Sensitivity and a priori uncertainty analysis of the CFRMF central flux spectrum

Technical Report · Mon Sep 01 04:00:00 EDT 1980

DOI:https://doi.org/10.2172/5135066· OSTI ID:5135066

Ryskamp, J. M.; Anderl, R. A.; Broadhead, B. L.; Ford, III, W. E.; Lucius, J. L.; Marable, J. H.; Wagschal, J. J.

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 (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5135066
• Report Number(s): EGG-PHYS-5243
• Country of Publication: United States
• Language: English

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CROSS SECTIONS
ELEMENTARY PARTICLES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST NEUTRONS
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NEUTRON FLUX
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