Open Access
EPJ Web of Conferences
Volume 42, 2013
WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
Article Number 07006
Number of page(s) 7
Section Poster Session
Published online 18 March 2013
  1. ROSFOND-2010 Library, Institute of Physics and Power Engineering, Obninsk, Russia (2010). Available online at
  2. K. Shibata et al., “JENDL-4.0: A new library for nuclear science and engineering” J. Nucl. Sci. Technol.. 48, pp. 1–30, 2011. [CrossRef]
  3. M.B. Chadwick et al., “ENDF/B-VII.1 Nuclear data for science and technology: cross sections, covariances, fission product yields and decay data,” Nuclear Data Sheets, v.112, 12, 2011 [CrossRef]
  4. The JEFF-3.1.1 Nuclear Data Library, JEFF Report 22, NEA No. 6807, OECD 2009.
  5. S.F. Mughabghab, “Atlas of Neutron Resonances: Thermal Cross Sections and Resonance Parameters”, Elsevier Publisher, Amsterdam, 2006.
  6. Experimental Nuclear Reaction Data (EXFOR / CSISRS),
  7. International Handbook of Evaluated Criticality Safety Benchmark Experiments, OECD/NEA, NEA/NSC/DOC(95)03 (September 2009 Edition)
  8. Yu.E. Golovko, T.T. Ivanova, M.N. Nikilaev et al., VANT, Nuclear Constants, v. 1–2, p.110–125, (2007).
  9. Norman L. Pruvost, Hugh C. Paxton, Nuclear Criticality Safety Guide./ LA-12808, UC-714, (1996)
  10. R.E. MacFarlane et al. NJOY97.0 Code System for Produsing Pointwise and Multigroup Neutron and Photon Sections from ENDF/B Data. RSIC Peripheral Shielding Routine Collection, PSR-368.
  11. Bethe N.A., Beyster J.R., Carter R.E. Inelastic Cross Sections for Fission Spectrum Neutrons – IV, J.Nucl.Energy, 1957, v.4, p,147 (EXFOR SUBENT 11461000).
  12. B.B. Forrest, T.E. Booth et al. “MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Overview and Theory, Volume I”, LA-UR-03-1987, LANL, (2003)