Open AccessAnalysis of measured and calculated counterpart test data in PWR and VVER 1000 simulators
Author(s) -
Francesco Saverio D'Auria,
M. Cherubini,
Maria Giorgio Galassi,
N. Muellner
Publication year - 2005
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp0501003d
Subject(s) - vver , scaling , pressurized water reactor , nuclear engineering , thermal hydraulics , transient (computer programming) , computer science , code (set theory) , scale (ratio) , nuclear reactor , nuclear data , nuclear physics , physics , mechanics , mathematics , engineering , neutron , heat transfer , geometry , set (abstract data type) , quantum mechanics , programming language , operating system
This paper presents an over view of the "scaling strategy", in particular the role played by the counter part test methodology. The recent studies dealing with a scaling analysis in light water reactor with special regard to the VVER 1000 Russian reactor type are presented to demonstrate the phenomena important for scaling. The adopted scaling approach is based on the selection of a few characteristic parameters chosen by taking into account their relevance in the behavior of the transient. The adopted computer code used is RELAP5/Mod3.3 and its accuracy has been demonstrated by qualitative and quantitative evaluation. Comparing experimental data, it was found that the investigated facilities showed similar behavior concerning the time trends, and that the same thermal hydraulic phenomena on a qualitative level could be predicted. The main results are: PSB and LOBI main parameters have similar trends. This fact is the confirmation of the validity of the adopted scaling approach and it shows that PWR and VVER reactor type behavior is very similar. No new phenomena occurred during the counter part test, despite the fact that the two facilities had a different lay out, and the already known phenomena were predicted correctly by the code. The code capability and accuracy are scale-independent. Both character is tics are necessary to permit the full scale calculation with the aim of nuclear power plant behavior prediction.