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          NRC Library  Document Collections  NUREG-Series Publications  Publications Resulting from International AgreementsAssessment Study of RELAP5/MOD3.2 Based on the Kalinin NPP Unit-1 Stop of Feedwater Supply to the Steam Generator No. 4 (NUREG/IA-0167)

On this page: Publication Information AbstractDownload complete document NUREG/IA-0167 (PDF 5.87 MB)Publication Information **Date Published:** October 1999 **Prepared by:** S. S. Pylev Nuclear Safety Institute Russian Research Centre "Kurchatov Institute" Kurchatov Square, 1 123182, Moscow Russia **Prepared as part of:** The Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP) Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Availability Notice Abstract This report has been prepared as a part of the Agreement on Research Participation and Technical Exchange under the Code Assessment and Maintenance Program. The data collected by Kalinin NPP Unit-1 Data Acquisition System and In-Vessel Monitoring System during stop of feedwater supply to the SG-4 transient have been analyzed by using the RELAP5/MOD3.2 and RELAP5/MOD3.2.2Beta codes. Kalinin NPP-1 is a Russian designed four loop pressurized water reactor (VVER-1000, project V-338) rated at 1000 MWe. RELAP5 code calculated results were compared with plant data. Sensitivity studies were carried out to investigate the effects of modeling on major thermal-hydraulic parameters and to examine a new heat transfer model for horizontal tube bundles. 
      
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