University of Hertfordshire

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  • R. Sarmento
  • M. Calviani
  • J. Praena
  • N. Colonna
  • F. Belloni
  • I. F. Goncalves
  • P. Vaz
  • G. Aerts
  • H. Alvarez
  • F. Alvarez-Velarde
  • S. Andriamonje
  • J. Andrzejewski
  • P. Assimakopoulos
  • L. Audouin
  • M. Barbagallo
  • G. Badurek
  • P. Baumann
  • F. Becvar
  • E. Berthoumieux
  • F. Calvino
  • D. Cano-Ott
  • R. Capote
  • C. Carrapico
  • A. Carrillo de Albornoz
  • P. Cennini
  • V. Chepel
  • E. Chiaveri
  • G. Cortes
  • A. Couture
  • J. Cox
  • M. Dahlfors
  • S. David
  • M. Diakaki
  • I. Dillmann
  • R. Dolfini
  • C. Domingo-Pardo
  • W. Dridi
  • I. Duran
  • C. Eleftheriadis
  • L. Ferrant
  • A. Ferrari
  • R. Ferreira-Marques
  • H. Frais-Koelbl
  • K. Fuji
  • W. Furman
  • E. Gonzalez-Romero
  • A. Goverdovski
  • F. Gramegna
  • E. Griesmayer
  • T. Rauscher
  • N TOF Collaboration
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Original languageEnglish
Article number044618
Number of pages10
JournalPhysical Review C
Journal publication date31 Oct 2011
Volume84
Issue4
DOIs
Publication statusPublished - 31 Oct 2011

Abstract

The neutron-induced fission cross section of U-236 was measured at the neutron Time-of-Flight (n_TOF) facility at CERN relative to the standard U-235(n, f) cross section for neutron energies ranging from above thermal to several MeV. The measurement, covering the full range simultaneously, was performed with a fast ionization chamber, taking advantage of the high resolution of the n_TOF spectrometer. The n_TOF results confirm that the first resonance at 5.45 eV is largely overestimated in some nuclear data libraries. The resonance triplet around 1.2 keV was measured with high resolution and resonance parameters were determined with good accuracy. Resonances at high energy have also been observed and characterized and different values for the cross section are provided for the region between 10 keV and the fission threshold. The present work indicates various shortcomings of the current nuclear data libraries in the subthreshold region and provides the basis for an accurate re-evaluation of the U-236(n, f) cross section, which is of great relevance for the development of emerging or innovative nuclear reactor technologies.

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