Open Access
Issue
EPJ Web of Conferences
Volume 111, 2016
WONDER-2015 – 4th International Workshop On Nuclear Data Evaluation for Reactor applications
Article Number 07001
Number of page(s) 8
Section Integral Nuclear data Measurements
DOI https://doi.org/10.1051/epjconf/201611107001
Published online 15 March 2016
  1. P. Leconte et al., MAESTRO: an ambitious experimental programme for the improvement of nuclear data of structural, detection, moderating and absorbing materials - First results for natV, 55Mn, 59Co and 103Rh, Proceedings of the ANIMMA2013 Conference, paper #1376, May 2013, Marseille, France. [Google Scholar]
  2. A. Gruel et al., Integral (n,γ) Cross-sections Measurement of Standard Light Water Reactors Materials, Proceedings of the IGORR2014 conference, Bariloche, Argentina, November 2014. [Google Scholar]
  3. S. Cathalau et al., More than forty years of neutronics experiments in critical facilities of Cadarache center: from EOLE and MINERVE to the future ZEPHYR reactor, Proceedings of the IGORR2014 conference, Bariloche, Argentina, Nov. 2014. [Google Scholar]
  4. G. Bignan et al., Reactor Physics Experiments on Zero Power Reactors, Handbook of Nuclear Engineering, Springer Science, pp 2053–2184, 2010. [CrossRef] [Google Scholar]
  5. A. Santamarina et al., Reactivity Worth Measurement of Major Fission Products in MINERVE LWR Lattice Experiment, Nuclear Science and Engineering, Vol. 178, 4, December 2014, 562-581. [CrossRef] [Google Scholar]
  6. P. Leconte, J.P. Hudelot, M. Antony, Integral Capture rate Measurements of Neutron Absorbers and Minor Actinides by Gamma-Ray Spectrometry on Specific Fuel Samples, Proceedings of the IYNC 2006 Conference, Stockholm, Sweden, June 2006. [Google Scholar]
  7. E. Brun et al., TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code, Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2013, SNA + MC 2013, Volume 82, p 151–160, August 2015. [Google Scholar]
  8. A. Santamarina et al., The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, OECD, NEA No. 6807, 2009. [Google Scholar]
  9. M.B. Chadwick et al., ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology, Nuclear Data Sheets, Vol. 107, 12, p. 2931–3060, December 2006. [NASA ADS] [CrossRef] [Google Scholar]
  10. J.C. Sublet et al., The European Activation File: EAF2010 neutron-induced cross section library, EASY Documentation Series, CCFE-R (10) 05, 2010. [Google Scholar]
  11. A. Gruel et al., Interpretation of Fission Product Oscillations in the MINERVE Reactor, from Thermal to Epithermal Spectra, Nuclear Science and Engineering, 169, 229–244, 2011. [CrossRef] [Google Scholar]
  12. D. Bernard et al., Validation of JEFF-3.1.1 Thermal and Epithermal Neutron-Induced Capture Cross Sections Through MELUSINE Experiment Analysis, Nuclear Science and Engineering, 179, 302–312, 2015. [CrossRef] [Google Scholar]

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