PWR Blowdown Heat Transfer Separate-Effects Program: Thermal-Hydraulic Test Facility Experimental Data Report for Test 158

Technical Report · Tue Oct 31 19:00:00 EST 1978

DOI:https://doi.org/10.2172/6786391· OSTI ID:6786391

Clemons, V. D. ^[1]; Hedrick, R. A. ^[1]; White, M. D. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 158, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 158 was conducted to obtain CHF information in the THTF bundle 1 operating at nominal power, containing four unpowered rods, having significant outlet subcooling, and utilizing a 30 to 70% break ratio.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USNRC
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6786391
• Report Number(s): NUREG/CR--0378; ORNL/NUREG/TM--249
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
SIMULATION
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS