1. Reflood Investigation of Model Fuel Assemblies of Light-Water Reactors for a Loss-of-Coolant Accident
- Author
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E. B. Popov, S. S. Bazyuk, N. Ya. Parshin, and Yu. A. Kuzma-Kichta
- Subjects
Materials science ,Nuclear Energy and Engineering ,Heat flux ,Nuclear engineering ,Mass velocity ,Wetting front ,VVER ,Residual ,Loss-of-coolant accident - Abstract
The results of a reflood investigation of model VVER and PWR fuel assemblies for maximum design-basis and beyond design-basis accidents performed on the RBHT, SVD, and PARAMETR stands are presented. The variation ranges of the regime parameters are: initial temperature of fuel element 460–600°C; mass velocity of water 47–160 kg/(m2·sec), underheating at the entry into the model fuel assembly 11–108°C; pressure 0.14–0.42 MPa; and, linear heat flux density simulating the residual heat release 0–2.3 kW/m. A colligating relation describing the experimental data to within 30% is obtained for the wetting front of model fuel assemblies, which makes it possible to calculate the cool-down time of model fuel assemblies with different designs and evaluate the reflooding time of VVER and PWR.
- Published
- 2014
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