PSB-VVER simulation of Kozloduy NPP “loss of feed water transient” |
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Authors: | PP Groudev AE Stefanova RV Gencheva MP Pavlova |
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Affiliation: | Institute for Nuclear Research and Nuclear Energy, Tzarigradsko Shaussee 72, Sofia 1784, Bulgaria |
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Abstract: | This paper provides a comparison between the PSB test facility experimental results obtained during the simulation of loss of feed water transient (LOFW) and the calculation results received by INRNE computer model of the same test facility. Integral thermal-hydraulic PSB-VVER test facility located at Electrogorsk Research and Engineering Center on NPPs Safety (EREC) was put in operation in 1998. The structure of the test facility allows experimental studies under steady state, transient and accident conditions.RELAP5/MOD3.2 computer code has been used to simulate the loss of feed water transient in a PSB-VVER model. This model was developed at the Institute for Nuclear Research and Nuclear Energy for simulation of loss of feed water transient.The objective of the experiment “loss of feed water”, which has been performed at PSB-VVER test facility is simulation of Kozloduy NPP LOFW transient. One of the main requirements to the experiment scenario has been to reproduce all main events and phenomena that occurred in Kozloduy NPP during the LOFW transient. Analyzing the PSB-VVER test with a RELAP5/MOD3.2 computer code as a standard problem allows investigating the phenomena included in the VVER code validation matrix as “integral system effects” and ”natural circulation“. For assessment of the RELAP5 capability to predict the “Integral system effect” phenomenon the following RELAP5 quantities are compared with external trends: the primary pressure and the hot and cold leg temperatures. In order to assess the RELAP5 capability to predict the “Natural circulation” phenomenon the hot and cold leg temperatures behavior have been investigated.This report was possible through the participation of leading specialists from Kozloduy NPP and with the support of Argonne National Laboratory (ANL), under the International Nuclear Safety Program (INSP) of the United States Department of Energy. |
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Keywords: | ANL Argonne National Laboratory BRU-K steam dumping devise to the condenser EREC Electrogorsk Research and Engineering Center on NPPs safety FASIV fast acting steam isolating valve INRNE-BAS Institute for Nuclear Research and Nuclear Energy-Bulgarian Academy of Sciences INSP International Nuclear Safety Program LOFW loss of feed water MCP main coolant pump MSH main steam header NPP nuclear power plant PRZ pressurizer SG steam generator |
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