Hot zero power reactor calculations using the Insilico code

Journal Article · Fri Mar 18 00:00:00 EDT 2016 · Journal of Computational Physics

DOI:https://doi.org/10.1016/j.jcp.2016.03.033· OSTI ID:1247928

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

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

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.

• Research Organization: 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 Organization: USDOE Office of Science (SC)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1247928
• Alternate ID(s): OSTI ID: 1352949
• Journal Information: Journal of Computational Physics, Vol. 314, Issue C; ISSN 0021-9991
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

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