Comprehensive uncertainty and sensitivity analysis for coupled code calculations of VVER plant transients
| Autor: | S. Danilin, S. Langenbuch, S. Nikonov, Anitta Hämäläinen, Sören Kliem, G. Hegyi, B. Krzykacz-Hausmann, J. Hadek, V. Khalimanchuk, A. Keresztúri, K.-D. Schmidt, A. Kuchin |
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| Jazyk: | angličtina |
| Rok vydání: | 2005 |
| Předmět: |
Nuclear and High Energy Physics
Engineering business.industry Mechanical Engineering Nuclear engineering Pressurized water reactor Mechanical engineering Nuclear reactor law.invention Thermal hydraulics Nuclear Energy and Engineering law code validation Benchmark (surveying) Nuclear power plant pressurized water reactors nuclear power plants General Materials Science Sensitivity (control systems) Transient (oscillation) VVER Safety Risk Reliability and Quality business Waste Management and Disposal |
| Zdroj: | 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 |
| DOI: | 10.1016/j.nucengdes.2004.09.003 |
| Popis: | 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. |
| Databáze: | OpenAIRE |
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