Simulation and analysis of pipe and vessel blowdown phenomena using RELAP5 and TRACE
Abstract
This paper presents results of pipe and vessel theoretical blowdown analysis in order to identify and assess basic rapid depressurization phenomena occurring during Loss of Coolant Accident e.g. in nuclear power plants. Therefore, calculations have been performed with 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 as well as a computational model built on the basis of available literature and implemented in the MATLAB® code. Finally, pipe depressurization results have been compared to experimental results taken from literature.References
[1] D’Auria F., Vigni P., Two-Phase Critical Flow Models, CSNI Report No. 49, 1980.
[2] Todreas N.E., Kazimi M.S., Nuclear Systems I Thermal Hydraulics Fundamentals, Taylor&Francis, 1993.
[3] Carlson K. E., Ransom V. H., Wagner R. J., The Application of RELAP5 to a Pipe Blowdown Experiment, Idaho National Engineering Laboratory, 1980.
[4] UK EPR Pre-Construction Safety Report, Areva NP & EDF, 2012. http://www.epr-reactor.co.uk/ (Styczeń, 2013).
[5] Lewandowski J., Mościcki M., „Porównanie granicznych modeli rozprzestrzeniania się pary w budynku reaktora w trakcie awarii typu LOCA”, Biuletyn Informacyjny Instytutu Techniki Cieplnej Politechniki Warszawskiej, Vol. 81, No. 81, 1995, pp. 13 – 22.
[6] Lahey R.T. Jr., Moody F.J., The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, American Nuclear Society, 1993.
[2] Todreas N.E., Kazimi M.S., Nuclear Systems I Thermal Hydraulics Fundamentals, Taylor&Francis, 1993.
[3] Carlson K. E., Ransom V. H., Wagner R. J., The Application of RELAP5 to a Pipe Blowdown Experiment, Idaho National Engineering Laboratory, 1980.
[4] UK EPR Pre-Construction Safety Report, Areva NP & EDF, 2012. http://www.epr-reactor.co.uk/ (Styczeń, 2013).
[5] Lewandowski J., Mościcki M., „Porównanie granicznych modeli rozprzestrzeniania się pary w budynku reaktora w trakcie awarii typu LOCA”, Biuletyn Informacyjny Instytutu Techniki Cieplnej Politechniki Warszawskiej, Vol. 81, No. 81, 1995, pp. 13 – 22.
[6] Lahey R.T. Jr., Moody F.J., The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, American Nuclear Society, 1993.
Published
2015-02-03
How to Cite
GURGACZ, Sebastian et al.
Simulation and analysis of pipe and vessel blowdown phenomena using RELAP5 and TRACE.
Journal of Power Technologies, [S.l.], v. 94, n. 5, p. 61--68, feb. 2015.
ISSN 2083-4195.
Available at: <https://papers.itc.pw.edu.pl/index.php/JPT/article/view/576>. Date accessed: 18 apr. 2024.
Section
Nuclear Power
Keywords
two-phase flow; two-phase flow simulation; nuclear engineering
Authors who publish with this journal agree to the following terms:
- Authors retain copyright and grant the journal right of first publication with the work simultaneously licensed under a Creative Commons Attribution License that allows others to share the work with an acknowledgement of the work's authorship and initial publication in this journal.
- Authors are able to enter into separate, additional contractual arrangements for the non-exclusive distribution of the journal's published version of the work (e.g., post it to an institutional repository or publish it in a book), with an acknowledgement of its initial publication in this journal.
- Authors are permitted and encouraged to post their work online (e.g., in institutional repositories or on their website) prior to and during the submission process, as it can lead to productive exchanges, as well as earlier and greater citation of published work (See The Effect of Open Access).
