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Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code

  • A. S. Bikeev , E. V. Bogdanova , E. K. Kosourov , D. A. Shkarovsky and M. A. Kalugin
Published/Copyright: August 31, 2018
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Kerntechnik
From the journal Kerntechnik Volume 83 Issue 4

Abstract

The purpose of the work is to calculate VVER-1200 neutron-physical characteristics that are important for safety using MCU Monte Carlo code for an independent verification of the accuracy of design calculations of the first fuel cycle. The calculations were carried out before the startup of the first VVER-1200 power unit. A full-scale computer model of VVER-1200 was developed using the design documentation of the fuel assemblies and the reactor facility. Special attention was given to the accurate specification of the geometry and material description of the core and its immediate environment. The full-scale VVER-1200 model allows performing Monte Carlo calculation of some safety-relevant characteristics for which it is impossible or extremely difficult to carry out full-scale reactor experiments. In total, more than 110 different states were calculated; five states were calculated taking feedbacks into account. For all calculations, the neutron-physical characteristics obtained by means of the MCU code were used to verify the BIPR-7A and the PERMAK-A codes.

Kurzfassung

Ziel der Arbeiten ist es, die für die Sicherheit von Kernkraftwerken wichtigen neutronenphysikalischen Eigenschaften des VVER-1200 mit Hilfe des Monte-Carlo-Programms MCU zu berechnen, um die Genauigkeit der Auslegungsberechnungen des ersten Brennstoffkreislaufs unabhängig zu überprüfen. Die Berechnungen wurden vor der Inbetriebnahme des ersten VVER-1200 Kraftwerks durchgeführt. Anhand der Konstruktionsdokumentation der Brennelemente und der Reaktoranlage wurde ein maßstäbliches Computermodell des VVER-1200 entwickelt. Besonderes Augenmerk wurde auf die genaue Spezifikation der Geometrie und Materialbeschreibung des Kerns und seiner unmittelbaren Umgebung gelegt. Das Modell VVER-1200 ermöglicht die Durchführung von Monte Carlo Berechnungen einiger sicherheitsrelevanter Kenngrößen, für die es unmöglich oder extrem schwierig ist, vollständige Reaktorexperimente durchzuführen. Insgesamt wurden mehr als 110 verschiedene Zustände berechnet; fünf Zustände wurden unter Berücksichtigung von Rückkopplungen berechnet. Für alle Berechnungen wurden die mit Hilfe des MCU-Codes ermittelten neutronenphysikalischen Eigenschaften zur Verifikation der Programme BIPR-7A und PERMAK-A.

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References

1 Kalugin, M. A.; Oleynik, D. S.; Shkarovsky, D. A.: Overview of the MCU Monte Carlo software package. Ann. Nucl. Energy82 (2015) 54, 10.1016/j.anucene.2014.08.032Search in Google Scholar

2 Bikeev, A.S.; Kalugin, M.A.; Oleynik, D.S.; et al.: MCU Code Precision Calculation of a Full-Scale VVER-1000 Model Considering Feedbacks. M&C 2017. International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, April 16–20, 2017, Jeju, KoreaSearch in Google Scholar

3 Bikeev, A. S.: Precision Calculations of Some Neutron-Physical Characteristics of VVER-1000 Using the MCU Code. Atomic Energy118 (2015) 23410.1007/s10512-015-9985-6Search in Google Scholar

4 Bikeev, A. S.; Marin, S.V.; Sukhino-Khomenko, E. A.: A comparison of the FA's models with the detailed and simplified description in the MCU code calculations. Kerntechnik78 (2013) 33010.3139/124.110386Search in Google Scholar

5 Bikeev, A. S.; Shkarovskiy, D. A.; Kalugin, M. A.: The status of KASKAD-MCU interface. First International Conference of the KASKAD Users Club, April 24–25, 2014, Moscow, RussiaSearch in Google Scholar

6 Computing resources of the federal collective usage center Complex for Simulation and Data Processing for Mega-science Facilities at NRC “Kurchatov Institute”, http://ckp.nrcki.ru/Search in Google Scholar

7 Gorodkov, S. S.; Shishkov, L. K.; Sukhino-Khomenko, E. A.: MCU calculation of spacing grid influence on FA's axial power distribution. 20th AER Symposium on VVER Reactor Physics and Reactor Safety, September 20–24, 2010, Espoo, FinlandSearch in Google Scholar

Received: 2017-12-11
Published Online: 2018-08-31
Published in Print: 2018-08-27

© 2018, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
  5. Technical Contributions/Fachbeiträge
  6. SIMULATE5-HEX extension for VVER analyses
  7. Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
  8. “Full-Core” VVER-440 extended calculation benchmark
  9. Calculation of “full core” VVER-1000 benchmark
  10. Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
  11. Advantages of VVER-440 fuel cycles with new fuel assemblies
  12. A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
  13. Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
  14. Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
  15. Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
  16. Power transient calculations with VERONA
  17. Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
  18. Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
  19. Hot channel calculation methodologies in case of VVER-1000/1200 reactors
  20. Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
  21. Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
https://doi.org/10.3139/124.110863

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
  5. Technical Contributions/Fachbeiträge
  6. SIMULATE5-HEX extension for VVER analyses
  7. Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
  8. “Full-Core” VVER-440 extended calculation benchmark
  9. Calculation of “full core” VVER-1000 benchmark
  10. Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
  11. Advantages of VVER-440 fuel cycles with new fuel assemblies
  12. A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
  13. Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
  14. Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
  15. Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
  16. Power transient calculations with VERONA
  17. Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
  18. Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
  19. Hot channel calculation methodologies in case of VVER-1000/1200 reactors
  20. Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
  21. Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods
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