Thermal mixing tests in a semiannular downcomer with interacting flows from cold legs: International Agreement Report
This report describes the test facility and test program for studying thermal mixing of high-pressure injection (HPI) water in the two-fifths scale model of three cold legs, semiannular downcomer and lower plenum of a pressurized water reactor. This test series has been carried out by mutual agreement on the pressurized thermal shock (PTS) information exchange between the US Nuclear Regulation Commission and Imatran Voima Oy. The test facility was originally designed to model the Finnish Loviisa plant but it was redesigned and modified for this test program. The facility can be operated at atmospheric pressure with loop and HPI flows from different cold legs in the area of interest to PTS. Transparent materials were used to allow flow visualization during the tests. The choice of transparent materials limit the upper temperature to 75/sup 0/C. The full buoyancy effect was induced by salt addition and the HPI temperature was used as a tracer. The test matrix consists of 20 tests. The varied parameters were flow rates and the number and configuration of cold legs with HPI and loop flows. Four tests were done with decreasing loop flow temperature to simulate primary flows during steam line breaks.
- Research Organization:
- Imatran Voima Oy, Helsinki (Finland); US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research
- OSTI ID:
- 7089518
- Report Number(s):
- NUREG/IA-0004; ON: TI87900527
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HIGH PRESSURE COOLANT INJECTION
FLOW VISUALIZATION
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
HEAT TRANSFER
HYDRAULICS
EXPERIMENTAL DATA
MIXING
REACTOR ACCIDENTS
RESEARCH PROGRAMS
TEST FACILITIES
THERMAL SHOCK
ACCIDENTS
COOLING SYSTEMS
DATA
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled