CFRMF spectrum update and application to dosimeter cross-section data testing

Technical Report · Fri Jan 01 00:00:00 EST 1982

OSTI ID:5309227

Anderl, R A; Harker, Y D; Millsap, D A; Rogers, J W; Ryskamp, J M

The Coupled Fast Reactivity Measurements Facility (CFRMF) at the Idaho National Engineering Laboratory (INEL) is a Cross Section Evaluation Working Group (CSEWG) benchmark for data testing of dosimetry, fission-product and actinide cross sections important to fast-reactor technology. In this paper we present the results of our work in updating the CFRMF spectrum characterization and in applying CFRMF integral data to testing ENDF/B-V dosimeter cross sections. Updated characterization of the central neutron spectrum includes the results of neutronics calculations with ENDF/B-V nuclear data, the generation of a fine-group spectrum representation for integral data-testing applications, and a sensitivity and uncertainty analysis which provides a flux-spectrum covariance matrix related to uncertainties and correlations in the nuclear data used in a neutronics calculation. Our application of CFRMF integral data to cross section testing has included both conventional integral testing analyses and least-squares-adjustment analyses with the FERRET code. The conventional integral data-testing analysis, based on C/E ratios, indicates discrepancies outside the estimated integral test uncertainty for the /sup 6/Li(n,He), /sup 10/B(n,He), /sup 47/Ti(n,p), /sup 58/Fe(n,..gamma..), /sup 197/Au(n,..gamma..) and /sup 232/Th(n,..gamma..) cross sections. The integral test uncertainty included contributions from the measured integral data and from the spectrum and cross sections used to obtain the calculated integral data. Within the uncertainty and correlation specifications for the input spectrum and dosimeter cross sections, the least-squares-adjustment analysis indicated a high degree of consistency between the measured integral data and the ENDF/B-V dosimeter cross sections for all reactions except /sup 10/B(n,He).

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5309227
• Report Number(s): EGG-M-08182; CONF-820321-27; ON: DE82016346
• Resource Relation: Conference: 4. ASTM-EURATOM symposium on reactor dosimetry, Gaithersburg, MD, USA, 22 Mar 1982; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

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NEUTRON SPECTRA
FISSION FOIL DETECTORS
NEUTRON DOSIMETRY
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MEASURING INSTRUMENTS
NEUTRON DETECTORS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
NUMERICAL SOLUTION
RADIATION DETECTORS
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