RESULTS OF VERTICAL UPFLOW PRESSURE DROP TESTS WITH WATER AT 2000 PSIA FOR PARALLEL FLOW THROUGH HEATED ROD BUNDLES
Technical Report
·
OSTI ID:4299876
Pressure drop tests were conducted with vertical upflow of water at 2000 psia using a test section having nine heated rods of PWR core 1 reference blanket size and pitch (0.413 in. diam by 0.468 in. square pitch by 9 1/4 in. long). These tests confirmed the validity of using design procedures based on tests with rectangular channels for calculating pressure drop for parallel flow through heated bundles. (J.R.D.)
- Research Organization:
- Westinghouse Electric Corp. Atomic Power Div., Pittsburgh
- NSA Number:
- NSA-13-000340
- OSTI ID:
- 4299876
- Report Number(s):
- WAPD-TH-437
- Country of Publication:
- United States
- Language:
- English
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