TY - GEN
T1 - VERA benchmarking results for Krŝko Nuclear Power plant cycle 1
AU - Godfrey, Andrew
AU - Jessee, Matthew
AU - Stimpson, Shane
AU - Collins, Benjamin
AU - Evans, Thomas
AU - Kromar, Marjan
AU - Franceschini, Fausto
AU - Salazar, David
PY - 2016
Y1 - 2016
N2 - The Consortium for Advanced Simulation of Light Water Reactors (CASL), the first US Department of Energy (DOE) Innovation Hub, has developed a high-fidelity suite of methods and software for engineering analyses of commercial nuclear power plants. The Virtual Environment for Reactor Applications (VERA) has been successfully developed and applied to several reactor types operated or designed by CASL partners. To broaden its validation basis, VERA was applied to the Nuklearna elektrarna Krško, a European two-loop Westing-house-designed pressurized water reactor (PWR) with 16×16 fuel. VERA enables multigroup deterministic and continuous-energy Monte Carlo neutron transport for the entire reactor using the same basic input and output features. Deterministic methods are directly coupled to a two-phase subchannel thermal-hydraulic method and an in-line isotopic decay and depletion module for 3D whole-core power distribution and fuel depletion analyses. VERA's performance for full core calculations is documented, and the results are compared to measured critical boron concentrations, startup physics tests results, and measured radial power distributions from Krsko Cycle 1. Results are also compared to calculations from the Jozef Stefan Institute (JSI) CORD-2 package routinely used for verification of the Krsko reload cores. Finally, comparisons are made for a set of 2D lattice depletions performed by Serpent and Polaris for additional verification.
AB - The Consortium for Advanced Simulation of Light Water Reactors (CASL), the first US Department of Energy (DOE) Innovation Hub, has developed a high-fidelity suite of methods and software for engineering analyses of commercial nuclear power plants. The Virtual Environment for Reactor Applications (VERA) has been successfully developed and applied to several reactor types operated or designed by CASL partners. To broaden its validation basis, VERA was applied to the Nuklearna elektrarna Krško, a European two-loop Westing-house-designed pressurized water reactor (PWR) with 16×16 fuel. VERA enables multigroup deterministic and continuous-energy Monte Carlo neutron transport for the entire reactor using the same basic input and output features. Deterministic methods are directly coupled to a two-phase subchannel thermal-hydraulic method and an in-line isotopic decay and depletion module for 3D whole-core power distribution and fuel depletion analyses. VERA's performance for full core calculations is documented, and the results are compared to measured critical boron concentrations, startup physics tests results, and measured radial power distributions from Krsko Cycle 1. Results are also compared to calculations from the Jozef Stefan Institute (JSI) CORD-2 package routinely used for verification of the Krsko reload cores. Finally, comparisons are made for a set of 2D lattice depletions performed by Serpent and Polaris for additional verification.
KW - CASL
KW - KRSKO
KW - PWR
KW - VERA
UR - http://www.scopus.com/inward/record.url?scp=84992123225&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:84992123225
T3 - Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
SP - 3998
EP - 4008
BT - Physics of Reactors 2016, PHYSOR 2016
PB - American Nuclear Society
T2 - Physics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016
Y2 - 1 May 2016 through 5 May 2016
ER -