Extensive Set of Low-Fidelity Covariances in Fast Neutron Region
- Brookhaven National Lab. (BNL), Upton, NY (United States)
An extensive set of covariances for neutron cross sections has been developed to provide initial, low fidelity but consistent uncertainty data for nuclear criticality safety applications. The methodology for the determination of such covariances in fast neutron region is presented. It combines the nuclear reaction code EMPIRE, which calculates sensitivity to nuclear reaction model parameters and the Bayesian code KALMAN to propagate uncertainty of the model parameters onto cross sections. Taking into account the large scale of the project (219 fission products), only partial reference to experimental data has been made. Therefore, the covariances are, to a large extent, derived from the perturbation of several critical model parameters selected through the sensitivity analysis. They define optical potential, level densities and pre-equilibrium emission. This exercise represents the first attempt to generate nuclear data covariances on such a scale.
- Research Organization:
- Brookhaven National Laboratory (BNL), Upton, NY (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Science (SC), Nuclear Physics (NP)
- DOE Contract Number:
- AC02-98CH10886
- OSTI ID:
- 920080
- Report Number(s):
- BNL--79512-2007-CP; KB0301041
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
ACCELERATORS
Advanced Fuel Cycle Initiative (AFCI)
Associated Fuel Cycles
Bayesian Code
CRITICALITY
CROSS SECTIONS
DATA COVARIANCES
EMPIRE
Evaluated Nuclear Data File (ENDF)
FAST NEUTRONS
FISSION
Global Nuclear Energy Partnership (GNEP)
Incident Neutron Energy (MeV)
KALMAN
NEUTRONS
NUCLEAR REACTIONS
Nuclear Criticality Safety Program (NCSP)
SAFETY
SENSITIVITY
SENSITIVITY ANALYSIS
97 MATHEMATICS AND COMPUTING
ACCELERATORS
Advanced Fuel Cycle Initiative (AFCI)
Associated Fuel Cycles
Bayesian Code
CRITICALITY
CROSS SECTIONS
DATA COVARIANCES
EMPIRE
Evaluated Nuclear Data File (ENDF)
FAST NEUTRONS
FISSION
Global Nuclear Energy Partnership (GNEP)
Incident Neutron Energy (MeV)
KALMAN
NEUTRONS
NUCLEAR REACTIONS
Nuclear Criticality Safety Program (NCSP)
SAFETY
SENSITIVITY
SENSITIVITY ANALYSIS