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Monte Carlo Particle Transport Methods: Neutron and Photon - gnssn

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80 <strong>Monte</strong> <strong>Carlo</strong> <strong>Particle</strong> <strong>Transport</strong> <strong>Methods</strong>: <strong>Neutron</strong> <strong>and</strong> <strong>Photon</strong> Calculations33. Levitt, L. B., The probability table method for treating unresolved resonances in <strong>Monte</strong> <strong>Carlo</strong> calculations,M(C/. Sci. Eng., 49, 450, 1972.34. Lux, I. <strong>and</strong> Koblinger, L., An ICL Version of the 05R Program System. KFKI-73-2 Report. CentralResearch Institute for Physics, Budapest, 1973.35. Lux, I., Selecting from Three Probability Distributions for Reactor Calculations K.FKI-75-62 Report. CentralResearch Institute for Physics, Budapest, 1975.36. Lux, I., Selecting the Energy <strong>and</strong> Scattering Angle of Thermal <strong>Neutron</strong>s in Free Gas Model. KFKI-75--84Report. Central Research Institute for Physics, Budapest, 1975.37. Lux, I., Semi-continuous Selection of Scattering Angles from Low-order p„ Scattering Densities, Nucl.Sci. Eng., 82, 332, 1982.38. McGrath, E. J. <strong>and</strong> Irving, I). C, R<strong>and</strong>om Number Generation for Selected Probability Distributions.ORNL-RSIC-38 Report, Techniques for Efficient <strong>Monte</strong> <strong>Carlo</strong> Simulation, Vol. II., Oak Ridge NationalLaboratory, Oak Ridge, 1975.39. McGrath, E. J. <strong>and</strong> Irving, D. C, Variance Reduction. ORNL-RSIC-38 Report, Techniques for Efficient<strong>Monte</strong> <strong>Carlo</strong> Simulation, Vol. III. Oak Ridge National Laboratory, Oak Ridge, 1975.40. Parzen, E., Modern Probability Theory <strong>and</strong> Its Applications, John Wiley & Sons, New York. 1960.41. Persliden, J., A <strong>Monte</strong> <strong>Carlo</strong> program for photon transport using analogue sampling of scattering angle incoherent <strong>and</strong> incoherent scattering processes, Comput. Progr. Biomed. 17, 115, 1983.42. Piechaty, E. F., Cullen, D. E., <strong>and</strong> Howcrtrm, R. K., Tables <strong>and</strong> Graphs of <strong>Photon</strong>-Interaction CrossSections from 0.1 keV to 100 MeV Derived from the LLL Evaluated — Nuclear-Data Library. LLL-50900Report, Vol. 6., Rev. 2. L.awrence Livermore Laboratory, Livermore, 1978.43. Scbreider, Y. A., Ed.: Metod statisticheskih ispytani <strong>Monte</strong> <strong>Carlo</strong> (in Russian) Fizmatgiz, Moscow, 1961,— German translation: Die <strong>Monte</strong> <strong>Carlo</strong> Methode und ihre Verwirklichung mit elektronischen Digitalrechnern,B.b. Teubner Verlagsgesellschaft. Leipzig, 1964, — English translation: The <strong>Monte</strong> <strong>Carlo</strong> Method,Pergamon Press, New York, 1966.44. Spanier. J. <strong>and</strong> Gelbard, E. M., <strong>Monte</strong> <strong>Carlo</strong> Principles <strong>and</strong> <strong>Neutron</strong> <strong>Transport</strong> Problems, Addison-Wesley, Reading, 1969.45. Watt, B. E., Energy spectrum of neutrons from thermal fission of U 235 , Phys. Rev., 87, 1037, 1952.46. Weinberg, A. M. <strong>and</strong> Wigner, E. P., The Physical Theory of <strong>Neutron</strong> Chain Reactors. University ofChicago Press. Chicago, 1958.47. Williams. M. M. R., The Slowing Down <strong>and</strong> Thermalisation of <strong>Neutron</strong>s, North-Holl<strong>and</strong>, Amsterdam,1966.48. Woodcock, E. R., Murphy, T., I lemmings, P. J., <strong>and</strong> Longworth, S. ('.. Techniques Used in the GEMCode for <strong>Monte</strong> <strong>Carlo</strong> <strong>Neutron</strong>ics Calculations in Reactors <strong>and</strong> Other Systems of Complex Geometry, inProc. on the Conf. Applications of Computing <strong>Methods</strong> to Reactor Problems. ANL-7050 Report. ArgonneNational Laoratory, Argonne, 1965, p557.

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