BARC/PUB/2016/0360

 
 

Experimental investigation of heat transfer during severe accident of a Pressurized Heavy Water Reactor with simulated decay heat generation in molten pool inside calandria vessel

 
     
 
Author(s)

Prasad, S. V.; Nayak, A. K.
(RED)

Source

Nuclear Engineering and Design, 2016. Vol. 303: pp. 75-87

ABSTRACT

The present study focuses on experimental investigation in a scaled facility of an Indian PHWR to investigate the cool ability of molten corium with simulated decay heat in the simulated calandria vessel. Molten borosilicate glass was used as the simulant due to its comparable heat transfer characteristics similar to prototypic material. About 60 kg of the molten material was poured into the test section at about 1200C. Decay heat in the melt pool was simulated using four high watt heaters cartridges, each having 9.2 kW. The temperature distributions inside the molten pool, across the vessel wall thickness and vault water were measured. Experimental results obtained are compared with the results obtained previously for no decay heat case. The results indicated that presence of decay heat seriously affects the cool ability behaviour and formation of crust in the melt pool. The location and magnitude of maximum heat flux and surface temperature of the vessel also are affected in the presence of decay heat.

 
 
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