RETU: The Finnish Research Programme on Reactor Safety: Interim Report 1995 - May 1997

Timo Vanttola, Eija-Karita Puska

    Research output: Book/ReportReport

    Abstract

    The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. The range of the models is extended by implementing advanced flow models and numerical solution methods. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme includes own experimental work, but participation in large international test programmes is of major importance. The Finnish thermal-hydraulic test facility PACTEL (Parallel Channel Test Loop) is used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. In order to enhance human competencies in the control of complex environments, practical tools for training and continuous learning are worked out, and methods to evaluate appropriateness of control room design are developed.
    Original languageEnglish
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Number of pages218
    ISBN (Electronic)951-38-5165-6
    ISBN (Print)951-38-5146-X
    Publication statusPublished - 1997
    MoE publication typeNot Eligible

    Publication series

    SeriesVTT Tiedotteita - Meddelanden - Research Notes
    Number1856
    ISSN1235-0605

    Fingerprint

    Accidents
    Nuclear fuels
    Risk management
    Nuclear power plants
    Reactor cores
    Nuclear reactors
    Test facilities
    Security systems
    Decision making
    Hydraulics
    Personnel
    Testing

    Keywords

    • nuclear power plants
    • nuclear reactors
    • reactor safety
    • nuclear reactor cores
    • accident prevention

    Cite this

    Vanttola, T., & Puska, E-K. (1997). RETU: The Finnish Research Programme on Reactor Safety: Interim Report 1995 - May 1997. Espoo: VTT Technical Research Centre of Finland. VTT Tiedotteita - Meddelanden - Research Notes, No. 1856
    Vanttola, Timo ; Puska, Eija-Karita. / RETU: The Finnish Research Programme on Reactor Safety : Interim Report 1995 - May 1997. Espoo : VTT Technical Research Centre of Finland, 1997. 218 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 1856).
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    abstract = "The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. The range of the models is extended by implementing advanced flow models and numerical solution methods. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme includes own experimental work, but participation in large international test programmes is of major importance. The Finnish thermal-hydraulic test facility PACTEL (Parallel Channel Test Loop) is used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. In order to enhance human competencies in the control of complex environments, practical tools for training and continuous learning are worked out, and methods to evaluate appropriateness of control room design are developed.",
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    author = "Timo Vanttola and Eija-Karita Puska",
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    Vanttola, T & Puska, E-K 1997, RETU: The Finnish Research Programme on Reactor Safety: Interim Report 1995 - May 1997. VTT Tiedotteita - Meddelanden - Research Notes, no. 1856, VTT Technical Research Centre of Finland, Espoo.

    RETU: The Finnish Research Programme on Reactor Safety : Interim Report 1995 - May 1997. / Vanttola, Timo; Puska, Eija-Karita.

    Espoo : VTT Technical Research Centre of Finland, 1997. 218 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 1856).

    Research output: Book/ReportReport

    TY - BOOK

    T1 - RETU: The Finnish Research Programme on Reactor Safety

    T2 - Interim Report 1995 - May 1997

    AU - Vanttola, Timo

    AU - Puska, Eija-Karita

    PY - 1997

    Y1 - 1997

    N2 - The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. The range of the models is extended by implementing advanced flow models and numerical solution methods. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme includes own experimental work, but participation in large international test programmes is of major importance. The Finnish thermal-hydraulic test facility PACTEL (Parallel Channel Test Loop) is used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. In order to enhance human competencies in the control of complex environments, practical tools for training and continuous learning are worked out, and methods to evaluate appropriateness of control room design are developed.

    AB - The Finnish national research programme on Reactor Safety (RETU, 1995-1998) concentrates on the search of safe limits of nuclear fuel and the reactor core, accident management methods and risk management of the operation of nuclear power plants. The annual volume of the programme has been about 26 person years and the annual funding FIM 15 million. This report summarises the structure and objectives of the programme, research fields included and the main results obtained during the period 1995 May 1997. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel is studied both in normal operation and during power transients. The static and dynamic reactor analysis codes are developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients and accidents. The range of the models is extended by implementing advanced flow models and numerical solution methods. Research on accident management aims at development and validation of calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Other goals are to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme includes own experimental work, but participation in large international test programmes is of major importance. The Finnish thermal-hydraulic test facility PACTEL (Parallel Channel Test Loop) is used extensively for the evaluation of the VVER-440 plant accident behaviour, for the validation of the accident analysis computer codes and for the testing of passive safety system concepts for future plant designs. In the field of risk management probabilistic methods are developed for safety related decision making and for complex phenomena and event sequences. Effects of maintenance on nuclear power plant safety are studied and more effective methods for the assessment of human reliability and safety critical organisations are searched. In order to enhance human competencies in the control of complex environments, practical tools for training and continuous learning are worked out, and methods to evaluate appropriateness of control room design are developed.

    KW - nuclear power plants

    KW - nuclear reactors

    KW - reactor safety

    KW - nuclear reactor cores

    KW - accident prevention

    M3 - Report

    SN - 951-38-5146-X

    T3 - VTT Tiedotteita - Meddelanden - Research Notes

    BT - RETU: The Finnish Research Programme on Reactor Safety

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Vanttola T, Puska E-K. RETU: The Finnish Research Programme on Reactor Safety: Interim Report 1995 - May 1997. Espoo: VTT Technical Research Centre of Finland, 1997. 218 p. (VTT Tiedotteita - Meddelanden - Research Notes; No. 1856).