New neutron cross-section measurements at ORELA and their application in nuclear criticality calculations

Many older neutron cross-section evaluations from libraries such as ENDF/B-VI or JENDL-3.2 show deficiencies in energy ranges that are important for criticality safety applications. Consequently, these evaluated data may not be adequate for nuclear criticality calculations where effects such as self...

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Bibliographic Details
Published inNuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms Vol. 241; no. 1-4; pp. 218 - 222
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 Elsevier B.V 01.12.2005
Subjects
Evaluated data
Neutron capture
Neutron sensitivity
Neutron sources
Weighting function
Neutron sensitivity
25.40.Lw
Evaluated data
Neutron sources
Weighting function
Neutron capture
28.90.+I
28.20.−v
24.30.−v
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Summary:Many older neutron cross-section evaluations from libraries such as ENDF/B-VI or JENDL-3.2 show deficiencies in energy ranges that are important for criticality safety applications. Consequently, these evaluated data may not be adequate for nuclear criticality calculations where effects such as self-shielding, multiple scattering, or Doppler broadening are important. To support the Nuclear Criticality Safety Program, neutron cross-section measurements have been initiated at the Oak Ridge Electron Linear Accelerator (ORELA). ORELA is ideally suited to measure fission, neutron total, and capture cross-sections in the energy range from 1eV to ∼600keV, which is important for many nuclear criticality safety applications.
ISSN:0168-583X
1872-9584
DOI:10.1016/j.nimb.2005.07.083