RELAP5/MOD3.2.2 Gamma Assessment For Down To Top Reflooding Process At VVER Like 37-Rod Bundle (NUREG/IA-0207)
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Date Published: July 2002
Russian Research Center "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
The assessment of RELAP5/MOD3.2.2 Gamma for down to top reflooding at VVER like 37-rod bundle is presented. The experiment have been performed at IPPE test facility at the following parameters: upper plenum pressure- 0,246 MPa, cooling water temperature- 51°C, water velocity- 4.91 sm/s, average linear heat flux density at maximal heat production zone before water supply-1,77 kWt/m. RELAP5/MOD3.2.2Gamma assessment showed that code gives satisfactory results for all parameters behavior. The main discrepancies were get for cladding temperature behavior at level H-2.7m, where the calculated cladding temperatures exceed experimental data approximately on 75 K. Computed quenching time for this level are much higher experimental ones. For other levels accordance between experimental and RELAP data is rather good.