Assessment 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)

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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

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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.