Hot zero power reactor calculations using the Insilico code

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

doi:10.1016/j.jcp.2016.03.033

Hot zero power reactor calculations using the Insilico code

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12 Scopus citations

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 Insilico using an SP_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.

Original language	English
Pages (from-to)	700-711
Number of pages	12
Journal	Journal of Computational Physics
Volume	314
DOIs	https://doi.org/10.1016/j.jcp.2016.03.033
State	Published - Jun 1 2016

Funding

Work for this paper was supported by Oak Ridge National Laboratory, which is managed and operated by UT-Battelle, LLC, for the U.S. Department of Energy under Contract No. DE-AC05-00OR22725 . This research was supported by the Consortium for Advanced Simulation of Light Water Reactors ( www.casl.gov ), an Energy Innovation Hub ( http://www.energy.gov/hubs ) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR22725 . This research used resources of the Oak Ridge Leadership Computing Facility at the 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 . Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the U.S. Department of Energy . The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes.

Keywords

Eigenvalue solvers
Nuclear cross sections
Nuclear reactor physics
Radiation transport

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10.1016/j.jcp.2016.03.033

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

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 Insilico using an SPN 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.",

keywords = "Eigenvalue solvers, Nuclear cross sections, Nuclear reactor physics, Radiation transport",

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

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AU - Evans, Thomas M.

AU - Davidson, Gregory G.

AU - Johnson, Seth R.

AU - Pandya, Tara M.

AU - Godfrey, Andrew T.

PY - 2016/6/1

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KW - Nuclear reactor physics

KW - Radiation transport

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ER -

Hot zero power reactor calculations using the Insilico code

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Keywords

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