REFERENCES

  1. K.~D.~Lathrop, ``DTF-IV, A FORTRAN-IV Program for Solving the Multigroup Transport Equation with Anisotropic Scattering,'' Los Alamos Scientific Laboratory report LA-3373 (November 1965).
  2. W.~W.~Engle,~Jr., ``A User's Manual for ANISN: A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering,'' Oak Ridge Gaseous Diffusion Plant Computing Technology Center report K-1693 (1967).
  3. R.~E.~Alcouffe, ``Diffusion Acceleration Methods for the Diamond-Difference Discrete-Ordinates Equations,'' Nucl. Sci. Eng. \underline{64}, 344 (1977).
  4. R.~D.~O'Dell, F.~W.~Brinkley,~Jr. and D.~R.~Marr, ``User's Manual for ONEDANT: A Code Package for \underline{One}-Dimensional, \underline{D}iffusion-\underline{A}ccelerated, \underline{N}eutral-Particle \underline{T}ransport,'' Los Alamos National Laboratory report LA-9184-M (February 1982).
  5. R.~E.~Alcouffe, F.~W.~Brinkley,~Jr., D.~R.~Marr and R.~D.~O'Dell, ``User's Guide for TWODANT: A Code Package for \underline{Two}-Dimensional \underline{D}iffusion-\underline{A}ccelerated, \underline{N}eutral-Particle \underline{T}ransport,'' Los Alamos National Laboratory report LA-10049-M, Revision 1 (1984).
  6. T.~J.~Seed, ``TRIDENT-CTR User's Manual,'' Los Alamos Scientific Laboratory report LA-7835-M (May 1979).
  7. J.~W.~Davidson, B.~A.~Clark, D.~A.~Marr, T.~J.~Seed, J.~Stepnek, C.~E.~Higgs and D.~M.~Davierwalla, ``TRISM: A Two-Dimensional Finite-Element Discrete-Ordinates Transport Code,'' Los Alamos National Laboratory draft report (1986).
  8. K. L. Derstine, ``DIF3D: A Code to Solve One-, Two-, and Three-Dimensional Finite-Difference Diffusion Theory Problems,'' Argonne National Laboratory report ANL-82-64 (1984).
  9. J. F. Briesmeister, Ed., ``MCNP--A General Monte Carlo Code for Neutron and Photon Transport, Version 3A,'' Los Alamos National Laboratory report LA-7396-M, Rev. 2 (1986).
  10. R.~E.~MacFarlane, ``TRANSX-CTR: A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes for Fusion Systems Analysis,'' Los Alamos National Laboratory report LA-9863-MS (1984).
  11. These equations are derived in many standard references on reactor physics. This discussion follows G.~I.~Bell, G.~E.~Hansen and H.~A.~ Sandmeier, ``Multitable Treatments of Anisotropic Scattering in S$_{\rm N}$ Multigroup Transport Calculations,'' Nucl. Sci. Eng. \underline{28}, 376 (1967).
  12. R. E. MacFarlane and R. M. Boicourt, ``NJOY: A Neutron and Photon Processing System,'' Trans. Am. Nucl. Soc. \underline{22}, 720 (1975).
  13. R. E. MacFarlane, R. J. Barrett, D. W. Muir, and R. M. Boicourt, ``NJOY: A Comprehensive ENDF/B Processing System,'' in {\it A Review of Multigroup Nuclear Cross-Section Processing, Proceedings of a Seminar-Workshop, Oak Ridge, Tennessee, March 14-16, 1978}, Oak Ridge National Laboratory report ORNL/RSIC-41 (October 1978). LI> R. E. MacFarlane, D. W. Muir, and R. M. Boicourt, ``The NJOY Nuclear Data Processing System, Volume 1: User's Manual,'' Los Alamos National Laboratory report LA-9303-M, Vol. I (ENDF-324), (May 1982). R. E. MacFarlane, D. W. Muir, and R. M. Boicourt, ``The NJOY Nuclear Data Processing System, Volume II: The NJOY, RECONR, BROADR, HEATR, and THERMR Modules,'' Los Alamos National Laboratory report LA-9303-M, Vol. II (ENDF-324) (May 1982). R. E. MacFarlane and D. W. Muir, ``The NJOY Nuclear Data Processing System, Volume III: The GROUPR, GAMINR, and MODER Modules,'' Los Alamos National Laboratory report LA-9303-M, Vol. III (ENDF-324) (October 1987). D. W. Muir and R. E. MacFarlane, ``The NJOY Nuclear Data Processing System, Volume IV: The ERRORR and COVR Modules,'' Los Alamos National Laboratory report LA-9303-M, Vol. IV (ENDF-324) (December 1985).
  14. R. E. MacFarlane, ``Introducing NJOY 89,'' in {\it Proceedings of the Seminar on NJOY and THEMIS,'' 20-21 June 1989}, OECD/NEA Data Bank, Saclay, France (1989). See also Nuclear Theory and Application Progress Report, January 1, 1989---April 1, 1990, pp. 21-38, Los Alamos National Laboratory report LA-11972-PR (December 1990).
  15. I.~I.~Bondarenko, Ed., {\it Group Constants for Nuclear Reactor Calculations}, (Consultants Bureau, New York, 1964).
  16. R.~E.~MacFarlane, R.~B.~Kidman and R.~J.~LaBauve, ``The Background Cross Section Method as A General Tool for Reactor Analysis,'' in {\it CONF-78040, Proc. ANS Topical Meeting, Gatlinberg, Tennessee, April 1978}, E.~G.~Silver, Ed. (1978).
  17. R.~B.~Kidman, ``Cross Section Structure Factor Interpolation Schemes,'' Hanford Engineering Development Laboratory report HEDL-TME-71-40 (1971).
  18. R.~W.~Hardie and W.~W.~Little, Jr., ``1DX, A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections,'' Battelle Northwest Laboratory report BNWL-954 (1969).
  19. R.~Protsik, E.~Kujawski, and C.~L.~Cowan, ``TDOWN-IV: A Computer Code to Generate Composition and Spatially Dependent Neutron Cross Sections for Multigroup Neutronics Analysis,'' General Electric Company report GEFR-00485 (1979).
  20. R.~B.~Kidman, R.~E.~MacFarlane, and M.~Becker, ``Flux Interpolation for Elastic Downscatter,'' Trans. Am. Nucl. Soc. \underline{26}, 580 (1977).
  21. J.~U.~Koppel and D.~H.~Houston, ``Reference Manual for ENDF Thermal Neutron Scattering Data,'' General Atomic report GA-8774 revised and re-issued as ENDF-269 by the National Nuclear Data Center at Brookhaven National Laboratory (1978).
  22. ``ENDF-202, Cross Section Evaluation Working Group Benchmark Specifications,'' Brookhaven National Laboratory report BNL 19302 (ENDF-202) with various revisions (1974).
  23. L.~R.~Greenwood and R.~K.~Smither, ``Displacement Damage Calculations with ENDF/B-V,'' Proceedings of the Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Reactor Safety Aspects, 12--16 October 1981, IAEA, Vienna, Austria (1981).
  24. R.~D.~O'Dell, ``Standard Interface Files and Procedures for Reactor Physics Codes, Version IV,'' Los Alamos Scientific Laboratory report LA-6941-MS (1977).
  25. T.~R.~Hill, ``ONETRAN: A Discrete Ordinates Finite Element Code for the Solution of the One-Dimensional Multigroup Transport Equation,'' Los Alamos Scientific Laboratory report LA-5990-MS (1975).
  26. R.~E.~MacFarlane and D.~C.~George, ``UPD: A Portable Version-Control Program,'' Los Alamos National Laboratory report LA-12057-MS (1991).

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