Critical heat flux experiments with a local hot patch in an internally heated annulus (LWBR development program)
Description
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 106 to 2.8 x 106 lb/hr-ft2 and inlet temperatures ranging from 200 to 6000F. 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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
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Additional details
Publishing Information
- Imprint Pagination
- 47 p.
- Report number
- WAPD-TM--1419
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10473976
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CONFIGURATION; CRITICAL HEAT FLUX; FLOW RATE; FUEL CHANNELS; HEAT TRANSFER; LWBR TYPE REACTORS; PRESSURE GRADIENTS
- Descriptors DEC
- BREEDER REACTORS; ENERGY TRANSFER; HEAT FLUX; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS