Performance of passive safety injection systems of advanced light water reactors

Jari Tuunanen

Research output: Contribution to journalArticleProfessional

Abstract

VTT Energy, in co-operation with Lappeenranta University of Technology, has run experiments in the PACTEL thermal-hydraulic test loop to study the performance of Passive Safety Injection Systems (PSISs) during loss-of-coolant accidents in Advanced Light Water Reactors (ALWRs) being designed for commercial use within the next 3-10 years. The experiments were a part of the European Commission's Nuclear Fission Safety programme. The main objectives of the project were to provide new and independent experiment data on the PSISs used in ALWRs, to create a data base for users and developers of thermal-hydraulic computer codes on the behaviour of PSISs, and to identify the accuracy, uncertainties and limitations of existing thermal-hydraulic codes in the modelling of PSISs. The PACTEL experiments served the first two objectives. The computer code simulations of selected experiments, still under way, will serve the third objective.
Original languageEnglish
Pages (from-to)31-34
JournalVTT Energy Highlights
Publication statusPublished - 1998
MoE publication typeD1 Article in a trade journal

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Light water reactors
Hydraulics
Experiments
Fission reactions
Loss of coolant accidents
Hot Temperature

Cite this

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title = "Performance of passive safety injection systems of advanced light water reactors",
abstract = "VTT Energy, in co-operation with Lappeenranta University of Technology, has run experiments in the PACTEL thermal-hydraulic test loop to study the performance of Passive Safety Injection Systems (PSISs) during loss-of-coolant accidents in Advanced Light Water Reactors (ALWRs) being designed for commercial use within the next 3-10 years. The experiments were a part of the European Commission's Nuclear Fission Safety programme. The main objectives of the project were to provide new and independent experiment data on the PSISs used in ALWRs, to create a data base for users and developers of thermal-hydraulic computer codes on the behaviour of PSISs, and to identify the accuracy, uncertainties and limitations of existing thermal-hydraulic codes in the modelling of PSISs. The PACTEL experiments served the first two objectives. The computer code simulations of selected experiments, still under way, will serve the third objective.",
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Performance of passive safety injection systems of advanced light water reactors. / Tuunanen, Jari.

In: VTT Energy Highlights, 1998, p. 31-34.

Research output: Contribution to journalArticleProfessional

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N2 - VTT Energy, in co-operation with Lappeenranta University of Technology, has run experiments in the PACTEL thermal-hydraulic test loop to study the performance of Passive Safety Injection Systems (PSISs) during loss-of-coolant accidents in Advanced Light Water Reactors (ALWRs) being designed for commercial use within the next 3-10 years. The experiments were a part of the European Commission's Nuclear Fission Safety programme. The main objectives of the project were to provide new and independent experiment data on the PSISs used in ALWRs, to create a data base for users and developers of thermal-hydraulic computer codes on the behaviour of PSISs, and to identify the accuracy, uncertainties and limitations of existing thermal-hydraulic codes in the modelling of PSISs. The PACTEL experiments served the first two objectives. The computer code simulations of selected experiments, still under way, will serve the third objective.

AB - VTT Energy, in co-operation with Lappeenranta University of Technology, has run experiments in the PACTEL thermal-hydraulic test loop to study the performance of Passive Safety Injection Systems (PSISs) during loss-of-coolant accidents in Advanced Light Water Reactors (ALWRs) being designed for commercial use within the next 3-10 years. The experiments were a part of the European Commission's Nuclear Fission Safety programme. The main objectives of the project were to provide new and independent experiment data on the PSISs used in ALWRs, to create a data base for users and developers of thermal-hydraulic computer codes on the behaviour of PSISs, and to identify the accuracy, uncertainties and limitations of existing thermal-hydraulic codes in the modelling of PSISs. The PACTEL experiments served the first two objectives. The computer code simulations of selected experiments, still under way, will serve the third objective.

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