SIMULATE5-HEX extension for VVER analyses
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T. Bahadir
Abstract
Studsvik's 3D, steady-state, nodal code SIMULATE5, which is widely used for square lattice geometries, has been recently extended to hexagonal geometry for the analysis of VVER 1000 and VVER 1200s. The lattice physics code CASMO5 is used for generating nodal cross sections data from single assembly calculations. SIMULATE5's HEX extension solves the multi-group diffusion equation, or optionally SP3 equations, for the hexagonal-z geometry by dividing each hexagonal into six triangles. In each triangle, the Fourier solution of the wave equation is approximated by eight plane waves to describe the intra-nodal flux accurately. The cross sections are described by a hybrid microscopic-macroscopic model that includes approximately 60 heavy nuclides and fission products. Heterogeneities, due to spacer/grid and control rod, in the axial direction of an assembly are treated systematically. This paper summarizes the physics models employed in SIMULATE5-HEX as well as the initial benchmarking activities.
Kurzfassung
Der stationäre 3D Nodalcode SIMULATE5 von Studsvik, der weltweit zur Berechnung von quadratischen Gittergeometrien verwendet wird, wurde für die Analyse von VVER 1000 und VVER 1200 s auf hexagonale Geometrien erweitert. Das Programm CASMO5 zur Berechnung der Physik des Gitters wird zur Erzeugung von Knotenquerschnittsdaten aus einzelnen Baugruppenberechnungen verwendet. Die HEX-Erweiterung von SIMULATE5 löst die Multi-Gruppen-Diffusionsgleichung oder optional SP3-Gleichungen für die Hexagonal-Z-Geometrie, indem sie jedes Hexagonal in sechs Dreiecke unterteilt. In jedem Dreieck wird die Fourier-Lösung der Wellengleichung durch acht ebene Wellen approximiert, um den intra-nodalen Fluss genau zu beschreiben. Die Querschnitte werden durch ein hybrides mikroskopisch-makroskopisches Modell beschrieben, das etwa 60 schwere Nuklide und Spaltprodukte enthält. Heterogenitäten durch Abstandhalter/Gitter und Steuerstab in axialer Richtung einer Baugruppe werden systematisch behandelt. Dieses Papier fasst die in SIMULATE5-HEX verwendeten physikalischen Modelle sowie die ersten Benchmark-Aktivitäten zusammen.
References
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© 2018, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
- Technical Contributions/Fachbeiträge
- SIMULATE5-HEX extension for VVER analyses
- Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
- “Full-Core” VVER-440 extended calculation benchmark
- Calculation of “full core” VVER-1000 benchmark
- Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
- Advantages of VVER-440 fuel cycles with new fuel assemblies
- A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
- Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
- Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
- Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
- Power transient calculations with VERONA
- Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
- Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
- Hot channel calculation methodologies in case of VVER-1000/1200 reactors
- Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
- Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Editorial
- Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
- Technical Contributions/Fachbeiträge
- SIMULATE5-HEX extension for VVER analyses
- Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
- “Full-Core” VVER-440 extended calculation benchmark
- Calculation of “full core” VVER-1000 benchmark
- Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
- Advantages of VVER-440 fuel cycles with new fuel assemblies
- A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
- Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
- Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
- Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
- Power transient calculations with VERONA
- Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
- Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
- Hot channel calculation methodologies in case of VVER-1000/1200 reactors
- Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
- Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
