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Technical Paper

Use of Monte Carlo Procedures to Estimate First and Second Collision Sources for Discrete Ordinates Transport Codes

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Pages 228-237 | Published online: 13 May 2017

References

  • K. D. LATHROP “Discrete Ordinates Methods for the Numerical Solution of the Transport Equation,” Reactor Technol., 15, 2, 107 (1972).
  • M. B. EMMETT “The MORSE Monte Carlo Radiation Transport Code System,” ORNL-4972, Oak Ridge National Laboratory (1975).
  • W. A. RHOADESAND R. L. CHILDS “DORT Two-Dimensional Discrete Ordinates Transport Code,” ORNL-5851, Oak Ridge National Laboratory (1982).
  • W. A. RHOADESAND R. L. CHILDS “The TORT Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code,” ORNL-6268, Oak Ridge National Laboratory (1987).
  • B. G. CARLSONAND D. LATHROP “Transport Theory, The Method of Discrete Ordinates,” LA-3251-MS, Los Alamos Scientific Laboratory (1965).
  • E. JAHNKEAND F. EMDE Table of Functions, Chap. VII, Dover Publications, New York (1945).
  • R. L. CHILDSAND J. V. PACE “GRTUNCL: First Collision Source Program,” Unpublished Documentation, Oak Ridge National Laboratory (1982).
  • F. R. MYNATT F. J. MUCKENTHALER and P. N. STEVENS “Development of Two-Dimensional Discrete Ordinates Transport Theory for Radiation Shielding,” CTC-INF-952, Union Carbide Corporation Nuclear Division, Oak Ridge, Tennessee (1969).

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