Physics of the ²⁵²Cf-Source-Driven Noise Analysis Measurement

Conference · Sun Jun 01 00:00:00 EDT 1997

OSTI ID:486154

Valentine, T. E. ^[1]; Mihalczo, J. T. ^[1]; Perez, R. B. ^[1]; Mattingly, J. K. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The ²⁵²Cf-source-driven noise analysis method is a versatile measurements tool that has been applied to measurements for initial loading of reactors, quality assurance of reactor fuel elements, fuel processing facilities, fuel reprocessing facilities, fuel storage facilities, zero-power testing of reactors, verification of calculational methods, process monitoring, characterization of storage vaults, and nuclear weapons identification. This method's broad range of application is due to the wide variety of time- and frequency domain signatures, each with unique properties, obtained from the measurement. The following parameters are obtained from this measurement: average detector count rates, detector multiplicities, detector autocorrelations, cross-correlation between detectors, detector auto power spectral densities, cross-power spectral densities between detectors, coherences, and ratios of spectral densities. All of these measured parameters can also be calculated using the MCNP-DSP Monte Carlo code. This paper presents a review of the time-domain signatures obtained from this measurement.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 486154
• Report Number(s): CONF-970607-3; ON: DE97002985; TRN: 97:010899
• Resource Relation: Conference: ARS '97: American Nuclear Society (ANS) International Meeting on Advanced Reactors Safety, Orlando, FL (United States), 1-5 Jun 1997; Other Information: PBD: [1997]
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
FISSILE MATERIALS
NEUTRON ACTIVATION ANALYSIS
CALIFORNIUM 252
USES
COUNTING RATES
CORRELATIONS
RADIATION SOURCES
RESPONSE FUNCTIONS
TRANSFER FUNCTIONS
CRITICALITY
FUEL CYCLE CENTERS
NEUTRON ACTIVATION ANALYZERS
Nuclear Criticality Safety Program (NCSP)
Reactor Fuel Elements
Fuel Reprocessing Facilities
Fuel Storage Facilities
MCNP-DSP
Monte Carlo Code
Detectors
Rossi-α
Ionization Chamber