COMMIX-1A analysis of fluid and thermal mixing in a model cold leg and downcomer of a PWR
Conference
·
OSTI ID:5870431
The issue of thermal shock of a PWR pressure vessel has been under considerable attention recently. A number of experimental as well as analytical studies have been performed to investigate the effect of the thermal transient on the pressure vessel due to the high pressure injection (HPI) of the cold fluid into the cold leg. This process has been called Pressurized Thermal Shock (PTS). This paper is an analytical study of PTS by using COMMIX-1A. Experimental investigations were performed at CREARE and SAI. In the CREARE experiment, a 1/5 scale model was set up to simulate a cold leg and downcomer of a PWR. Tests with several different ratios of hot loop flow versus cold HPI flow were performed to study the effect of the flow ratio on the fluid and thermal mixing process in the system, especially in the downcomer region. Analytical investigations also proceeded in parallel with the experiments. Quite a few analytical investigations were performed with the COMMIX-1A code. However, in this version of COMMIX, the effect of the numerical diffusion was not addressed.
- Research Organization:
- Argonne National Lab., IL (USA); Electric Power Research Inst., Palo Alto, CA (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5870431
- Report Number(s):
- CONF-830932-4; ON: DE83014741
- Country of Publication:
- United States
- Language:
- English
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COMMIX-1A analysis of fluid and thermal mixing in a model cold leg and downcomer of a PWR
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Related Subjects
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210200 -- Power Reactors
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ACCIDENTS
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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
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FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS