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Technical Paper

Using the Cartesian Discrete Ordinates Code DORT for Assembly-Level Calculations

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Pages 233-258 | Published online: 17 Mar 2017

REFERENCES

  • A. HÉBERT, Applied Reactor Physics, Ecole Polytechnique de Montreal (2006).
  • E. E. LEWIS and W. F. MILLER, Jr., Computational Methods of Neutron Transport, American Nuclear Society, La Grange Park, Illinois (1993).
  • R. STAMMLER, “HELIOS Methods, Proprietary Studsvik Scandpower Report, Distributed Together with the HELIOS Code,” Studsvik Scandpower (2000).
  • G. MARLEAU, “DRAGON Theory Manual Part 1: Collision Probability Calculations,” Ecole Polytechnique de Montreal (Oct. 2001).
  • Y. HAN et al., “Effect of Void Dependent Reactivity Modeling Bias on BWR Axial Power Tilt,” Proc. PHYSOR 2010— Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, Pennsylvania, May 9–14, 2010, American Nuclear Society (2010).
  • R. LE TELLIER and A. HÉBERT, “An Improved Algebraic Collapsing Acceleration with General Boundary Conditions for the Characteristics Method,” Nucl. Sci. Eng., 156, 121 (2007).
  • T. POSTMA and J. VUJIC, “The Method of Characteristics in General Geometry with Anisotropic Scattering,” Proc. Int. Conf. Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, Madrid, Spain, September 27–30, 1999.
  • R. LE TELLIER and A. HÉBERT, “A PWR Assembly Computational Scheme Based on the DRAGON V4 Lattice Code,” Proc. Joint Int. Topl. Mtg. Mathematics and Computation and Supercomputing in Nuclear Applications (M&C + SNA 2007), Monterey, California, April 15–19, 2007, American Nuclear Society (2007).
  • M. D. DeHART, R. E. PEVEY, and T. A. PARISH, “An Extended Step Characteristic Method for Solving the Transport Equation in General Geometries,” Nucl. Sci. Eng., 118, 79 (1994).
  • M. D. DeHART, “Lattice Physics Capabilities of the SCALE Code System Using TRITON,” Proc. PHYSOR-2006 Topl. Mtg. Reactor Physics: Advances in Nuclear Analysis and Simulation, Vancouver, Canada, September 10–14, 2006, American Nuclear Society (2006).
  • A. PAUTZ et al., “Fuel Assembly Calculations Using the Method of Discrete Ordinates,” Nucl. Sci. Eng., 149, 197 (2005).
  • Y. Y. AZMY, J. C. GEHIN, and R. ORSI, “DORT Solutions to the Two-Dimensional C5G7MOX Benchmark Problem,” Prog. Nucl. Energy, 45, 215 (2004).
  • “Benchmark on Deterministic Transport Calculations Without Spatial Approximation,” NEA/NSC/DOC(2005) 16, Nuclear Energy Agency (2005).
  • “RSICC Computer Code Collection DOORS3.2a,” Oak Ridge National Laboratory (Oct. 2003).
  • G. MARLEAU, A. HÉBERT, and R. ROY, “A User Guide for DRAGON 3.06,” Ecole Polytechnique de Montreal (Mar. 2008).
  • G. MARLEAU, A. HÉBERT, and R. ROY, “A User Guide for DRAGON Version 4,” Ecole Polytechnique de Montreal (Aug. 2008).
  • X5 MONTE CARLO TEAM, “MCNP—AGeneral Monte Carlo N-Particle Transport Code, Version 5” (2003).
  • “The JEFF-2.2 Nuclear Data Library,” Nuclear Energy Agency (2000).
  • J. C. WAGNER et al., “MCNP: Multi-Group/Adjoint Capabilities,” LA-12704, Los Alamos National Laboratory (Apr. 1994).
  • V. XULUBANA et al., “Accuracy Evaluation of Pin Exposure Calculations in Current LWR Core Design Codes,” Trans. Am. Nucl. Soc., 93, 664 (2005).
  • E. E. LEWIS et al., “Benchmark Specification for Deterministic 2-D/3-D MOX Fuel Assembly Transport Calculations Without Spatial Homogenisation,” NEA/NSC/DOC(2001)4, Nuclear Energy Agency (2003).
  • B. MERVIN et al., “Under-Prediction of Localized Tally Uncertainties in Monte Carlo Eigenvalue Calculations,” Trans. Am. Nucl. Soc., 104, 329 (2011).
  • R. ORSI, “BOT3PVersion 5.0: APre/Post-Processor System for Transport Analysis” (Apr. 2005).
  • N. KRIANGCHAIPORN, “Transport Model Based on 3-D Cross-Section Generation for TRIGA Core Analysis,” PhD Dissertation, The Pennsylvania State University (2006).
  • R. SANCHEZ and L. MAO, “New Developments in the Interface-Current Module TDT,” Proc. Joint Int. Mtg. Mathematics and Computation and Supercomputing in Nuclear Applications, Saratoga Springs, New York, October 6–10, 1997, American Nuclear Society (1997).
  • A. YAMAMOTO et al., “Benchmark Problem Suite for Reactor Physics Study of LWR Next Generation Fuels,” Nucl. Sci. Technol., 39, 900 (2002).
  • G. F. KNOLL, Radiation Detection and Measurement, 4th ed., Wiley Interscience (2010).

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