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 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.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division
- Publication Date:
- 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.
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
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.
@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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