MCNP-DSP Calculations of the 252Cf-Source-Driven Noise Analysis Measurements of Highly Enriched Uranium Metal Cylinders
Conference
·
OSTI ID:96845
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division
This paper presents calculations of the 252Cf-source-driven noise analysis measurements for subcritical highly enriched uranium metal cylinders using the Monte Carlo code MCNP-DSP. This code directly calculates the noise analysis data from the 252Cf-source-driven noise analysis method for both neutron and gamma ray detectors. Direct calculation of experimental observables by the Monte Carlo method allows for the benchmarking of the calculational model and the cross sections and for determining the bias in the calculation.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Instrumentation and Controls Division
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 96845
- Report Number(s):
- CONF-9509100--3; ON: DE95014579
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
Autopower Spectral Densities (APSDs)
BENCHMARKS
CALIFORNIUM 252
CRITICALITY
CROSS SECTIONS
Cross-Power Spectral Densities (CPSDs)
Evaluated Nuclear Data File (ENDF)
Fissile Material
HIGHLY ENRICHED URANIUM
M CODES
MCNP-DSP
MONTE CARLO METHOD
MULTIPLICATION FACTORS
Monte Carlo Code
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
Neutron and Gamma Ray Detectors
Nuclear Criticality Safety Program (NCSP)
PROMPT NEUTRONS
SPECTRAL DENSITY
97 MATHEMATICS AND COMPUTING
Autopower Spectral Densities (APSDs)
BENCHMARKS
CALIFORNIUM 252
CRITICALITY
CROSS SECTIONS
Cross-Power Spectral Densities (CPSDs)
Evaluated Nuclear Data File (ENDF)
Fissile Material
HIGHLY ENRICHED URANIUM
M CODES
MCNP-DSP
MONTE CARLO METHOD
MULTIPLICATION FACTORS
Monte Carlo Code
NEUTRON TRANSPORT
NUCLEAR DATA COLLECTIONS
Neutron and Gamma Ray Detectors
Nuclear Criticality Safety Program (NCSP)
PROMPT NEUTRONS
SPECTRAL DENSITY