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

K. H. Guber, L. C. Leal, R. O. Sayer, P. E. Koehler, T. E. Valentine, H. Derrien, J. A. Harvey

Research output: Contribution to journalArticlepeer-review

13 Scopus citations

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.

FundersFunder number
U.S. Department of Energy
Oak Ridge National Laboratory

    Keywords

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

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