Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4)

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

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Abstract

Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal–hydraulic system codes. In the EU Phare project SRR1/95 these codes have been validated against real plant transients by the participants from several countries. Data measured during a test in the Balakovo-4 VVER-1000 have been analysed by coupled codes. In the test, one of two working feed water pumps of the steam generators was switched off at nominal power. The steady-state assembly powers measured before and after this transient are reproduced by the codes with a maximum deviation of about 5%. The time behaviour of the most safety-relevant parameters, such as total fission power, coolant temperatures and pressures is well modelled. Thermal–hydraulic feedback effects observed in the measurement are described by the codes in a consistent manner. The analyses have shown, that an accurate treatment of the heat transfer from the fuel rods to the coolant is important. In all, the results have increased the confidence in the coupled code analyses of VVER-1000 transients.
Original languageEnglish
Pages (from-to)857-873
Number of pages7
JournalAnnals of Nuclear Energy
Volume28
Issue number9
DOIs
Publication statusPublished - 2001
MoE publication typeA1 Journal article-refereed

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Neutrons
Hydraulics
Coolants
Kinetics
Steam generators
Pumps
Heat transfer
Feedback
Hot Temperature
Water
Temperature

Cite this

Mittag, R. ; Kliem, S. ; Weiss, F. ; Kyrki-Rajamäki, Riitta ; Hämäläinen, Anitta ; Langenbuch, S. ; Danilin, S. ; Hadek, J. ; Hegyi, G. ; Kuchin, A. ; Panayotov, D. / Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1 : Analysis of a VVER-1000 transient (Balakovo-4). In: Annals of Nuclear Energy. 2001 ; Vol. 28, No. 9. pp. 857-873.
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abstract = "Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal–hydraulic system codes. In the EU Phare project SRR1/95 these codes have been validated against real plant transients by the participants from several countries. Data measured during a test in the Balakovo-4 VVER-1000 have been analysed by coupled codes. In the test, one of two working feed water pumps of the steam generators was switched off at nominal power. The steady-state assembly powers measured before and after this transient are reproduced by the codes with a maximum deviation of about 5{\%}. The time behaviour of the most safety-relevant parameters, such as total fission power, coolant temperatures and pressures is well modelled. Thermal–hydraulic feedback effects observed in the measurement are described by the codes in a consistent manner. The analyses have shown, that an accurate treatment of the heat transfer from the fuel rods to the coolant is important. In all, the results have increased the confidence in the coupled code analyses of VVER-1000 transients.",
author = "R. Mittag and S. Kliem and F. Weiss and Riitta Kyrki-Rajam{\"a}ki and Anitta H{\"a}m{\"a}l{\"a}inen and S. Langenbuch and S. Danilin and J. Hadek and G. Hegyi and A. Kuchin and D. Panayotov",
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Mittag, R, Kliem, S, Weiss, F, Kyrki-Rajamäki, R, Hämäläinen, A, Langenbuch, S, Danilin, S, Hadek, J, Hegyi, G, Kuchin, A & Panayotov, D 2001, 'Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1: Analysis of a VVER-1000 transient (Balakovo-4)', Annals of Nuclear Energy, vol. 28, no. 9, pp. 857-873. https://doi.org/10.1016/S0306-4549(00)00095-5

Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1 : Analysis of a VVER-1000 transient (Balakovo-4). / Mittag, R. (Corresponding Author); Kliem, S.; Weiss, F.; Kyrki-Rajamäki, Riitta; Hämäläinen, Anitta; Langenbuch, S.; Danilin, S.; Hadek, J.; Hegyi, G.; Kuchin, A.; Panayotov, D.

In: Annals of Nuclear Energy, Vol. 28, No. 9, 2001, p. 857-873.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Validation of coupled neutron kinetic/thermal-hydraulic codes. Part 1

T2 - Analysis of a VVER-1000 transient (Balakovo-4)

AU - Mittag, R.

AU - Kliem, S.

AU - Weiss, F.

AU - Kyrki-Rajamäki, Riitta

AU - Hämäläinen, Anitta

AU - Langenbuch, S.

AU - Danilin, S.

AU - Hadek, J.

AU - Hegyi, G.

AU - Kuchin, A.

AU - Panayotov, D.

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AB - Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal–hydraulic system codes. In the EU Phare project SRR1/95 these codes have been validated against real plant transients by the participants from several countries. Data measured during a test in the Balakovo-4 VVER-1000 have been analysed by coupled codes. In the test, one of two working feed water pumps of the steam generators was switched off at nominal power. The steady-state assembly powers measured before and after this transient are reproduced by the codes with a maximum deviation of about 5%. The time behaviour of the most safety-relevant parameters, such as total fission power, coolant temperatures and pressures is well modelled. Thermal–hydraulic feedback effects observed in the measurement are described by the codes in a consistent manner. The analyses have shown, that an accurate treatment of the heat transfer from the fuel rods to the coolant is important. In all, the results have increased the confidence in the coupled code analyses of VVER-1000 transients.

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DO - 10.1016/S0306-4549(00)00095-5

M3 - Article

VL - 28

SP - 857

EP - 873

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

SN - 0306-4549

IS - 9

ER -