Neutron cross section measurements at ORELA for improved nuclear data and their application

To support the Nuclear Criticality Safety Program, the Oak Ridge Electron Linear Accelerator (ORELA) has been used to measure the total and capture neutron cross sections of several nuclides in the energy range from 100 eV to -600 keV. Concerns about the use of existing cross section data in nuclear...

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Bibliographic Details
Published inRadiation protection dosimetry Vol. 116; no. 1-4 Pt 2; p. 579
Main Authors Guber, K H, Leal, L C, Sayer, R O, Koehler, P E, Valentine, T E, Derrien, H, Harvey, J A
Format Journal Article
LanguageEnglish
Published England 20.12.2005
Subjects
Databases, Factual
Fast Neutrons
Linear Energy Transfer
Particle Accelerators
Radiation Dosage
Radiation Protection - methods
Radioisotopes - analysis
Radiometry - methods
Scattering, Radiation
Tennessee
Tennessee
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Summary:To support the Nuclear Criticality Safety Program, the Oak Ridge Electron Linear Accelerator (ORELA) has been used to measure the total and capture neutron cross sections of several nuclides in the energy range from 100 eV to -600 keV. Concerns about the use of existing cross section data in nuclear criticality calculations have been a prime motivator for the new cross-section measurements. Our new capture cross sections of aluminium, silicon, chlorine, fluorine and potassium in the energy range from 100 eV to 600 keV are substantially different from the cross sections in evaluated nuclear data files of ENDF/B-VI and JENDL-3.2.
ISSN:0144-8420
DOI:10.1093/rpd/nci100