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Uncertainties of the neutronic calculations at core level determined by the KARATE code system and the KIKO3D code

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Published/Copyright: October 21, 2013
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Kerntechnik
From the journal Kerntechnik Volume 78 Issue 4

Abstract

In this paper the uncertainties of the neutronic calculations at core level – originating from the uncertainties of the basic nuclear data – are presented. The investigations have been made for a VVER-1000 core (Kozloduy-6) defined in the frame of the OECD NEA UAM benchmark. In the first part of the paper, the uncertainties of the effective multiplication factor, the assembly-wise radial power distribution, the axial power distribution and the rod worth are shown. After that the preliminary evaluation of the uncertainties of the neutron kinetic calculations are presented for a rod movement transient at HZP (Hot Zero Power) state, where the uncertainties of the time dependent core and assembly powers and the dynamic reactivity were evaluated. In both cases, we will see that the most important quantities –at core level and at HZP state – have a considerable uncertainty which is originating from the uncertainties of the basic cross section library in these investigations.

Kurzfassung

In diesem Beitrag wird die Bestimmung der Unsicherheiten der Neutronenberechnungen auf Kernebene basierend auf den Unsicherheiten der nuklearen Basisdaten vorgestellt. Im Rahmen des OECD NEA UAM Benchmarks wurden diese Untersuchungen für einen Kern eines WWER-1000 Reaktors (Kozloduy-6) durchgeführt. Im ersten Teil des Beitrags werden die Unsicherheiten der effektiven Mulitplikationsfaktoren, der radialen brennelementweisen und der axialen Leistungsverteilungen sowie der Wirksamkeiten der Steuerelemente angegeben. Im zweiten Teil werden die Ergebnisse der Berechnung der Unsicherheiten für eine Transiente mit Steuerelementbewegung im heißen Nullleistungsbereich vorgestellt. Dabei werden die Unsicherheiten der zeitabhängigen Kern- und Bündelleistungen sowie der dynamischen Reaktivität bestimmt. Bei beiden Untersuchungen stellt sich heraus, dass die Unsicherheiten der den Rechnungen zugrunde liegenden Wirkungsquerschnittsbibliotheken den größten Anteil zur berechneten Gesamtunsicherheit liefern.

3 Dr. István Panka (corresponding author), E-mail:

References

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Received: 2013-2-15
Published Online: 2013-10-21
Published in Print: 2013-08-28

© 2013, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Selected contributions to the XXIInd symposium of the Atomic Energy Research organization
  7. Technical Contributions/Fachbeiträge
  8. Fuel cycles of WWER-440: results of basic design modification
  9. Use of erbium as burnable poison for VVER reactors
  10. The estimation of the control rods absorber burn-up during the VVER-1000 operation
  11. The main characteristic of the evolution project SuperVVER with spectrum shift regulation
  12. Automatic loading pattern optimization tool for Loviisa VVER-440 reactors
  13. Uncertainties of the neutronic calculations at core level determined by the KARATE code system and the KIKO3D code
  14. The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model
  15. Comparison of sensitivity and uncertainty in Gd and Er containing fuels for VVER-1000 using TSUNAMI-2D
  16. Contribution of the number of measured data to calculation uncertainty in the worth of VVER control rods
  17. A comparison of the FA's models with the detailed and simplified description in the MCU code calculations
  18. Account for uncertainties of control measurements in the assessment of design margin factors
  19. Results of precision calculations of three-dimensional power density in VVER-1000 core with feedbacks using MCU code
  20. CFD analysis of temperature deviations in Gd assembly heads
  21. Application of statistical uncertainty and sensitivity evaluations to a PWR LBLOCA analysis calculated with the code ATHLET. Part 1: uncertainty analysis
  22. Post test calculations of a severe accident experiment for VVER-440 reactors by the ATHLET code
  23. The impact on the competence on severe accidents following the Fukushima event
https://doi.org/10.3139/124.110378

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Selected contributions to the XXIInd symposium of the Atomic Energy Research organization
  7. Technical Contributions/Fachbeiträge
  8. Fuel cycles of WWER-440: results of basic design modification
  9. Use of erbium as burnable poison for VVER reactors
  10. The estimation of the control rods absorber burn-up during the VVER-1000 operation
  11. The main characteristic of the evolution project SuperVVER with spectrum shift regulation
  12. Automatic loading pattern optimization tool for Loviisa VVER-440 reactors
  13. Uncertainties of the neutronic calculations at core level determined by the KARATE code system and the KIKO3D code
  14. The reactor dynamics code DYN3D and its trigonal-geometry nodal diffusion model
  15. Comparison of sensitivity and uncertainty in Gd and Er containing fuels for VVER-1000 using TSUNAMI-2D
  16. Contribution of the number of measured data to calculation uncertainty in the worth of VVER control rods
  17. A comparison of the FA's models with the detailed and simplified description in the MCU code calculations
  18. Account for uncertainties of control measurements in the assessment of design margin factors
  19. Results of precision calculations of three-dimensional power density in VVER-1000 core with feedbacks using MCU code
  20. CFD analysis of temperature deviations in Gd assembly heads
  21. Application of statistical uncertainty and sensitivity evaluations to a PWR LBLOCA analysis calculated with the code ATHLET. Part 1: uncertainty analysis
  22. Post test calculations of a severe accident experiment for VVER-440 reactors by the ATHLET code
  23. The impact on the competence on severe accidents following the Fukushima event
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