Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): THARE summary report

Ismo Karppinen, Seppo Hillberg, Pasi Inkinen, Sampsa Lauerma, Juha Luukka, Joona Kurki, Ari Silde, Risto Huhtanen

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

Abstract

Calculation methods for evaluating safety of nuclear power plants has been enhanced by developing and validating both thermal hydraulic system codes APROS and TRACE and models in CFD code Fluent. Several experiments in national and international research programs have been calculated and results have compared with measured data. The validation cases has been chosen according the safety relevance of the studied phenomena and taking in account the specific features of the new plant concepts offered to Finnish utilities.
Original languageEnglish
Title of host publicationSAFIR2010
Subtitle of host publicationThe Finnish Research Programme on Safety 2007-2010: Final Report
Place of PublicationEspoo
PublisherVTT Technical Research Centre of Finland
Pages204-215
ISBN (Electronic)978-951-38-7690-6
ISBN (Print)978-951-38-7689-0
Publication statusPublished - 2011
MoE publication typeNot Eligible

Publication series

SeriesVTT Tiedotteita - Research Notes
Number2571
ISSN1235-0605

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