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

NameVTT Tiedotteita - Research Notes
PublisherVTT
Number2571
ISSN (Print)1235-0605
ISSN (Electronic)1455-0865

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Nuclear reactors
Hydraulics
Nuclear power plants
Computational fluid dynamics
Experiments
Hot Temperature

Cite this

Karppinen, I., Hillberg, S., Inkinen, P., Lauerma, S., Luukka, J., Kurki, J., ... Huhtanen, R. (2011). Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): THARE summary report. In SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report (pp. 204-215). Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Research Notes, No. 2571
Karppinen, Ismo ; Hillberg, Seppo ; Inkinen, Pasi ; Lauerma, Sampsa ; Luukka, Juha ; Kurki, Joona ; Silde, Ari ; Huhtanen, Risto. / Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE) : THARE summary report. SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo : VTT Technical Research Centre of Finland, 2011. pp. 204-215 (VTT Tiedotteita - Research Notes; No. 2571).
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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.",
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Karppinen, I, Hillberg, S, Inkinen, P, Lauerma, S, Luukka, J, Kurki, J, Silde, A & Huhtanen, R 2011, Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): THARE summary report. in SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. VTT Technical Research Centre of Finland, Espoo, VTT Tiedotteita - Research Notes, no. 2571, pp. 204-215.

Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE) : THARE summary report. / Karppinen, Ismo; Hillberg, Seppo; Inkinen, Pasi; Lauerma, Sampsa; Luukka, Juha; Kurki, Joona; Silde, Ari; Huhtanen, Risto.

SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo : VTT Technical Research Centre of Finland, 2011. p. 204-215 (VTT Tiedotteita - Research Notes; No. 2571).

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

TY - CHAP

T1 - Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE)

T2 - THARE summary report

AU - Karppinen, Ismo

AU - Hillberg, Seppo

AU - Inkinen, Pasi

AU - Lauerma, Sampsa

AU - Luukka, Juha

AU - Kurki, Joona

AU - Silde, Ari

AU - Huhtanen, Risto

PY - 2011

Y1 - 2011

N2 - 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.

AB - 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.

M3 - Chapter or book article

SN - 978-951-38-7689-0

T3 - VTT Tiedotteita - Research Notes

SP - 204

EP - 215

BT - SAFIR2010

PB - VTT Technical Research Centre of Finland

CY - Espoo

ER -

Karppinen I, Hillberg S, Inkinen P, Lauerma S, Luukka J, Kurki J et al. Improved Thermal Hydraulic Analysis of Nuclear Reactor and Containment (THARE): THARE summary report. In SAFIR2010: The Finnish Research Programme on Safety 2007-2010: Final Report. Espoo: VTT Technical Research Centre of Finland. 2011. p. 204-215. (VTT Tiedotteita - Research Notes; No. 2571).