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Section B

Methodology to resolve the transport equation with the discrete ordinates code TORT into the IPEN/MB-01 reactor

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Pages 113-123 | Received 13 Nov 2012, Accepted 22 Apr 2013, Published online: 04 Jun 2013

REFERENCES

  • Organization for Economic Co-operation and Development-Nuclear Energy Agency, International Reactor Physics Experiments Database Project (IRPhE). NEA/NSC/DOC(2006)1: International Handbook of Evaluated Reactor Physics Benchmark Experiments, DVD ed., Organization for Economic Co-operation and Development-Nuclear Energy Agency (OECD-NEA), Paris, 2011.
  • E.E. Lewis and W.F. Miller, Computational Methods of Neutron Transport, Wiley, New York, 1984.
  • R.E. MacFarlane and D.W. Muir, NJOY99.0 Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data, PSR-480/NJOY99.0, Los Alamos National Laboratory, Las Alamos, NM, 2000.
  • W.A. Rhoades and R.L. Childs, DOORS-3.2a, One, Two- and Three-Dimensional Discrete Ordinates Neutron/ Photon Transport Code System, RSICC Computer Code Collection CCC-650, Oak Ridge National Laboratory, Oak Ridge, TN, 2003.
  • W.A. Rhoades and D.B. Simpson, The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code, ORNL/TM-13221, Oak Ridge National Laboratory, Oak Ridge, TN, 1997.
  • X-5 Monte Carlo Team, MCNP – A General Monte Carlo N-particle Transport Code, Version 5 – Vol. I: Overview and Theory, Report LA-UR-03-1987, Los Alamos National Laboratory, Las Alamos, NM, 2003.

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