Integral Test Facility PKL: Experimental PWR Accident Investigation

Autor: Klaus Umminger, Lars Dennhardt, Simon Schollenberger, Bernhard Schoen
Jazyk: angličtina
Rok vydání: 2012
Předmět:
Zdroj: Science and Technology of Nuclear Installations, Vol 2012 (2012)
Druh dokumentu: article
ISSN: 1687-6075
1687-6083
DOI: 10.1155/2012/891056
Popis: Investigations of the thermal-hydraulic behavior of pressurized water reactors under accident conditions have been carried out in the PKL test facility at AREVA NP in Erlangen, Germany for many years. The PKL facility models the entire primary side and significant parts of the secondary side of a pressurized water reactor (PWR) at a height scale of 1 : 1. Volumes, power ratings and mass flows are scaled with a ratio of 1 : 145. The experimental facility consists of 4 primary loops with circulation pumps and steam generators (SGs) arranged symmetrically around the reactor pressure vessel (RPV). The investigations carried out encompass a very broad spectrum from accident scenario simulations with large, medium, and small breaks, over the investigation of shutdown procedures after a wide variety of accidents, to the systematic investigation of complex thermal-hydraulic phenomena. This paper presents a survey of test objectives and programs carried out to date. It also describes the test facility in its present state. Some important results obtained over the years with focus on investigations carried out since the beginning of the international cooperation are exemplarily discussed.
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