Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
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M. Růčka
Abstract
Physical startup tests are an important part of the operation of each nuclear reactor fuel cycle. This paper is focused on calculations of these tests for Dukovany NPP using MOBY-DICK diffusion macrocode. In this paper two tests are presented, specifically SCRAM test and “Weight of the 6th group of control assemblies” test. Both tests are described, methodology of calculation is introduced and results of calculations are compared with experimental data.
Kurzfassung
Physikalische Inbetriebnahmetests sind ein wichtiger Bestandteil des Betriebs jedes Kernreaktor-Brennstoffkreislaufs. Dieses Papier beschreibt Berechnungen dieser Tests für das Kernkraftwerk Dukovany unter Verwendung des MOBY-DICK-Diffusionsmakrocodes. In diesem Beitrag werden zwei Tests vorgestellt: der SCRAM-Test und der Test „Gewicht der sechsten Gruppe der Steuerstäben“. Beide Tests werden beschrieben, die Berechnungsmethodik vorgestellt und die Ergebnisse der Berechnungen mit experimentellen Daten verglichen.
References
1 Bajgl, J.; Krýsl, V.; Švarný, J: An analysis of reactivity prediction during reactor start-up process. Kerntechnik80 (2015) 339–34810.3139/124.110507Suche in Google Scholar
2 Bikeev, A. S.; etal.: Calculations of VVER-1000 start-up physics tests using MCU Monte Carlo code, 26th Symposium of AER, Helsinki, October, FinlandSuche in Google Scholar
3 Bahadir, T.; Giffen, M. M.; Wells, C.: Fixed-Source and Ex-Core calculations with SIMULATE5. M&C – International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, April, 2017Suche in Google Scholar
4 Krýsl, V.; Mikoláš, P.; et al.: MOBY-DICK macrocode. ŠKODA JS a.s., Plzeň, 2017Suche in Google Scholar
5 DOORS 3.2a: Program Package for One, Two and Three Dimensional Discrete Ordinates Transport. CCC-650, RSICC, ORNL, Oak Ridge, Tennessee, May 2007Suche in Google Scholar
6 Bárta, M.: Dukovany NPP, ČEZ a.s., personal communicationSuche in Google Scholar
7 Tuttle, R. J.: Delayed-Neutron Data for Reactor-Physics Analysis. Nuclear Science and Engineering56 (1975) 37–7110.13182/NSE75-A26620Suche in Google Scholar
8 Švarný, J.; Krýsl, V.; Mikoláš, P.; Vlachovský, K.: Calculation of Point-Kinetics Parameters in the MOBY-DICK System. Nuclear Science and Engineering128 (1998) 76–8710.13182/NSE98-A1947Suche in Google Scholar
© 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
