Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre

Elina Syrjälahti, Anitta Hämäläinen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

The best-estimate modelling of nuclear power plants is part of the modern safety analysis. Because with three-dimensional neutron kinetics codes conservatism of all assumptions cannot be guaranteed, present trend is to use best-estimate analysis and to complete them with sensitivity and uncertainty methods. Especially statistical methods demand large amount of transient calculations. For that reason new sensitivity tool was programmed. The sensitivity analysis tool makes it possible to easily perform large amount of transient calculations with varied values of input parameters without remarkable amount of extra work. The main steam line break is one of the basic cases to be analysed as a part of the safety analysis of a pressurized water reactor. Its accurate modelling is very demanding task, because various complicated processes such as asymmetric power generation, flow mixing in the reactor vessel and various protection and conventional automation signals, contribute to the scenario. In this paper, sensitivity analysis tool has been utilised in the analysis of the main steam line break of the Loviisa VVER-440 power plant. Previous analysis has shown that the worst case might be reached with a smaller break size than double-ended guillotine break. In this paper, worst case has been searched by using several break sizes, by assuming failure of some protection systems and also starting from different initial power levels.
Original languageEnglish
Title of host publicationProceedings of the PHYSOR 2010
Place of PublicationLaGrange Park, IL
PublisherAmerican Nuclear Society ANS
Pages2358-2373
ISBN (Print)978-0-89448-079-9
Publication statusPublished - 2010
MoE publication typeA4 Article in a conference publication
EventAdvances in Reactor physics to Power the Nuclear Renaissance, PHYSOR 2010 - Pittsburgh, PA, United States
Duration: 9 May 201014 May 2010

Conference

ConferenceAdvances in Reactor physics to Power the Nuclear Renaissance, PHYSOR 2010
Abbreviated titlePHYSOR 2010
CountryUnited States
CityPittsburgh, PA
Period9/05/1014/05/10

Fingerprint

Steam piping systems
Sensitivity analysis
Pressurized water reactors
Nuclear power plants
Power generation
Statistical methods
Power plants
Neutrons
Automation
Kinetics

Keywords

  • HEXTRAN-SMABRE
  • Steam line break
  • Uncertainty analysis

Cite this

Syrjälahti, E., & Hämäläinen, A. (2010). Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre. In Proceedings of the PHYSOR 2010 (pp. 2358-2373). LaGrange Park, IL: American Nuclear Society ANS.
Syrjälahti, Elina ; Hämäläinen, Anitta. / Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre. Proceedings of the PHYSOR 2010. LaGrange Park, IL : American Nuclear Society ANS, 2010. pp. 2358-2373
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Syrjälahti, E & Hämäläinen, A 2010, Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre. in Proceedings of the PHYSOR 2010. American Nuclear Society ANS, LaGrange Park, IL, pp. 2358-2373, Advances in Reactor physics to Power the Nuclear Renaissance, PHYSOR 2010, Pittsburgh, PA, United States, 9/05/10.

Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre. / Syrjälahti, Elina; Hämäläinen, Anitta.

Proceedings of the PHYSOR 2010. LaGrange Park, IL : American Nuclear Society ANS, 2010. p. 2358-2373.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Syrjälahti E, Hämäläinen A. Sensitivity studies for the main steam line break in the Loviisa NPP with the Hextran-Smabre. In Proceedings of the PHYSOR 2010. LaGrange Park, IL: American Nuclear Society ANS. 2010. p. 2358-2373