Published October 1983 | Version v1
Report Restricted

Application of new techniques to ORELA neutron-transmission measurements and their uncertainty analysis: the case of natural nickel from 2 keV to 20 MeV

Description

The neutron transmission through a 2.54-cm sample of natural nickel has been measured for neutron energies between 2 keV and 20 MeV. Known background sources are described, and the methods used to correct for these backgrounds are presented. An in-depth uncertainty analysis is given for this measurement, with explicit formulas derived for each effect contributing to the cross-section uncertainty. Parameters uncertainties and correlations among the parameters describing the backgrounds, deadtime, and other sources of uncertainty are given. To obtain a covariance matrix for this measurement, the final cross-section results are binned into 15 energy groups, and covariance matrix is provided for this 15-group set. We find that the largest contributions to the cross-section uncertainty are due to sample properties, beam monitors (used to normalize sample-in and sample-out counts), and ORELA power variations during the run which affect the deadtime correction. Overall uncertainties in the cross section for this measurement are on the order of 2%. The resulting cross sections are compared with the ENDF/B-V file for nickel; many resonances not presently in the file are observed, and energy-scale differences are noted

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC E05/MF A01 as DE84002265.

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Additional details

Publishing Information

Imprint Pagination
123 p.
Report number
ORNL/TM--8203

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15032278
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
CROSS SECTIONS; ENERGY DEPENDENCE; ERRORS; EXPERIMENTAL DATA; NEUTRON TRANSPORT; NICKEL; NUCLEAR DATA COLLECTIONS; ORELA
Descriptors DEC
ACCELERATORS; DATA; ELEMENTS; INFORMATION; LINEAR ACCELERATORS; METALS; NEUTRAL-PARTICLE TRANSPORT; NUMERICAL DATA; RADIATION TRANSPORT; TRANSITION ELEMENTS

Optional Information

Secondary number(s)
ENDF--333.