Effect of buoyancy on forced convection in a cusped duct
Creators
- 1. Florida International Univ., Miami, FL (United States). Dept. of Mechanical Engineering
Description
In the event of a loss of coolant accident in a pressurized water reactor, swelling of the fuel rod cladding will lead to reduction of the subchannel flow area and worsening of the core heat transfer in the region of the blockage. The four-cusped duct is an ideal geometry for the simulation of such a channel blockage. Understanding the characteristics of flow and heat transfer in the cusped duct is essential for better design of the emergency core cooling system. Thus, in this paper, combined natural and forced convection in a vertical cusped duct has been investigated in the region of both hydrodynamically and thermally fully developed flow. The thermal boundary condition imposed on the cusped duct is the axial uniform heat flux with peripheral uniform temperature. The results indicate that the fluid flow and heat transfer in the corner region of the cusped duct are improved because of the influence of natural convection. As the Rayleigh number increases, the friction factor and Nusselt number increase accordingly. It was also found that the critical Rayleigh number is 1200, at which flow reversal occurs in the buoyancy-assisted flow (heated upflow). The velocity, temperature, and local Nusselt number distribution are presented for range of Rayleigh numbers
Additional details
Publishing Information
- Journal Title
- Numerical Heat Transfer. Part A, Applications
- Journal Volume
- 25
- Journal Issue
- 6
- Journal Page Range
- p. 743-755.
- ISSN
- 1040-7782
- CODEN
- NHAAES
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25074180
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- CUSPED GEOMETRIES; ECCS; FORCED CONVECTION; NATURAL CONVECTION; PWR TYPE REACTORS
- Descriptors DEC
- CONVECTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT TRANSFER; MAGNETIC FIELD CONFIGURATIONS; OPEN CONFIGURATIONS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS