Evaluation of silicon neutron resonance parameters in the thermal to 1800 keV energy range

Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture...

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Veröffentlicht in:Radiation protection dosimetry 2005-01, Vol.115 (1-4), p.227-231
Hauptverfasser: Derrien, H., Leal, L. C., Guber, K. H., Larson, N. M.
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container_issue 1-4
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container_title Radiation protection dosimetry
container_volume 115
creator Derrien, H.
Leal, L. C.
Guber, K. H.
Larson, N. M.
description Because silicon is a major constituent of concrete and soil, neutron and gamma ray information on silicon is important for reactor shielding and criticality safety calculations. Therefore, much effort was put into the ENDF/B-VI evaluation for the three stable isotopes of silicon. The neutron capture cross section of natural silicon was recently measured at the Oak Ridge Electron Linear Accelerator (ORELA) in the energy range 1–700 keV. Using the ENDF/B-VI evaluation for initial values, a new evaluation of the resonance parameters was performed by adding the results of the ORELA capture measurements to the experimental database. The computer code SAMMY was used for the analysis of the experimental data; the new version of SAMMY allows accurate calculations of the self-shielding and multiple scattering effects in the capture measurements. The accuracy of the radiative capture widths of the resonances was improved by this analysis. Accurate values of the s-, p- and d-wave neutron strength functions were also obtained. Although the resonance capture component of the present evaluation is 2–3 times smaller than that in ENDF/B-VI, the total capture cross section is much larger, at least for energies >250 keV, because the direct capture component contributes values of the same order of magnitude as the resonance component. The direct component was not taken into account in the ENDF/B-VI evaluation and was calculated for the first time in the present evaluation.
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source MEDLINE; Oxford University Press Journals All Titles (1996-Current)
subjects Computer Simulation
Data Interpretation, Statistical
Energy Transfer
Isotopes - analysis
Materials Testing - methods
Models, Chemical
Neutron Diffraction - methods
Neutrons
Radiation Dosage
Radiation Protection - instrumentation
Radiation Protection - methods
Radiometry - methods
Silicon - analysis
title Evaluation of silicon neutron resonance parameters in the thermal to 1800 keV energy range
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