Deterministically estimated fission source distributions for Monte Carlo k-eigenvalue problems

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Abstract

The standard Monte Carlo (MC) k-eigenvalue algorithm involves iteratively converging the fission source distribution using a series of potentially time-consuming inactive cycles before quantities of interest can be tallied. One strategy for reducing the computational time requirements of these inactive cycles is the Sourcerer method, in which a deterministic eigenvalue calculation is performed to obtain an improved initial guess for the fission source distribution. This method has been implemented in the Exnihilo software suite within SCALE using the SPN or SN solvers in Denovo and the Shift MC code. The efficacy of this method is assessed with different Denovo solution parameters for a series of typical k-eigenvalue problems including small criticality benchmarks, full-core reactors, and a fuel cask. It is found that, in most cases, when a large number of histories per cycle are required to obtain a detailed flux distribution, the Sourcerer method can be used to reduce the computational time requirements of the inactive cycles.

Original languageEnglish
Pages (from-to)7-22
Number of pages16
JournalAnnals of Nuclear Energy
Volume119
DOIs
StatePublished - Sep 2018

Funding

This work was funded in part by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research under Task Order NRCHQ6015T0026 “Shift – Integration of SCALE Nuclear Stochastic Methods,” under NRC Agreement No. NRCHQ6014D0005 “ SCALE Support for Reactor and Spent Fuel Analyses” (DOE Interagency Agreement No. 1886-V779-14 ). Work for this paper was supported by Oak Ridge National Laboratory , which is managed and operated by UT-Battelle, LLC, for the US Department of Energy under Contract No. DEAC05-00OR22725 . This research used resources of the Oak Ridge Leadership Computing Facility at Oak Ridge National Laboratory, which is supported by the Office of Science of the U.S. Department of Energy under Contract No. DE-AC05-00OR22725 . Appendix A This work was funded in part by the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research under Task Order NRCHQ6015T0026 “Shift – Integration of SCALE Nuclear Stochastic Methods,” under NRC Agreement No. NRCHQ6014D0005 “SCALE Support for Reactor and Spent Fuel Analyses” (DOE Interagency Agreement No. 1886-V779-14). Work for this paper was supported by Oak Ridge National Laboratory, which is managed and operated by UT-Battelle, LLC, for the US Department of Energy under Contract No. DEAC05-00OR22725. This research used resources of the Oak Ridge Leadership Computing Facility at Oak Ridge National Laboratory, which is supported by the Office of Science of the U.S. Department of Energy under Contract No. DE-AC05-00OR22725.

Keywords

  • Fission source convergence
  • Hybrid methods
  • Monte Carlo transport

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