Open Access
EPJ Web of Conferences
Volume 111, 2016
WONDER-2015 – 4th International Workshop On Nuclear Data Evaluation for Reactor applications
Article Number 11003
Number of page(s) 6
Section POSTER Session
Published online 15 March 2016
  1. D. Blanchet, L. Buiron, N. E. Stauff, T. K. Kim, T. Taiwo, AEN – WPRS Sodium Fast Reactor Core Definitions (Version 1.2 – September 19th), 2011, available at OECD/NEA Data Bank.
  2. Sodium Fast Reactor Core Feed-back and Transient Response Task Force (SFR-FT Task Force), (2014)
  3. SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, Version 6.1, ORNL/TM-2005/39, Oak Ridge National Laboratory, Oak Ridge, Tennessee, June 2011. Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785
  4. J.T. Goorley et al., Initial MCNP6 Release Overview - MCNP6 version 1.0, Los Alamos National Laboratory, LA-UR-13-22934 (2013).
  5. J. Leppänen, M. Pusa, T. Vittanen, V. Valtavirta, T. Kaltiaisenaho, The Serpent Monte Carlo code: Status, development and applications in 2013, Ann. Nuc. Energy 82, 142–150, (2015) [CrossRef]
  6. W. Zwermann, A. Aures, L. Gallner, V. Hannstein, B. Krzykacz-Hausmann, K. Velkov, J.S. Martinez, Nuclear Data Uncertainty and Sensitivity Analysis with XSUSA for Fuel Assembly Depletion Calculations, Nucl. Eng. and Tech. 46, No. 3, (2014) [CrossRef]