Open Access
Issue
EPJ Web of Conferences
Volume 42, 2013
WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
Article Number 03003
Number of page(s) 5
Section Uncertainties and Covariance Matrices
DOI https://doi.org/10.1051/epjconf/20134203003
Published online 18 March 2013
  1. A. Santamarina, et al, “The JEFF – 3.1.1 Nuclear Data Library, JEFF Report” 22, NEA No. 6807 (2009).
  2. M. Herman, “Development of ENDF/B-VII.1 and Its Covariance Components”, Journal of the Korean Physical Society, 59, pp.1034–1039 (2011).
  3. K. Shibata et al., “JENDL-4.0: A New Library for Innovative Nuclear Energy Systems,” Journal of the Korean Physical Society, 59, pp.1046–1051 (2011).
  4. “SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation, Version 6”, ORNL/TM-2005/39 (2009).
  5. B.T. Rearden and D.E. Mueller, “Uncertainty Quantification Techniques of SCALE/ TSUNAMI”, Trans. Am. Nucl. Soc., 104, pp.371–373 (2011).
  6. I. Kodeli, “The SUSD3D Code for Cross-Section Sensitivity and Uncertainty Analysis – Recent Development,” Trans. Am. Nucl. Soc., 104, pp.791–793 (2011).
  7. N. García-Herranz, O. Cabellos, J. Sanz, J. Juan, and J. C. Kuijper, “Propagation of Statistical and Nuclear Data Uncertainties in Monte Carlo Burnup Calculations,” Annals of Nucl. Energy, 35, pp.714–730 (2008).
  8. O. Buss, A. Hoefer, and J.C. Neuber, “NUDUNA – Nuclear Data Uncertainty Analysis,” Proc. International Conference on Nuclear Criticality (ICNC 2011), Edinburgh, Scotland, Sep. 19–22, 2011, on CD-ROM (2011).
  9. A. J. Koning and D. Rochman, “Towards Sustainable Nuclear Energy: Putting Nuclear Physics to Work,” Annals of Nucl. Energy, 35, pp.2024–2030 (2008).
  10. W. Zwermann, B. Krzykacz-Hausmann, L. Gallner, A. Pautz, “Influence of Nuclear Covariance Data on Reactor Core Calculations,” Second International Workshop on Nuclear Data Evaluation for Reactor Applications (WONDER 2009), Cadarache, France, 29 Sep. – 2 Oct., 2009, pp.99–104 (2009).
  11. B. Krzykacz, E. Hofer, M. Kloos, “A Software System for Probabilistic Uncertainty and Sensitivity Analysis of Results from Computer Models,” Proc. International Conference on Probabilistic Safety Assessment and Management (PSAM-II), San Diego, Ca., USA, (1994).
  12. “International Handbook of Evaluated Criticality Safety Benchmark Experiments”, September 2010 Edition, available on DVD-ROM, NEA/NSC/DOC(95)03.
  13. “International Handbook of Evaluated Reactor Physics Benchmark Experiments”, March 2010 Edition, available on DVD-ROM, NEA/NSC/DOC (2006)1.
  14. T. Kozlowski, T. J. Downar, “The PWR MOX/UO2 Core Transient Benchmark, Final Report”, NEA/NSC/DOC(2006)20.

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