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On a Continuous Energy Monte Carlo Simulator for Neutron Transport: Optimisation with Fission, Intermediate and Thermal Distributions

In: Integral Methods in Science and Engineering, Volume 2

Author

Listed:
  • L. F. F. Chaves Barcellos

    (Federal University of Rio Grande do Sul)

  • B. E. J. Bodmann

    (Federal University of Rio Grande do Sul)

  • S. Q. Bogado Leite

    (National Nuclear Energy Commission)

  • M. T. Vilhena

    (Federal University of Rio Grande do Sul)

Abstract

The time dependent continuous energy neutron spectrum is decomposed into fission, intermediate and thermal probability distributions. For the high and intermediate energy distribution the Monte Carlo simulation takes into account tracking and interaction of neutrons, whereas the thermal regime is simulated considering only reaction rates. The Monte Carlo implementation is then used to determine the transition rates between the three distributions, that after insertion in a differential equation system models the distribution kinetics.

Suggested Citation

  • L. F. F. Chaves Barcellos & B. E. J. Bodmann & S. Q. Bogado Leite & M. T. Vilhena, 2017. "On a Continuous Energy Monte Carlo Simulator for Neutron Transport: Optimisation with Fission, Intermediate and Thermal Distributions," Springer Books, in: Christian Constanda & Matteo Dalla Riva & Pier Domenico Lamberti & Paolo Musolino (ed.), Integral Methods in Science and Engineering, Volume 2, chapter 0, pages 1-10, Springer.
    • Handle: RePEc:spr:sprchp:978-3-319-59387-6_1
    DOI: 10.1007/978-3-319-59387-6_1
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