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

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Abstract

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 1 eV to ∼600 keV, which is important for many nuclear criticality safety applications.

Original languageEnglish
Pages (from-to)218-222
Number of pages5
JournalNuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms
Volume241
Issue number1-4
DOIs
StatePublished - Dec 2005

Funding

ORNL is managed by UT-Battelle, LLC, for the U.S. Department of Energy under contract no. DE-AC05-00OR22725.

Keywords

  • Evaluated data
  • Neutron capture
  • Neutron sensitivity
  • Neutron sources
  • Weighting function

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