Calculation of “full core” VVER-1000 benchmark
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S. S. Aleshin
Abstract
The 2-D benchmark related to the “full-core” of VVER-1000 was proposed at the AER working group A&B meeting in 2015. Such type of benchmarks requires the adequate specification of the volume surrounding the core where geometry is complex enough. The proposed benchmarks have been solved using the codes included into the software package KASKAD. The data calculated by the engineering codes have been compared with the calculation results of the Monte-Carlo code MCU.
Kurzfassung
Der 2-D-Benchmark zum „Full-Core“ des VVER-1000 wurde auf der AER-Arbeitsgruppe A&B im Jahr 2015 vorgeschlagen. Diese Art von Benchmarks erfordert die adäquate Spezifikation des komplexen Volumens, das den Kern umgibt. Die Benchmarks wurden mit den im Softwarepaket KASKAD enthaltenen Codes berechnet. Die Ergebnisse dieser sog. Engineering-Codes wurden dann mit den Ergebnissen des Monte-Carlo-Codes MCU verglichen.
References
1 Krýsl, V.; Mikoláš, P.; Sprinzl, D.; Švarný, J.: “Full-Core” VVER-1000 benchmark calculated by MOBY-DICK macrocode. AER Working Groups A&B, Plzeň, Czech Republic, 21–22 April, 2015Search in Google Scholar
2 Aleshin, S. S., Oleynik, D. S., Shcherenko, A. I.: Calculation of VVER benchmarks by codes included into software package KASKAD. Proceedings of the twenty-sixth Symposium of AER, Helsinki, Finland, October 10–14, 2016Search in Google Scholar
3 Kalugin, M. A.; Oleynik, D. S.; Shkarovsky, D. A.: Overview of the MCU Monte Carlo Software Package. Annals of Nuclear Energy82 (2015) 54–6210.1016/j.anucene.2014.08.032Search in Google Scholar
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© 2018, Carl Hanser Verlag, München
Articles in the same Issue
- 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
Articles in the same Issue
- 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
