Carlo Methods
NONDESTRUCTIVE ANALYSIS
Neutron Multiplication Factor
Nondestructive Assay (NDA)
Nuclear Criticality Safety Program (NCSP)
Pressurized Water Reactor (PWR)
SPENT FUELS
Single Fuel Assembly