New neutron cross section measurements at ORELA for improved nuclear data

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

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The Oak Ridge Electron Linear Accelerator (ORELA) was used to measure neutron total and capture cross sections of aluminum, silicon, chlorine, fluorine, and potassium in the energy range from 100 eV to ∼600 keV. These measurements were carried out to support the Nuclear Criticality Safety Program (NCSP). 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 results are substantially different from the evaluated nuclear data files of ENDF/B-VI and JENDL-3.2.

Original languageEnglish
Title of host publicationProceedings of the PHYSOR 2004
Subtitle of host publicationThe Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Pages1937-1941
Number of pages5
StatePublished - 2004
EventPHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments - Chicago, IL, United States
Duration: Apr 25 2004Apr 29 2004

Publication series

NameProceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments

Conference

ConferencePHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Country/TerritoryUnited States
CityChicago, IL
Period04/25/0404/29/04

Keywords

  • Al
  • Cl
  • F
  • K
  • Neutron capture cross section
  • Neutron sensitivity
  • Si
  • Transmission

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