Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility

S. Mittag (Corresponding Author), U. Grundmann, F.-P. Weiss, P.T. Petkov, Elja Kaloinen, A. Keresztúri, I. Panka, A. Kuchin, V. Ionov, D. Powney

Research output: Contribution to journalArticleScientificpeer-review

12 Citations (Scopus)

Abstract

Measurements carried out in an original-size VVER-1000 mock-up (V-1000 facility, Kurchatov Institute, Moscow) were used for the validation of three-dimensional neutron-kinetic codes, designed for VVER safety calculations. The significant neutron flux tilt measured in the V-1000 core, which is caused only by radial-reflector asymmetries, was successfully modeled. A good agreement between calculated and measured steady-state powers has been achieved, for relative assembly powers and inner-assembly pin power distributions. Calculated effective multiplication factors exceed unity in all cases. The time behaviour of local powers, measured during two transients that were initiated by control rod moving in a slightly super-critical core, has been well simulated by the neutron-kinetic codes.
Original languageEnglish
Pages (from-to)485 - 506
Number of pages22
JournalNuclear Engineering and Design
Volume235
Issue number2-4
DOIs
Publication statusPublished - 2005
MoE publication typeA1 Journal article-refereed

Fingerprint

Moscow
Neutrons
assembly
control rods
neutrons
Control rods
kinetics
Kinetics
Neutron flux
flux (rate)
multiplication
tilt
reflectors
unity
asymmetry
safety
code
distribution
calculation

Keywords

  • nuclear power plants
  • nuclear reactor safety
  • nuclear safety
  • validation
  • code validation
  • pressurized water reactors

Cite this

Mittag, S., Grundmann, U., Weiss, F-P., Petkov, P. T., Kaloinen, E., Keresztúri, A., ... Powney, D. (2005). Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility. Nuclear Engineering and Design, 235(2-4), 485 - 506. https://doi.org/10.1016/j.nucengdes.2004.08.043
Mittag, S. ; Grundmann, U. ; Weiss, F.-P. ; Petkov, P.T. ; Kaloinen, Elja ; Keresztúri, A. ; Panka, I. ; Kuchin, A. ; Ionov, V. ; Powney, D. / Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility. In: Nuclear Engineering and Design. 2005 ; Vol. 235, No. 2-4. pp. 485 - 506.
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Mittag, S, Grundmann, U, Weiss, F-P, Petkov, PT, Kaloinen, E, Keresztúri, A, Panka, I, Kuchin, A, Ionov, V & Powney, D 2005, 'Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility', Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 485 - 506. https://doi.org/10.1016/j.nucengdes.2004.08.043

Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility. / Mittag, S. (Corresponding Author); Grundmann, U.; Weiss, F.-P.; Petkov, P.T.; Kaloinen, Elja; Keresztúri, A.; Panka, I.; Kuchin, A.; Ionov, V.; Powney, D.

In: Nuclear Engineering and Design, Vol. 235, No. 2-4, 2005, p. 485 - 506.

Research output: Contribution to journalArticleScientificpeer-review

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T1 - Neutron-kinetic code validation against measurements in the Moscow V-1000 zero-power facility

AU - Mittag, S.

AU - Grundmann, U.

AU - Weiss, F.-P.

AU - Petkov, P.T.

AU - Kaloinen, Elja

AU - Keresztúri, A.

AU - Panka, I.

AU - Kuchin, A.

AU - Ionov, V.

AU - Powney, D.

PY - 2005

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AB - Measurements carried out in an original-size VVER-1000 mock-up (V-1000 facility, Kurchatov Institute, Moscow) were used for the validation of three-dimensional neutron-kinetic codes, designed for VVER safety calculations. The significant neutron flux tilt measured in the V-1000 core, which is caused only by radial-reflector asymmetries, was successfully modeled. A good agreement between calculated and measured steady-state powers has been achieved, for relative assembly powers and inner-assembly pin power distributions. Calculated effective multiplication factors exceed unity in all cases. The time behaviour of local powers, measured during two transients that were initiated by control rod moving in a slightly super-critical core, has been well simulated by the neutron-kinetic codes.

KW - nuclear power plants

KW - nuclear reactor safety

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KW - code validation

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