Simulation and analysis of pipe and vessel blowdown phenomena using RELAP5 and TRACE

• Autorzy: Gurgacz S. , Pawluczyk M. , Niewiński G. , Mazgaj P.
• Języki publikacji: EN

Abstrakty

EN

This paper presents the results of a pipe and vessel theoretical blowdown analysis in order to identify and assess rapid depressurization phenomena occurring during a Loss of Coolant Accident in a nuclear power plant. Calculations were performed in conditions similar to those in a reactor pressure vessel. Due to critical two-phase flow occurrence, RELAP5 mod 3.3. and TRACE v 3.0 system codes were used for this purpose and a computational model was built on the basis of available literature and implemented in MATLABr code. Finally, pipe depressurization results were compared to experimental results taken from the literature.

Słowa kluczowe

EN

two-phase flow; two-phase flow simulation; nuclear engineering

PL

przepływ dwufazowy; symulacja przepływu dwufazowego; inżynieria jądrowa

• Wydawca: Institute of Heat Engineering, Warsaw University of Technology
• Czasopismo: Journal of Power Technologies
• Rocznik: 2014
• Tom: Vol. 94, nr 5
• Strony: 61--68
• Opis fizyczny: Bibliogr. 6 poz., rys., tab., wykr.

Twórcy

autor

Gurgacz S.

• Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Street, 00-665 Warsaw, Poland

autor

Pawluczyk M.

• Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Street, 00-665 Warsaw, Poland

autor

Niewiński G.

• Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Street, 00-665 Warsaw, Poland

autor

Mazgaj P.

• Institute of Heat Engineering, Warsaw University of Technology, 21/25 Nowowiejska Street, 00-665 Warsaw, Poland

Bibliografia

• [1] F. D’Auria, P. Vigni, Two-phase critical flow models, Tech. Rep. 49, CSNI (1980).
• [2] N. E. Todreas, M. S. Kazimi, Nuclear Systems I Thermal Hydraulics Fundamentals, Taylor & Francis, 1993.
• [3] K. E. Carlson, V. H. Ransom, R. J. Wagner, The Application of RELAP5 to a Pipe Blowdown Experiment, Idaho National Engineering Laboratory, 1980.
• [4] Areva NP&EDF, UK EPR Pre-Construction Safety Report (2012). URL http://www.epr-reactor.co.uk/
• [5] J. Lewandowski, M. Mościcki, Porównanie granicznych modeli rozprzestrzeniania się pary w budynku reaktora w trakcie awarii typu loca, Biuletyn Informacyjny Instytutu Techniki Cieplnej Politechniki Warszawskiej 81 (1995) 13–22.
• [6] R. T. J. Lahey, F. J. Moody, The Thermal-Hydraulics of a BoilingWater Nuclear Reactor, American Nuclear Society, 1993.