Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2011 (2011), Article ID 683147, 7 pages
Research Article

Development and Application of MCNP5 and KENO-VI Monte Carlo Models for the Atucha-2 PHWR Analysis

1San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, via Diotisalvi 2, 56122 Pisa, Italy
2Nucleoelectrica Argentina-Societad Anonima (NA-SA), C1429BKQ Buenos Aires, Argentina

Received 22 September 2010; Accepted 2 December 2010

Academic Editor: Juan Ferreri

Copyright © 2011 M. Pecchia et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. C. Parisi, “Definition of a relevant core status,” GRNSPG Report SIR-2.1, rev. 1, 2007.
  2. F. Moretti, F. Terzuoli, and D. Melideo, “CFD Transient Analyses for CNA-2,” GRNSPG Report TFR-6, Rev. 0, 2007.
  3. X-5 Monte Carlo Team, MCNP—A general Monte Carlo N-Particle Transport Code, Version 5, vol. 1, LA-UR-03-1987, 2003.
  4. D. F. Hollenbach, L. M. Petrie, and N. F. Landers, “KENO-VI: a General Quadratic Version of the KENO Program,” ORNL/TM-2005/39 Version 5.1 Vol. II, Book 3, Sect. F17, 2005.
  5. RELAP5-3D Code Manual, “Volume I: Code Structure, System Models, And Solution Methods,” INEEL-EXT-98-00834, ver. 2.4, 2005.
  6. P. Turinsky et al., Few-Group Neutron Diffusion Equation Solver Utilizing the Nodal Expansion Method for Eigenvalue, Adjoint, Fixed-Source Steady-State and Transient Problems, Electric Power Research Center, North Carolina State University, Raleigh, NC, USA, 1994.
  7. K. M. Case, F. de Hoffmann, and G. Placzek, Introduction to the Theory of Neutron Diffusion, vol. 1, Los Alamos Scientific Laboratory, 1953.
  8. C. Parisi and M. Pecchia, “Calculation of Cross Section weighting coefficients for the Atucha2 CR model,” GRNSPG Report NEU-3.6.1, rev. 0, 2008.