Validation of coupled neutron kinetic/thermal-hydraulic codes: Part 2: Analysis of a VVER-440 transient (Loviisa-1)

Anitta Hämäläinen (Corresponding Author), Riitta Kyrki-Rajamäki, R. Mittag, S. Kliem, F. Weiss, S. Langenbuch, S. Danilin, J. Hadek, G. Hegyi

Research output: Contribution to journalArticleScientificpeer-review

24 Citations (Scopus)

Abstract

Several three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal-hydraulic system codes. Under the auspices of the European Union's Phare programme these codes have been validated against real plant transients by the participants from 7 countries. Two of the collected five transients were chosen for validation of the codes. Part 1 of this article consists of validation against VVER-1000 reactor data. This second part is focussed to validation against measured data of `One turbo-generator load drop experiment' at the Loviisa-1 VVER-440 reactor. The experiment was performed just after plant modernisation and more measured data was available to validation than in normal operation of real plants. Good accuracy of the results was generally achieved comparable to the measurement accuracy. The confidence in the results of the different code systems has increased, and consequences of certain model changes could be evaluated.
Original languageEnglish
Pages (from-to)255-269
JournalAnnals of Nuclear Energy
Volume29
Issue number3
DOIs
Publication statusPublished - 2002
MoE publication typeA1 Journal article-refereed

Fingerprint

Neutrons
Hydraulics
Kinetics
Modernization
Experiments
Hot Temperature
European Union

Keywords

  • accident modelling
  • field test
  • genetically modified organism
  • GMHAZID
  • risk assessment method
  • hazard identification
  • plants
  • research articles
  • risk analysis
  • risk evaluation
  • systematic hazard identificatione

Cite this

Hämäläinen, Anitta ; Kyrki-Rajamäki, Riitta ; Mittag, R. ; Kliem, S. ; Weiss, F. ; Langenbuch, S. ; Danilin, S. ; Hadek, J. ; Hegyi, G. / Validation of coupled neutron kinetic/thermal-hydraulic codes : Part 2: Analysis of a VVER-440 transient (Loviisa-1). In: Annals of Nuclear Energy. 2002 ; Vol. 29, No. 3. pp. 255-269.
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abstract = "Several three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal-hydraulic system codes. Under the auspices of the European Union's Phare programme these codes have been validated against real plant transients by the participants from 7 countries. Two of the collected five transients were chosen for validation of the codes. Part 1 of this article consists of validation against VVER-1000 reactor data. This second part is focussed to validation against measured data of `One turbo-generator load drop experiment' at the Loviisa-1 VVER-440 reactor. The experiment was performed just after plant modernisation and more measured data was available to validation than in normal operation of real plants. Good accuracy of the results was generally achieved comparable to the measurement accuracy. The confidence in the results of the different code systems has increased, and consequences of certain model changes could be evaluated.",
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Hämäläinen, A, Kyrki-Rajamäki, R, Mittag, R, Kliem, S, Weiss, F, Langenbuch, S, Danilin, S, Hadek, J & Hegyi, G 2002, 'Validation of coupled neutron kinetic/thermal-hydraulic codes: Part 2: Analysis of a VVER-440 transient (Loviisa-1)', Annals of Nuclear Energy, vol. 29, no. 3, pp. 255-269. https://doi.org/10.1016/S0306-4549(01)00039-1

Validation of coupled neutron kinetic/thermal-hydraulic codes : Part 2: Analysis of a VVER-440 transient (Loviisa-1). / Hämäläinen, Anitta (Corresponding Author); Kyrki-Rajamäki, Riitta; Mittag, R.; Kliem, S.; Weiss, F.; Langenbuch, S.; Danilin, S.; Hadek, J.; Hegyi, G.

In: Annals of Nuclear Energy, Vol. 29, No. 3, 2002, p. 255-269.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Validation of coupled neutron kinetic/thermal-hydraulic codes

T2 - Part 2: Analysis of a VVER-440 transient (Loviisa-1)

AU - Hämäläinen, Anitta

AU - Kyrki-Rajamäki, Riitta

AU - Mittag, R.

AU - Kliem, S.

AU - Weiss, F.

AU - Langenbuch, S.

AU - Danilin, S.

AU - Hadek, J.

AU - Hegyi, G.

PY - 2002

Y1 - 2002

N2 - Several three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal-hydraulic system codes. Under the auspices of the European Union's Phare programme these codes have been validated against real plant transients by the participants from 7 countries. Two of the collected five transients were chosen for validation of the codes. Part 1 of this article consists of validation against VVER-1000 reactor data. This second part is focussed to validation against measured data of `One turbo-generator load drop experiment' at the Loviisa-1 VVER-440 reactor. The experiment was performed just after plant modernisation and more measured data was available to validation than in normal operation of real plants. Good accuracy of the results was generally achieved comparable to the measurement accuracy. The confidence in the results of the different code systems has increased, and consequences of certain model changes could be evaluated.

AB - Several three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal-hydraulic system codes. Under the auspices of the European Union's Phare programme these codes have been validated against real plant transients by the participants from 7 countries. Two of the collected five transients were chosen for validation of the codes. Part 1 of this article consists of validation against VVER-1000 reactor data. This second part is focussed to validation against measured data of `One turbo-generator load drop experiment' at the Loviisa-1 VVER-440 reactor. The experiment was performed just after plant modernisation and more measured data was available to validation than in normal operation of real plants. Good accuracy of the results was generally achieved comparable to the measurement accuracy. The confidence in the results of the different code systems has increased, and consequences of certain model changes could be evaluated.

KW - accident modelling

KW - field test

KW - genetically modified organism

KW - GMHAZID

KW - risk assessment method

KW - hazard identification

KW - plants

KW - research articles

KW - risk analysis

KW - risk evaluation

KW - systematic hazard identificatione

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DO - 10.1016/S0306-4549(01)00039-1

M3 - Article

VL - 29

SP - 255

EP - 269

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

IS - 3

ER -