Improved thermal hydraulic analyses of nuclear reactor and containment (THARE): THARE summary report

Ismo Karppinen, Seppo Hillberg, Pasi Inkinen, Sampsa Lauerma, Joona Kurki, Markku Hänninen, Risto Huhtanen, Jarto Niemi

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Abstract

The main objectives of the THARE project are to develop and validate calculation methods for safety evaluation of nuclear power plants. The CCFL model of the APROS code has been validated with the IVO upper tie plate experiments. The analysis capabilities of APROS have been verified with the integral OECD/ROSA and OECD/PSB-VVER experiments. TRACE code validation has been started with creating a model of ROSA/LSTF test facility. Containment analysis methods have been enhanced by developing and validating a wall condensation model in Fluent CFD code and by validating the spray model of the APROS code.
Original languageEnglish
Title of host publicationSAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010
Subtitle of host publicationInterim Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages173-181
ISBN (Electronic)978-951-38-7267-0
ISBN (Print)978-951-38-7266-3
Publication statusPublished - 2009
MoE publication typeNot Eligible

Publication series

SeriesVTT Tiedotteita - Research Notes
Number2466
ISSN1235-0605

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    Karppinen, I., Hillberg, S., Inkinen, P., Lauerma, S., Kurki, J., Hänninen, M., Huhtanen, R., & Niemi, J. (2009). Improved thermal hydraulic analyses of nuclear reactor and containment (THARE): THARE summary report. In SAFIR2010: The Finnish Research Programme on Nuclear Power Plant Safety 2007-2010: Interim Report (pp. 173-181). VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2466 http://www.vtt.fi/inf/pdf/tiedotteet/2009/T2466.pdf