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

doi: 10.1093/rpd/nci100
pmid: 16604703
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.
- Oak Ridge National Laboratory United States
- Oak Ridge National Laboratory United States
Radioisotopes, Databases, Factual, Radiation Dosage, Tennessee, Fast Neutrons, Radiation Protection, Scattering, Radiation, Linear Energy Transfer, Particle Accelerators, Radiometry
Radioisotopes, Databases, Factual, Radiation Dosage, Tennessee, Fast Neutrons, Radiation Protection, Scattering, Radiation, Linear Energy Transfer, Particle Accelerators, Radiometry
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