PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440213 Nuclear Power Plants
Joint Authors
Tóth, I.
Szabados, L.
Ézsöl, Gy.
Perneczky, L.
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2012, Issue 2012 (31 Dec. 2012), pp.1-22, 22 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2011-10-30
Country of Publication
Egypt
No. of Pages
22
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP.
The facility was the first integral-type facility for VVERs.
The PMK-2 was followed later by the PACTEL (for VVER-440), the ISB, and PSB for VVER-1000.
Since the startup of the facility in 1985, 55 experiments have been performed primarily in international frameworks with the participation of experts from 29 European and overseas countries forming a scientific school to better understand VVER system behaviour and reach a high level of modelling of accident sequences.
The ATHLET, CATHARE, and RELAP5 codes have been validated including both qualitative and quantitative assessments.
The former was almost exclusively applied to the early phase of validation by integral experiments, while the quantitative assessments have been performed by the Fast Fourier Transform Based Method.
Paper gives comprehensive information on the design features of PMK-2 facility with a special respect to the representativeness of phenomena, the experiments performed, and the results of the validation of ATHLET, CATHARE, and RELAP5 codes.
Safety significance of the PMK-2 projects is also discussed.
American Psychological Association (APA)
Ézsöl, Gy.& Perneczky, L.& Szabados, L.& Tóth, I.. 2011. PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440213 Nuclear Power Plants. Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-22.
https://search.emarefa.net/detail/BIM-497420
Modern Language Association (MLA)
Ézsöl, Gy.…[et al.]. PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440213 Nuclear Power Plants. Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-22.
https://search.emarefa.net/detail/BIM-497420
American Medical Association (AMA)
Ézsöl, Gy.& Perneczky, L.& Szabados, L.& Tóth, I.. PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440213 Nuclear Power Plants. Science and Technology of Nuclear Installations. 2011. Vol. 2012, no. 2012, pp.1-22.
https://search.emarefa.net/detail/BIM-497420
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-497420