References
- N. M. LARSON, “Updated Users’ Guide for SAMMY: Multi-Level R-Matrix Fits to Neutron Data Using Bayes’s Equations,” ENDF-364/R2, Oak Ridge National Laboratory (2008), available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as PSR-158.
- M. E. DUNN and N. M. GREENE, “AMPX-2000: A Cross-Section Processing System for Generating Nuclear Data for Criticality Safety Applications,” Trans. Am. Nucl. Soc., 86, 118 (2002).
- J.-C. SUBLET et al., “Unresolved Resonance Range Cross Section, Probability Tables and Self Shielding Factors,” CEA-R-6227, Commissariat à l’Énergie Atomique (June 2009).
- L. LEAL et al., “Assessment of the Unresolved Resonance Treatment for Cross-Section and Covariance Representation,” WPEC-32, OECD/NEA, Working Party on International Evaluation Co-operation of the NEA Nuclear Science Committee (2011).
- A. LANE and R. THOMAS, “R-Matrix Theory of Nuclear Reactions,” Rev. Mod. Phys., 30, 2, 257 (1958); http://dx.doi.org/10.1103/RevModPhys.30.257.
- D. CACUCI, Handbook of Nuclear Engineering, Springer, New York (2010).
- “ENDF-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data Files ENDF/B-VI and ENDF/B-VII,” A. TRKOV, M. HERMAN, and D. BROWN, Eds., BNL-90365-2009 Rev. 2, CSEWG Document ENDF-102 (2012).
- M. E. DUNN and L. C. LEAL, “Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods,” Proc. Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics, Safety and High Performance Computing (PHYSOR 2002), Seoul, Korea, October 7–10, 2002.
- “SCALE: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design,” ORNL/TM-2005/39, Version 6.1, Oak Ridge National Laboratory (June 2011), available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-785.
- “International Handbook of Evaluated Criticality Safety Benchmark Experiments,” NEA/NSC/DOC(95)03/I-VIII, OECD/NEA (Sep. 2004).
- A. NOURI et al., “DICE: Database for the International Criticality Safety Benchmark Evaluation Program Handbook,” Nucl. Sci. Eng., 145, 11 (2003); http://dx.doi.org/10.13182/NSE03-15.
- B. T. REARDEN et al., “TSUNAMI Primer: A Primer for Sensitivity/Uncertainty Calculations with SCALE,” ORNL/TM-2009/027, Oak Ridge National Laboratory (Jan. 2009).
- T. GOORLEY et al., “Initial MCNP6 Release Overview,” Nucl. Technol., 180, 298 (2012); http://dx.doi.org/10.13182/NT11-135.