Abstract
The range of specialized radiation transport problems that can be analyzed using Monte Carlo methods is broad and extends well beyond the rudiments developed in the preceding chapters. The purpose of this chapter is to give the reader a brief introduction to some advanced radiation transport applications of Monte Carlo. The literature is full of special Monte Carlo techniques that allow users to attack sophisticated problems in radiation analysis as well as other fields of science, and the reader is referred to such literature for additional discussion of the topics treated in this chapter and for information on other advanced concepts.
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References
See George I. Bell and Samuel Glasstone, Nuclear Reactor Theory, Van Nostrand Reinhold, New York, 1970, Section 2.7, for the effect of the change of variables on the one-speed transport equation.
This manipulation is described in numerous places and the details are not reproduced here. See ibid., pp. 257–58; James H. Renken, “Use of Solutions to the Adjoint Transport Equation for the Evaluation of Radiation Shield Designs,” Sandia Laboratories, Albuquerque, NM, Report SC-RR-70-98, January 1970; G. E. Hansen and H. A. Sandmeier, “Neutron Penetration Factors Obtained by Using Adjoint Transport Calculations,” Nuc Sci Eng 22, 1965, pp. 315–320.
M. H. Kalos, Appendix G of “ANTE 2, Adjoint Monte Carlo Time-Dependent Neutron Transport Code in Combinatorial Geometry,” Mathematical Applications Group Inc. (MAGI), White Plains, NY, 1970. See also Hansen and Sandmeier, op. cit.
See Bell and Glasstone, op. cit., pp. 604–5.
Ibid.
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© 2002 Springer Science+Business Media New York
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Dupree, S.A., Fraley, S.K. (2002). Advanced Applications of Monte Carlo. In: A Monte Carlo Primer. Springer, Boston, MA. https://doi.org/10.1007/978-1-4419-8491-3_9
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DOI: https://doi.org/10.1007/978-1-4419-8491-3_9
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