INEL integral data-testing report for ENDF/B-V dosimeter cross sections
An integral data-testing study done at the Idaho National Engineering Laboratory (INEL) for ENDF/B-V dosimeter cross sections is documented. The integral data base used is a set of spectrum-averaged cross sections derived from integral reaction rates measured for 23 dosimeter reactions. The measured integral reaction-rate data were obtained from irradiation experiments in the fast neutron field of the Coupled Fast Reactivity Measurements Facility (CFRMF). Up-to-date values for the integral reaction rates are compiled and the derivation of a consistent set of spectrum-averaged cross sections is documented. The central neutron field of the CFRMF is characterized and specified by including the results of neutronics calculations with ENDF/B-IV and ENDF/B-V nuclear data, active neutron spectrometry measurements, and a sensitivity and uncertainty analysis for the spectrum. A scheme for generating 620-group fluxes from the 68-group fluxes obtained from a transport calculation is described. Results of the following computations are included here: (1) calculations of spectrum-averaged cross sections for various CFRMF flux spectra, cross-section data bases and different weighting functions, (2) estimation of the flux and dosimeter cross-section uncertainty contributions to the uncertainty in the calculated integral cross sections, and (3) characterization of the energy response for each dosimeter reaction in the CFRMF. Integral tests, as defined by the ratio of calculated-to-measured integral cross sections, are assessed for each dosimeter reaction with respect to reaction energy response, uncertainty considerations, spectrum shape changes and weighting function effects.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5803319
- Report Number(s):
- EGG-PHYS-5608; ON: DE82004743; TRN: 82-005108
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALUMINIUM 27 TARGET
NEUTRON REACTIONS
BORON 10 TARGET
CROSS SECTIONS
EVALUATED DATA
COBALT 59 TARGET
COPPER 63 TARGET
DOSEMETERS
GOLD 197 TARGET
INDIUM 115 TARGET
IRON 54 TARGET
IRON 58 TARGET
LITHIUM 6 TARGET
NEPTUNIUM 237 TARGET
NEUTRON DETECTORS
NICKEL 58 TARGET
PLUTONIUM 239 TARGET
SCANDIUM 45 TARGET
THORIUM 232 TARGET
TITANIUM 46 TARGET
TITANIUM 47 TARGET
TITANIUM 48 TARGET
URANIUM 235 TARGET
URANIUM 238 TARGET
CAPTURE
CHARGE-EXCHANGE REACTIONS
ENERGY DEPENDENCE
EXPERIMENTAL DATA
FISSION
NEUTRON DOSIMETRY
PICKUP REACTIONS
RESPONSE FUNCTIONS
WEIGHTING FUNCTIONS
BARYON REACTIONS
DATA
DIRECT REACTIONS
DOSIMETRY
FUNCTIONS
HADRON REACTIONS
INFORMATION
MEASURING INSTRUMENTS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
RADIATION DETECTORS
TARGETS
TRANSFER REACTIONS
440102* - Radiation Instrumentation- Radiation Dosemeters
651000 - Nuclear Physics