Steam-water mixing and system hydrodynamics program. Task 4. Quarterly progress report, April 1, 1977--June 30, 1977. [PWR]
Technical Report
·
OSTI ID:7212700
Experimental studies were conducted in a 2/15-scale model of a four-loop pressurized water reactor at pressures to 75 psia to extend the understanding of steam-water interaction phenomena and processes associated with a loss-of-coolant accident. The initial test series in this facility was completed which consisted of quasi-steady penetration tests. Additionally, plenum filling studies with and without hot walls and no cold leg steam were completed. Preliminary analyses of these data indicate that results obtained from both modes of testing, quasi-steady penetration with lower plenum draining and plenum filling, provide similar results which can be used to develop downcomer penetration correlations and to compare results from tests conducted in either operational mode. Comparisons of 1/15- and 2/15-scale data show that fluid behavior in both sizes is similar in that the observed effects on downcomer penetration of core steam flow, system pressure, ECC flow, and ECC water subcooling are common to both systems. The 1/15 and 2/15 data are compared using the j* or flooding parameters as the scaling basis. Although the comparisons appear to show good agreement, analyses indicate that a statistically significant difference exists in the data. This difference is being examined further. Two different forms are examined for correlating the combined sets of 2/15- and 1/15-scale data. Statistical tests were used to select the most appropriate form. Comparisons of data and correlational outputs are presented for both sized systems to illustrate the degree of data representation.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, Wash. (USA)
- OSTI ID:
- 7212700
- Report Number(s):
- BMI-NUREG-1979
- Country of Publication:
- United States
- Language:
- English
Similar Records
Steam--water mixing and system hydrodynamics program. Task 4. Quarterly progress report, January 1--March 31, 1978. [PWR]
Steam-Water Mixing and System Hydrodynamics Program Task 4: Quarterly Progress Report, October 1, 1977 - December 31, 1977
Steam--water mixing and system hydrodynamics program. Task 4. Quarterly progress report, July 1, 1977--Septmber 30, 1977. [PWR]
Technical Report
·
Mon May 01 00:00:00 EDT 1978
·
OSTI ID:6704000
Steam-Water Mixing and System Hydrodynamics Program Task 4: Quarterly Progress Report, October 1, 1977 - December 31, 1977
Technical Report
·
Tue Feb 28 23:00:00 EST 1978
·
OSTI ID:6649420
Steam--water mixing and system hydrodynamics program. Task 4. Quarterly progress report, July 1, 1977--Septmber 30, 1977. [PWR]
Technical Report
·
Mon Oct 31 23:00:00 EST 1977
·
OSTI ID:5241425
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Nonbreeding
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Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
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ENGINEERED SAFETY SYSTEMS
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PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SIMULATION
STEAM
STRUCTURAL MODELS
TESTING
TWO-PHASE FLOW
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
ECCS
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HYDRODYNAMICS
HYDROGEN COMPOUNDS
LOSS OF COOLANT
MECHANICS
MIXING
MOCKUP
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
SIMULATION
STEAM
STRUCTURAL MODELS
TESTING
TWO-PHASE FLOW
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS