Assessment of RELAP5/MOD3.2 With the LSTF Experiment Simulating a Loss of Residual Heat Removal Event During Mid-Loop Operation (NUREG/IA-0143)
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Date Published: August 1998
K. W. Seul, Y. S. Bang, S. Lee, H. J. Kim
Korea Institute of Nuclear Safety
Advanced Reactor Dept.
P.O. Box 114
Prepared as part of:
The Agreement on Research Participation and Technical Exchange under the
International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
The potential for the RELAP5/MOD3.2 code was assessed for the loss of residual heat removal (RHR) event during the mid-loop operation. The predictability of major thermal hydraulic phenomena was evaluated for the long term transient. The results of two typical cases, cold leg opening (CLO) case with water-filled steam generators (SGs) and pressurizer opening (PRO) case with emptied SGs were compared with experimental data conducted at ROSA-IV/LSTF in Japan.
It was found that the code was capable of simulating the system responses to the loss-of-RHR event during the reduced inventory operation. The thermal hydraulic transport process including noncondensable gas behavior was reasonably predicted with an appropriate time setup and CPU time. Overall, the code well predicted the major thermal hydraulic phenomena during the transient.