Published 1986 | Version v1
Book

Coolability of collapsed core debris bed

  • 1. Osaka Univ., Suita (Japan). Faculty of Engineering

Description

For gaining basic information on the post accident heat removal, measurement of dryout heat flux was made, with water as coolant, in a 50 mm i.d. pyrex glass cylinder vessel. The fuel debris bed subjected to decay heat was simulated by steel balls or pellets which were induction-heated with a power supply of 20 kHz and 30 kW. Emphases were placed on the effects of system pressure, particle size, size mixing and coolant flow. Mixtures of cylindrical steel pellets and ceramic balls were also used to simulate TMI-2 type degraded core. The experiment covered the ranges over the system pressure of 0.02 - 0.5 MPa, the steel ball diameter of 0.3 - 4.0 mm and the pellets of 5.5 mm dia. x 9 mm, 8 mm dia. x 12 mm and 11 mm dia. x 11 mm with about 2 mm Al2O3 balls. The experimental results, as a whole, agreed fairly well with the prediction based on Lipinski's O-D model in the dependence of dryout heat flux both on pressure and on particle size. In detail, however, the dryout heat flux deviates toward a lower value at a higher pressure while to a higher value for a small size particle bed. Comparison of the results between the free and fixed beds suggests that the deviation to the higher side will be attributed to the channeling and/or levitation. For mixture, a number-weighted average diameter is available as the equivalent hydraulic diameter, which means that smaller particles of large number govern the dryout. The dryout heat flux increases with coolant mass flux, approaching to the complete vaporization of coolant, and greatly enhanced by a small amount of flow or circulation head. (author)

Additional details

Publishing Information

Publisher
Atomic Energy Soc. of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of second international topical meeting on nuclear power plant thermal hydraulics and operations
Imprint Pagination
1191 p.
Journal Page Range
p. 6/34-6/40.

Conference

Title
2. international topical meeting on nuclear power plant thermal hydraulics and operations.
Dates
15-17 Apr 1986.
Place
Tokyo (Japan).