Validation of coupled codes using VVER plant measurements

Timo Vanttola (Corresponding Author), Anitta Hämäläinen, S. Kliem, Y. Kozmenkov, F.-P. Weiss, A. Keresztúri, J. Hádek, C. Strmensky, S. Stefanova, A. Kuchin, P. Hlbocky, D. Siko, S. Danilin

Research output: Contribution to journalArticleScientificpeer-review

22 Citations (Scopus)

Abstract

A data set of five transients at different VVER type nuclear power plants was collected in order to validate neutron kinetics/thermal hydraulics codes. Two of these transients ‘drop of control rod at nominal power at Bohunice-3’ of VVER-440 type and ‘coast-down of 1 from 3 working MCPs at Kozloduy-6’ of VVER-1000 type, were then utilised for code validation. Eight institutes contributed to the validation with 10 calculations using 5 different combinations of coupled codes. The thermal hydraulic codes were ATHLET, SMABRE and RELAP5 and the neutron kinetic codes DYN3D, HEXTRAN, KIKO3D and BIPR8. The general behaviour of both the transients was quite well calculated with all the codes. Even an elementary modelling of coolant mixing in reactor pressure vessel under asymmetric transients improved correspondence to the measurements. Some differences between the calculations seem to indicate that fuel modelling and treatment of VVER-440 control rods need further consideration. The simultaneous validation interacted with the data collection effort and thus improved its quality. The complexity of data collection systems and sometimes conflicting data, however, called for compromises and interpretation guides that also taught the analysts balanced plant modelling.
Original languageEnglish
Pages (from-to)507 - 519
Number of pages13
JournalNuclear Engineering and Design
Volume235
Issue number2-4
DOIs
Publication statusPublished - 2005
MoE publication typeA1 Journal article-refereed

Fingerprint

Control rods
control rods
Neutrons
Hydraulics
hydraulics
Kinetics
Pressure vessels
Coolants
Nuclear power plants
modeling
Coastal zones
neutrons
kinetics
pressure vessels
nuclear power plants
coolants
nuclear power plant
coasts
code
vessel

Keywords

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

Cite this

Vanttola, Timo ; Hämäläinen, Anitta ; Kliem, S. ; Kozmenkov, Y. ; Weiss, F.-P. ; Keresztúri, A. ; Hádek, J. ; Strmensky, C. ; Stefanova, S. ; Kuchin, A. ; Hlbocky, P. ; Siko, D. ; Danilin, S. / Validation of coupled codes using VVER plant measurements. In: Nuclear Engineering and Design. 2005 ; Vol. 235, No. 2-4. pp. 507 - 519.
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title = "Validation of coupled codes using VVER plant measurements",
abstract = "A data set of five transients at different VVER type nuclear power plants was collected in order to validate neutron kinetics/thermal hydraulics codes. Two of these transients ‘drop of control rod at nominal power at Bohunice-3’ of VVER-440 type and ‘coast-down of 1 from 3 working MCPs at Kozloduy-6’ of VVER-1000 type, were then utilised for code validation. Eight institutes contributed to the validation with 10 calculations using 5 different combinations of coupled codes. The thermal hydraulic codes were ATHLET, SMABRE and RELAP5 and the neutron kinetic codes DYN3D, HEXTRAN, KIKO3D and BIPR8. The general behaviour of both the transients was quite well calculated with all the codes. Even an elementary modelling of coolant mixing in reactor pressure vessel under asymmetric transients improved correspondence to the measurements. Some differences between the calculations seem to indicate that fuel modelling and treatment of VVER-440 control rods need further consideration. The simultaneous validation interacted with the data collection effort and thus improved its quality. The complexity of data collection systems and sometimes conflicting data, however, called for compromises and interpretation guides that also taught the analysts balanced plant modelling.",
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Vanttola, T, Hämäläinen, A, Kliem, S, Kozmenkov, Y, Weiss, F-P, Keresztúri, A, Hádek, J, Strmensky, C, Stefanova, S, Kuchin, A, Hlbocky, P, Siko, D & Danilin, S 2005, 'Validation of coupled codes using VVER plant measurements', Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 507 - 519. https://doi.org/10.1016/j.nucengdes.2004.08.047

Validation of coupled codes using VVER plant measurements. / Vanttola, Timo (Corresponding Author); Hämäläinen, Anitta; Kliem, S.; Kozmenkov, Y.; Weiss, F.-P.; Keresztúri, A.; Hádek, J.; Strmensky, C.; Stefanova, S.; Kuchin, A.; Hlbocky, P.; Siko, D.; Danilin, S.

In: Nuclear Engineering and Design, Vol. 235, No. 2-4, 2005, p. 507 - 519.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Validation of coupled codes using VVER plant measurements

AU - Vanttola, Timo

AU - Hämäläinen, Anitta

AU - Kliem, S.

AU - Kozmenkov, Y.

AU - Weiss, F.-P.

AU - Keresztúri, A.

AU - Hádek, J.

AU - Strmensky, C.

AU - Stefanova, S.

AU - Kuchin, A.

AU - Hlbocky, P.

AU - Siko, D.

AU - Danilin, S.

PY - 2005

Y1 - 2005

N2 - A data set of five transients at different VVER type nuclear power plants was collected in order to validate neutron kinetics/thermal hydraulics codes. Two of these transients ‘drop of control rod at nominal power at Bohunice-3’ of VVER-440 type and ‘coast-down of 1 from 3 working MCPs at Kozloduy-6’ of VVER-1000 type, were then utilised for code validation. Eight institutes contributed to the validation with 10 calculations using 5 different combinations of coupled codes. The thermal hydraulic codes were ATHLET, SMABRE and RELAP5 and the neutron kinetic codes DYN3D, HEXTRAN, KIKO3D and BIPR8. The general behaviour of both the transients was quite well calculated with all the codes. Even an elementary modelling of coolant mixing in reactor pressure vessel under asymmetric transients improved correspondence to the measurements. Some differences between the calculations seem to indicate that fuel modelling and treatment of VVER-440 control rods need further consideration. The simultaneous validation interacted with the data collection effort and thus improved its quality. The complexity of data collection systems and sometimes conflicting data, however, called for compromises and interpretation guides that also taught the analysts balanced plant modelling.

AB - A data set of five transients at different VVER type nuclear power plants was collected in order to validate neutron kinetics/thermal hydraulics codes. Two of these transients ‘drop of control rod at nominal power at Bohunice-3’ of VVER-440 type and ‘coast-down of 1 from 3 working MCPs at Kozloduy-6’ of VVER-1000 type, were then utilised for code validation. Eight institutes contributed to the validation with 10 calculations using 5 different combinations of coupled codes. The thermal hydraulic codes were ATHLET, SMABRE and RELAP5 and the neutron kinetic codes DYN3D, HEXTRAN, KIKO3D and BIPR8. The general behaviour of both the transients was quite well calculated with all the codes. Even an elementary modelling of coolant mixing in reactor pressure vessel under asymmetric transients improved correspondence to the measurements. Some differences between the calculations seem to indicate that fuel modelling and treatment of VVER-440 control rods need further consideration. The simultaneous validation interacted with the data collection effort and thus improved its quality. The complexity of data collection systems and sometimes conflicting data, however, called for compromises and interpretation guides that also taught the analysts balanced plant modelling.

KW - nuclear power plants

KW - nuclear reactor safety

KW - nuclear safety

KW - validation

KW - code validation

KW - pressurized water reactors

U2 - 10.1016/j.nucengdes.2004.08.047

DO - 10.1016/j.nucengdes.2004.08.047

M3 - Article

VL - 235

SP - 507

EP - 519

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 2-4

ER -