SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff , and α Using PARTISN

doi:10.1080/00295639.2018.1471296

Title: SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, k_eff , and α Using PARTISN

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Abstract

SENSMG is a tool for calculating the first-order sensitivities of reaction-rate ratios, k _eff, and α in critical problems and reaction-rate ratios, reaction rates, and leakage in fixed-source problems to multigroup cross sections, isotope densities, material mass densities, and interface locations using the PARTISN multigroup discrete-ordinates code by implementing Generalized Perturbation Theory. SENSMG can be used for one-dimensional spherical and slab (r) and two-dimensional cylindrical (r-z) geometries. For fixed-source (leakage) problems, SENSMG relies on the MISC and/or SOURCES4C codes to compute neutron source rate densities from spontaneous fission and (α,n) sources. SENSMG is a combination of Python and Fortran and was developed under Linux. This computer code abstract describes all user inputs, the input file, and output files. Furthermore, this computer code abstract describes how SENSMG can be modified to support different computer platforms, PARTISN versions, or cross-section availability. Several verification problems are presented in which SENSMG results are compared with MCNP6, SCALE6.2, and direct perturbations (central differences).

Authors:

Favorite, Jeffrey A. ^[1]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Publication Date:: 2018-07-23

Research Org.:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1467217

Report Number(s):: LA-UR-18-22532
Journal ID: ISSN 0029-5639

Grant/Contract Number:: AC52-06NA25396

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Science and Engineering

Additional Journal Information:: Journal Volume: 192; Journal Issue: 1; Journal ID: ISSN 0029-5639

Publisher:: American Nuclear Society - Taylor & Francis

Country of Publication:: United States

Language:: English

Subject:: 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; multigroup; discrete ordinates; adjoint; first-order sensitivity analysis

Citation Formats


                    Favorite, Jeffrey A. SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff , and α Using PARTISN.  United States: N. p., 2018. 
        Web.  doi:10.1080/00295639.2018.1471296.

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                    Favorite, Jeffrey A. SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff , and α Using PARTISN.  United States.  doi:10.1080/00295639.2018.1471296.

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                    Favorite, Jeffrey A. Mon .  
        "SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff , and α Using PARTISN".  United States.  doi:10.1080/00295639.2018.1471296.  https://www.osti.gov/servlets/purl/1467217.

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@article{osti_1467217,

  title        = {SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff , and α Using PARTISN},

  author       = {Favorite, Jeffrey A.},

  abstractNote = {SENSMG is a tool for calculating the first-order sensitivities of reaction-rate ratios, keff, and α in critical problems and reaction-rate ratios, reaction rates, and leakage in fixed-source problems to multigroup cross sections, isotope densities, material mass densities, and interface locations using the PARTISN multigroup discrete-ordinates code by implementing Generalized Perturbation Theory. SENSMG can be used for one-dimensional spherical and slab (r) and two-dimensional cylindrical (r-z) geometries. For fixed-source (leakage) problems, SENSMG relies on the MISC and/or SOURCES4C codes to compute neutron source rate densities from spontaneous fission and (α,n) sources. SENSMG is a combination of Python and Fortran and was developed under Linux. This computer code abstract describes all user inputs, the input file, and output files. Furthermore, this computer code abstract describes how SENSMG can be modified to support different computer platforms, PARTISN versions, or cross-section availability. Several verification problems are presented in which SENSMG results are compared with MCNP6, SCALE6.2, and direct perturbations (central differences).},

  doi          = {10.1080/00295639.2018.1471296},

  journal      = {Nuclear Science and Engineering},

  number       = 1,

  volume       = 192,

  place        = {United States},

  year         = {2018},

  month        = {7}

}

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Title: SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, keff , and α Using PARTISN

Abstract

Citation Formats

Title: SENSMG: First-Order Sensitivities of Neutron Reaction Rates, Reaction-Rate Ratios, Leakage, k_eff , and α Using PARTISN