Critical heat flux experiments with a local hot patch in an internally heated annulus (LWBR development program)
Critical heat flux experiments were conducted for upflow of water in a vertical 84 inch annular flow channel, 0.303 inch heated I.D. and 0.500 inch unheated O.D. Test data were obtained at pressures from 1200 to 2000 psia, mass velocities from 0.25 x 10/sup 6/ to 2.8 x 10/sup 6/ lb/hr-ft/sup 2/ and inlet temperatures ranging from 200 to 600/sup 0/F. Three different test sections were employed with (1) axially uniform heat flux over the 84 inch length to serve as a no-hot-patch data base, (2) axially uniform heat flux over 82 inches with a 1.5 heat flux ratio hot patch over the last two inches, and (3) axially uniform heat flux over 82 inches with a 2.25 heat flux ratio hot patch over the last two inches.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA (USA)
- DOE Contract Number:
- EY-76-C-11-0014
- OSTI ID:
- 6449178
- Report Number(s):
- WAPD-TM-1419
- Country of Publication:
- United States
- Language:
- English
Similar Records
Critical heat flux tests with high pressure water in an internally heated annulus with alternating axial heat flux distribution
Critical heat flux experiments in an internally heated annulus with a non-uniform, alternate high and low axial heat flux distribution (AWBA Development Program)
Critical heat flux and pressure drop tests with vertical upflow of water in a 20-rod bundle of 0. 695-inch diameter rods. [LWBR]
Technical Report
·
Sat Sep 01 00:00:00 EDT 1979
·
OSTI ID:5765846
Critical heat flux experiments in an internally heated annulus with a non-uniform, alternate high and low axial heat flux distribution (AWBA Development Program)
Technical Report
·
Sat Jan 31 23:00:00 EST 1981
·
OSTI ID:6655346
Critical heat flux and pressure drop tests with vertical upflow of water in a 20-rod bundle of 0. 695-inch diameter rods. [LWBR]
Technical Report
·
Mon Jan 31 23:00:00 EST 1977
·
OSTI ID:7225235
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CONFIGURATION
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLOW RATE
FUEL CHANNELS
HEAT FLUX
HEAT TRANSFER
LWBR TYPE REACTORS
PRESSURE GRADIENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CONFIGURATION
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLOW RATE
FUEL CHANNELS
HEAT FLUX
HEAT TRANSFER
LWBR TYPE REACTORS
PRESSURE GRADIENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS