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This roport was proporad os an account of Govarnmont tponsorad work.
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A proposed monte carlo method for computing the basic lattice parameters and the space dependent neutron spectra
G.D. Joanou
- 01 Dec 1959
TL;DR: In this paper, the authors proposed a Monte Carlo method for computing thermal neutron spectra in both homogeneous and heterogeneous lattices, which is applicable to computing thermal neutra.
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Abstract: lattice parameters and space-dependent neutron spectra. The method follows neutron histories through many generations, the total number depending on the statistical uncertainty desired. The major differences in the proposed Monte Carlo scheme and previous Monte Carlo calculations are enumerated. The use of neutron weights is introduced into the routine for the calculation of the fast fission factor. The calculation of the resonance escape probability employs the use of doubling surfaces in the moderator. In computing the thermal utilization, the thermal neutron spectrum is not assumed to be in the usual Wigner-Wilkins form but is calculated for every region. The effects of spectral hardening and epithermal fission are included. The neutron flux is calculated according to the definition that the neutron flux is proportional to the sum of the path lenthhs per cubic centimeter. The proposed method is applicable to computing thermal neutron spectra in both homogeneous and heterogeneous lattices. (C.J.G.)
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Citations
Neutron Cross-Sections
TL;DR: Neutron Cross Sections Prepared by the United States Atomic Energy Commission (Selected Reference Material on Atomic Energy) Pp viii + 328 (London: McGraw-Hill Publishing Company, Ltd, 1955) 90s as discussed by the authors
References
A Practical Manual on the Monte Carlo Method for Random Walk Problems
E. D. Cashwell,C.J. Everett +1 more
Abstract: This report is written to serve as a guide to those persons who, having no previous experience with Monte Carlo methods, wish to apply these methods to their own problems. Particular emphasis is given to techniques which are useful in dealing with probIems concerned with the diffusion of particles (and gamma rays) in material media of some complexity, both from a geometrical and a nuclear standpoint. Included as an appendix are brief summaries of a variety of problems of the above-mentioned type to which the methods described have been applied successfully. (auth)
399
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A practical manual on the Monte Carlo method for random walk problems
Edmond D Cashwell,C.J. Everett +1 more
- 01 Jan 1959
TL;DR: In this paper, a guide to applying Monte Carlo methods to the diffusion of particles (and gamma rays) in material media of some complexity, both from a geometrical and a nuclear standpoint, is given.
294
Neutron Cross-Sections
TL;DR: Neutron Cross Sections Prepared by the United States Atomic Energy Commission (Selected Reference Material on Atomic Energy) Pp viii + 328 (London: McGraw-Hill Publishing Company, Ltd, 1955) 90s as discussed by the authors
The monte-carlo calculation of resonance capture in reactor lattices
R.D. Richtmyer,R. Van Norton,A. Wolfe +2 more
- 31 Oct 1958
TL;DR: The calculation of the resonance escape probabitity by the Monte Carlo method is treated and the problem is described in genneral terms and also with reference to a code for the IBM-704 computer.
5
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A Monte Carlo calculation of thermal utilization
A. Rotenberg,A. Lapidus,E. Wetherwell +2 more
- 03 Sep 2011
TL;DR: In this article, a Monte Carlo calculation of thermal utilization is described with emphasis on the statistical procedures employed for calculating the thermal utilization of a nuclear reactor model with slightly enriched fuel rods in a hexagonal lattice.
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