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
Creators
Description
Highlights: • Scaled test facility simulating the calandria vessel and calandria vault water of PHWR with simulated decay heat was built. • Experiments conducted with simulant material at about 1200 °C. • Experimental result shows that melt coolability and growth rate of crust thickness are affected by presence of decay heat. • No gap was observed between the crust and vessel on opening. • Result shows that vessel integrity is intact with presence of water inside water tank in both cases. - Abstract: The present study focuses on experimental investigation in a scaled facility of an Indian PHWR to investigate the coolability 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 1200 °C. 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 coolability 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.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.03.027Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.03.027;
- PII
- S0029-5493(16)30012-7;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 303
- Journal Page Range
- p. 75-87
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48005745
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- AFTER-HEAT; BORON SILICATES; BOROSILICATE GLASS; COMPARATIVE EVALUATIONS; DECAY; HEAT; HEAT FLUX; HEAT TRANSFER; INDIA; PHWR TYPE REACTORS; PONDS; REACTOR ACCIDENTS; SIMULATION; TANKS; TEMPERATURE DISTRIBUTION; TEMPERATURE RANGE 1000-4000 K; TEST FACILITIES; THICKNESS
- Descriptors DEC
- ACCIDENTS; ASIA; BORON COMPOUNDS; CONTAINERS; DEVELOPING COUNTRIES; DIMENSIONS; ENERGY; ENERGY TRANSFER; EVALUATION; GLASS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; OXYGEN COMPOUNDS; REACTORS; SILICATES; SILICON COMPOUNDS; SURFACE WATERS; TEMPERATURE RANGE
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.