Sensitivity and a priori uncertainty analysis of the CFRMF central flux spectrum
The Coupled Fast Reactor Measurement Facility (CFRMF), is a zoned-core critical assembly with a fast-neutron-spectrum zone in the center of an enriched U-235, water-moderated thermal driver. The central neutron spectrum is a Cross-Section Evaluation Working Group (CSEWG) benchmark field for data testing of fission-product, actinide, and dosimetry cross sections important to fast reactor technology. The AMPX and FORSS code systems were used to determine a flux covariance matrix for the CFRMF central neutron spectrum due to neutral cross-section and fission-spectrum uncertainties and correlations. Uncertainties in the /sup 238/U inelastic-scattering cross sections and /sup 235/U fission spectrum contribute most to the standard deviations in the central flux spectrum. The full flux-spectrum covariance matrix contains strong correlations. This strongly motivates including the off-diagonal elements in data-testing and cross-section adjustment application.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5135066
- Report Number(s):
- EGG-PHYS-5243; TRN: 80-016736
- Country of Publication:
- United States
- Language:
- English
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CFRMF REACTOR
NEUTRON FLUX
NEUTRON SPECTRA
COMPUTER CALCULATIONS
CROSS SECTIONS
FAST NEUTRONS
NUCLEAR DATA COLLECTIONS
BARYONS
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FERMIONS
HADRONS
NEUTRONS
NUCLEONS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
SPECTRA
ZERO POWER REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors