Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients

S. Langenbuch (Corresponding Author), B. Krzykacz-Hausmann, K.-D. Schmidt, G. Hegyi, A. Keresztúri, S. Kliem, J. Hadek, S. Danilin, S. Nikonov, A. Kuchin, V. Khalimanchuk, Anitta Hämäläinen

Research output: Contribution to journalArticleScientificpeer-review

15 Citations (Scopus)

Abstract

The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics codes, is an important step to perform best-estimate calculations for plant transients of nuclear power plants. For applications in safety analysis, these coupled codes should be validated by benchmark calculations and, preferably, by comparison with plant transient data from operating plants. In addition, the results should be supplemented by applying uncertainty and sensitivity analysis methods, which allow to identify relevant parameters of models and solution procedures affecting the results and to quantify their relative importance. Both objectives were part of the VALCO project. The aspect of validation is presented in [S. Mittag, et al., 2004. Neutron-Kinetic Code Validation against Measurements in the Moscow V-1000 Zero-Power Facility, in press; T. Vanttola et al., 2004. Validation of coupled codes using VVER plant measurements, in press], the aspect of a comprehensive uncertainty and sensitivity analysis for coupled code calculations is the topic of this contribution. The results and experiences obtained by the analysis for two plant transients in a VVER-440 and a VVER-1000, respectively, are presented and discussed.
Original languageEnglish
Pages (from-to)521 - 540
Number of pages20
JournalNuclear Engineering and Design
Volume235
Issue number2-4
DOIs
Publication statusPublished - 2005
MoE publication typeA1 Journal article-refereed

Fingerprint

Uncertainty analysis
uncertainty analysis
sensitivity analysis
Sensitivity analysis
Neutrons
Kinetics
Nuclear power plants
Hydraulics
hydraulic equipment
neutrons
kinetics
Moscow
nuclear power plants
nuclear power plant
code
calculation
safety
hydraulics
estimates

Keywords

  • nuclear power plants
  • code validation
  • pressurized water reactors

Cite this

Langenbuch, S. ; Krzykacz-Hausmann, B. ; Schmidt, K.-D. ; Hegyi, G. ; Keresztúri, A. ; Kliem, S. ; Hadek, J. ; Danilin, S. ; Nikonov, S. ; Kuchin, A. ; Khalimanchuk, V. ; Hämäläinen, Anitta. / Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients. In: Nuclear Engineering and Design. 2005 ; Vol. 235, No. 2-4. pp. 521 - 540.
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abstract = "The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics codes, is an important step to perform best-estimate calculations for plant transients of nuclear power plants. For applications in safety analysis, these coupled codes should be validated by benchmark calculations and, preferably, by comparison with plant transient data from operating plants. In addition, the results should be supplemented by applying uncertainty and sensitivity analysis methods, which allow to identify relevant parameters of models and solution procedures affecting the results and to quantify their relative importance. Both objectives were part of the VALCO project. The aspect of validation is presented in [S. Mittag, et al., 2004. Neutron-Kinetic Code Validation against Measurements in the Moscow V-1000 Zero-Power Facility, in press; T. Vanttola et al., 2004. Validation of coupled codes using VVER plant measurements, in press], the aspect of a comprehensive uncertainty and sensitivity analysis for coupled code calculations is the topic of this contribution. The results and experiences obtained by the analysis for two plant transients in a VVER-440 and a VVER-1000, respectively, are presented and discussed.",
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Langenbuch, S, Krzykacz-Hausmann, B, Schmidt, K-D, Hegyi, G, Keresztúri, A, Kliem, S, Hadek, J, Danilin, S, Nikonov, S, Kuchin, A, Khalimanchuk, V & Hämäläinen, A 2005, 'Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients', Nuclear Engineering and Design, vol. 235, no. 2-4, pp. 521 - 540. https://doi.org/10.1016/j.nucengdes.2004.09.003

Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients. / Langenbuch, S. (Corresponding Author); Krzykacz-Hausmann, B.; Schmidt, K.-D.; Hegyi, G.; Keresztúri, A.; Kliem, S.; Hadek, J.; Danilin, S.; Nikonov, S.; Kuchin, A.; Khalimanchuk, V.; Hämäläinen, Anitta.

In: Nuclear Engineering and Design, Vol. 235, No. 2-4, 2005, p. 521 - 540.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients

AU - Langenbuch, S.

AU - Krzykacz-Hausmann, B.

AU - Schmidt, K.-D.

AU - Hegyi, G.

AU - Keresztúri, A.

AU - Kliem, S.

AU - Hadek, J.

AU - Danilin, S.

AU - Nikonov, S.

AU - Kuchin, A.

AU - Khalimanchuk, V.

AU - Hämäläinen, Anitta

PY - 2005

Y1 - 2005

N2 - The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics codes, is an important step to perform best-estimate calculations for plant transients of nuclear power plants. For applications in safety analysis, these coupled codes should be validated by benchmark calculations and, preferably, by comparison with plant transient data from operating plants. In addition, the results should be supplemented by applying uncertainty and sensitivity analysis methods, which allow to identify relevant parameters of models and solution procedures affecting the results and to quantify their relative importance. Both objectives were part of the VALCO project. The aspect of validation is presented in [S. Mittag, et al., 2004. Neutron-Kinetic Code Validation against Measurements in the Moscow V-1000 Zero-Power Facility, in press; T. Vanttola et al., 2004. Validation of coupled codes using VVER plant measurements, in press], the aspect of a comprehensive uncertainty and sensitivity analysis for coupled code calculations is the topic of this contribution. The results and experiences obtained by the analysis for two plant transients in a VVER-440 and a VVER-1000, respectively, are presented and discussed.

AB - The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics codes, is an important step to perform best-estimate calculations for plant transients of nuclear power plants. For applications in safety analysis, these coupled codes should be validated by benchmark calculations and, preferably, by comparison with plant transient data from operating plants. In addition, the results should be supplemented by applying uncertainty and sensitivity analysis methods, which allow to identify relevant parameters of models and solution procedures affecting the results and to quantify their relative importance. Both objectives were part of the VALCO project. The aspect of validation is presented in [S. Mittag, et al., 2004. Neutron-Kinetic Code Validation against Measurements in the Moscow V-1000 Zero-Power Facility, in press; T. Vanttola et al., 2004. Validation of coupled codes using VVER plant measurements, in press], the aspect of a comprehensive uncertainty and sensitivity analysis for coupled code calculations is the topic of this contribution. The results and experiences obtained by the analysis for two plant transients in a VVER-440 and a VVER-1000, respectively, are presented and discussed.

KW - nuclear power plants

KW - code validation

KW - pressurized water reactors

U2 - 10.1016/j.nucengdes.2004.09.003

DO - 10.1016/j.nucengdes.2004.09.003

M3 - Article

VL - 235

SP - 521

EP - 540

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 2-4

ER -