RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium

Timo Vanttola (Editor)

    Research output: Book/ReportBook (editor)

    Abstract

    The Reactor Safety (RETU, 1995-1998) research programme concentrated on search of safe limits for nuclear fuel and the reactor core, accident management methods and risk management of nuclear power plants. The total volume of the programme was 100 person years and funding FIM 58 million. This symposium report summarises the research fields, the objectives and the main results obtained. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel was studied both in normal operation and during power transients. The static and dynamic reactor analysis codes were developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients. Advanced flow models and numerical solution methods for the dynamics codes were developed and tested. Research on accident management developed and validated calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Efforts were made to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme included experimental work, but also participation in large international tests. The Finnish thermal-hydraulic test facility PACTEL was 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 risk management probabilistic methods were developed for safety related decision making and for complex event sequences. Effects of maintenance on safety were studied and effective methods for assessment of human reliability and safety critical organisations were searched. To enhance human competencies in control of complex environments, practical tools for training and continuous learning were worked out, and methods to evaluate appropriateness of control room design were developed.
    Original languageEnglish
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Number of pages260
    ISBN (Print)951-38-5262-8
    Publication statusPublished - 1998
    MoE publication typeC2 Edited books
    EventRETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium - Espoo, Finland
    Duration: 24 Nov 199824 Nov 1998

    Publication series

    SeriesVTT Symposium
    Number189
    ISSN0357-9387

    Fingerprint

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

    Keywords

    • reactor safety
    • nuclear fuel
    • reactor physics
    • thermal-hydraulics
    • severe accidents
    • risk analysis

    Cite this

    Vanttola, T. (Ed.) (1998). RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium. Espoo: VTT Technical Research Centre of Finland. VTT Symposium, No. 189
    Vanttola, Timo (Editor). / RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium. Espoo : VTT Technical Research Centre of Finland, 1998. 260 p. (VTT Symposium; No. 189).
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    abstract = "The Reactor Safety (RETU, 1995-1998) research programme concentrated on search of safe limits for nuclear fuel and the reactor core, accident management methods and risk management of nuclear power plants. The total volume of the programme was 100 person years and funding FIM 58 million. This symposium report summarises the research fields, the objectives and the main results obtained. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel was studied both in normal operation and during power transients. The static and dynamic reactor analysis codes were developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients. Advanced flow models and numerical solution methods for the dynamics codes were developed and tested. Research on accident management developed and validated calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Efforts were made to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme included experimental work, but also participation in large international tests. The Finnish thermal-hydraulic test facility PACTEL was 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 risk management probabilistic methods were developed for safety related decision making and for complex event sequences. Effects of maintenance on safety were studied and effective methods for assessment of human reliability and safety critical organisations were searched. To enhance human competencies in control of complex environments, practical tools for training and continuous learning were worked out, and methods to evaluate appropriateness of control room design were developed.",
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    Vanttola, T (ed.) 1998, RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium. VTT Symposium, no. 189, VTT Technical Research Centre of Finland, Espoo.

    RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium. / Vanttola, Timo (Editor).

    Espoo : VTT Technical Research Centre of Finland, 1998. 260 p. (VTT Symposium; No. 189).

    Research output: Book/ReportBook (editor)

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    N2 - The Reactor Safety (RETU, 1995-1998) research programme concentrated on search of safe limits for nuclear fuel and the reactor core, accident management methods and risk management of nuclear power plants. The total volume of the programme was 100 person years and funding FIM 58 million. This symposium report summarises the research fields, the objectives and the main results obtained. In the field of operational margins of a nuclear reactor, the behaviour of high burnup nuclear fuel was studied both in normal operation and during power transients. The static and dynamic reactor analysis codes were developed and validated to cope with new fuel designs and complicated three-dimensional reactivity transients. Advanced flow models and numerical solution methods for the dynamics codes were developed and tested. Research on accident management developed and validated calculation methods needed to plan preventive measures and to train the personnel to severe accident mitigation. Efforts were made to reduce uncertainties in phenomena important in severe accidents and to study actions planned for accident management. The programme included experimental work, but also participation in large international tests. The Finnish thermal-hydraulic test facility PACTEL was 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 risk management probabilistic methods were developed for safety related decision making and for complex event sequences. Effects of maintenance on safety were studied and effective methods for assessment of human reliability and safety critical organisations were searched. To enhance human competencies in control of complex environments, practical tools for training and continuous learning were worked out, and methods to evaluate appropriateness of control room design were developed.

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    Vanttola T, (ed.). RETU: The Finnish Research Programme on Reactor Safety 1995-1998: Final Symposium. Espoo: VTT Technical Research Centre of Finland, 1998. 260 p. (VTT Symposium; No. 189).