Showing 1 - 17 results of 17 for search 'Kord S. Smith.', query time: 0.04s Refine Results
  1. 1
    The "virtual density" theory of neutronics

    The "virtual density" theory of neutronics by Reed, Mark Wilbert

    Published 2014
    Other Authors: “…Kord S. Smith.…”
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    Thesis
  2. 2
    Improvements and applications of the Uniform Fission Site method in Monte Carlo

    Improvements and applications of the Uniform Fission Site method in Monte Carlo by Hunter, Jessica Lynn

    Published 2015
    Other Authors: “…Kord S. Smith.…”
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    Thesis
  3. 3
    On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems

    On-the-fly nuclear data processing methods for Monte Carlo simulations of intermediate and fast spectrum systems by Walsh, Jonathan A. (Jonathan Alan)

    Published 2017
    Other Authors: “…Benoit Forget and Kord S. Smith.…”
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    Thesis
  4. 4
    Methods for including multiphysics feedback in Monte Carlo reactor physics calculations

    Methods for including multiphysics feedback in Monte Carlo reactor physics calculations by Ellis, Matthew Shawn

    Published 2017
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  5. 5
    Acceleration methods for Monte Carlo particle transport simulations

    Acceleration methods for Monte Carlo particle transport simulations by Li, Lulu, Ph. D Massachusetts Institute of Technology

    Published 2017
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  6. 6
    Development of high fidelity methods for 3D Monte Carlo transient analysis of nuclear reactors

    Development of high fidelity methods for 3D Monte Carlo transient analysis of nuclear reactors by Shaner, Samuel Christopher

    Published 2018
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  7. 7
    Parallel, asynchronous ray-tracing for scalable, 3D, full-core method of characteristics neutron transport on unstructured mesh

    Parallel, asynchronous ray-tracing for scalable, 3D, full-core method of characteristics neutron transport on unstructured mesh by Gaston, Derek Ray.

    Published 2021
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  8. 8
    Cumulative migration method for computing multi-group transport cross sections and diffusion coefficients with Monte Carlo calculations

    Cumulative migration method for computing multi-group transport cross sections and diffusion coefficients with Monte Carlo calculations by Liu, Zhaoyuan,Ph. D.Massachusetts Institute of Technology.

    Published 2021
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  9. 9
    A low order acceleration scheme for solving the neutron transport equation

    A low order acceleration scheme for solving the neutron transport equation by Li, Lulu, Ph. D Massachusetts Institute of Technology

    Published 2014
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  10. 10
    On-the-fly Doppler broadening using multipole representation for Monte Carlo simulations on heterogeneous clusters

    On-the-fly Doppler broadening using multipole representation for Monte Carlo simulations on heterogeneous clusters by Xu, Sheng, S.M. Massachusetts Institute of Technology

    Published 2014
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  11. 11
    Transient method of characteristics via the Adiabatic, Theta, and Multigrid Amplitude Function methods

    Transient method of characteristics via the Adiabatic, Theta, and Multigrid Amplitude Function methods by Shaner, Samuel Christopher

    Published 2014
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  12. 12
    Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration

    Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration by Herman, Bryan R. (Bryan Robert)

    Published 2015
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  13. 13
    Computational methods for efficient nuclear data management in Monte Carlo neutron transport simulations

    Computational methods for efficient nuclear data management in Monte Carlo neutron transport simulations by Walsh, Jonathan A. (Jonathan Alan)

    Published 2015
    Other Authors: “…Benoit Forget and Kord S. Smith.…”
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    Thesis
  14. 14
    The Greedy Exhaustive Dual Binary Swap methodology for fuel loading optimization in PWR reactors using the poropy reactor optimization Tool

    The Greedy Exhaustive Dual Binary Swap methodology for fuel loading optimization in PWR reactors using the poropy reactor optimization Tool by Haugen, Carl C. (Carl Christopher)

    Published 2015
    Other Authors: “…Kord S. Smith and Benoit Forget.…”
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    Thesis
  15. 15
    Domain decomposition for Monte Carlo particle transport simulations of nuclear reactors

    Domain decomposition for Monte Carlo particle transport simulations of nuclear reactors by Horelik, Nicholas E. (Nicholas Edward)

    Published 2015
    Other Authors: “…Benoit Forget and Kord S. Smith.…”
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    Thesis
  16. 16
    Prediction of departure from nucleate boiling in PWR fast power transients

    Prediction of departure from nucleate boiling in PWR fast power transients by Lenci, Giancarlo

    Published 2013
    Other Authors: “…Kord S. Smith and Neil E. Todreas.…”
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    Thesis
  17. 17
    Advanced nodal methods for MOX fuel analysis

    Advanced nodal methods for MOX fuel analysis by Palmtag, Scott P. (Scott Parker)

    Published 2005
    Other Authors: “…Allan F. Henry and Kord S. Smith.…”
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    Thesis

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