Hot zero power reactor calculations using the Insilico code

Hamilton, Steven P.; Evans, Thomas M.; Davidson, Gregory G.; Johnson, Seth R.; Pandya, Tara M.; Godfrey, Andrew T.

doi:10.1016/j.jcp.2016.03.033

Title: Hot zero power reactor calculations using the Insilico code

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Abstract

In this paper we describe the reactor physics simulation capabilities of the insilico code. A description of the various capabilities of the code is provided, including detailed discussion of the geometry, meshing, cross section processing, and neutron transport options. Numerical results demonstrate that the insilico SP_N solver with pin-homogenized cross section generation is capable of delivering highly accurate full-core simulation of various PWR problems. Comparison to both Monte Carlo calculations and measured plant data is provided.

Authors:

Hamilton, Steven P. ^[1]; Evans, Thomas M. ^[1]; Davidson, Gregory G. ^[1]; Johnson, Seth R. ^[1]; Pandya, Tara M. ^[1]; Godfrey, Andrew T. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

Publication Date:: Fri Mar 18 00:00:00 EDT 2016

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Oak Ridge Leadership Computing Facility (OLCF); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Consortium for Advanced Simulation of LWRs (CASL)

Sponsoring Org.:: USDOE Office of Science (SC)

OSTI Identifier:: 1247928

Alternate Identifier(s):: OSTI ID: 1352949

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Computational Physics

Additional Journal Information:: Journal Volume: 314; Journal Issue: C; Journal ID: ISSN 0021-9991

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; Reactor analysis; Neutron transport; Radiation transport; Nuclear reactor physics; Eigenvalue solvers; Nuclear cross sections

Citation Formats


                    Hamilton, Steven P., Evans, Thomas M., Davidson, Gregory G., Johnson, Seth R., Pandya, Tara M., and Godfrey, Andrew T. Hot zero power reactor calculations using the Insilico code.  United States: N. p., 2016. 
Web.  doi:10.1016/j.jcp.2016.03.033.

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                    Hamilton, Steven P., Evans, Thomas M., Davidson, Gregory G., Johnson, Seth R., Pandya, Tara M., & Godfrey, Andrew T. Hot zero power reactor calculations using the Insilico code.  United States.  https://doi.org/10.1016/j.jcp.2016.03.033

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                    Hamilton, Steven P., Evans, Thomas M., Davidson, Gregory G., Johnson, Seth R., Pandya, Tara M., and Godfrey, Andrew T. Fri .  
"Hot zero power reactor calculations using the Insilico code".  United States.  https://doi.org/10.1016/j.jcp.2016.03.033.  https://www.osti.gov/servlets/purl/1247928.

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@article{osti_1247928,

  title        = {Hot zero power reactor calculations using the Insilico code},

  author       = {Hamilton, Steven P. and Evans, Thomas M. and Davidson, Gregory G. and Johnson, Seth R. and Pandya, Tara M. and Godfrey, Andrew T.},

  abstractNote = {In this paper we describe the reactor physics simulation capabilities of the insilico code. A description of the various capabilities of the code is provided, including detailed discussion of the geometry, meshing, cross section processing, and neutron transport options. Numerical results demonstrate that the insilico SPN solver with pin-homogenized cross section generation is capable of delivering highly accurate full-core simulation of various PWR problems. Comparison to both Monte Carlo calculations and measured plant data is provided.},

  doi          = {10.1016/j.jcp.2016.03.033},

  journal      = {Journal of Computational Physics},

  number       = C,

  volume       = 314,

  place        = {United States},

  year         = {Fri Mar 18 00:00:00 EDT 2016},

  month        = {Fri Mar 18 00:00:00 EDT 2016}

}

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Hot zero power reactor calculations using the Insilico code

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In this paper we describe the reactor physics simulation capabilities of the Insilico code. A description of the various capabilities of the code is provided, including detailed discussion of the geometry, meshing, cross section processing, and neutron transport options. Numerical results demonstrate that Insilico using an SP{sub N} solver with pin-homogenized cross section generation is capable of delivering highly accurate full-core simulation of various pressurized water reactor problems. Comparison to both Monte Carlo calculations and measured plant data is provided.
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