Actions for COMMIX-1A analysis of fluid and thermal mixing in a model cold leg and downcomer of a PWR [electronic resource].
COMMIX-1A analysis of fluid and thermal mixing in a model cold leg and downcomer of a PWR [electronic resource].
- Published
- Argonne, Ill. : Argonne National Laboratory, 1983.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 7 : digital, PDF file
- Additional Creators
- Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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.
- Report Numbers
- E 1.99:conf-830932-4
conf-830932-4 - Subject(s)
- Other Subject(s)
- Loss Of Coolant
- Heat Transfer
- Hydraulics
- Pressure Vessels
- Thermal Shock
- Pwr Type Reactors
- Computer Calculations
- Primary Coolant Circuits
- Reactor Safety
- Temperature Gradients
- Accidents
- Containers
- Cooling Systems
- Energy Systems
- Energy Transfer
- Fluid Mechanics
- Mechanics
- Reactor Accidents
- Reactor Components
- Reactor Cooling Systems
- Reactors
- Safety
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
01/01/1983.
"conf-830932-4"
"DE83014741"
International conference on numerical methods in nuclear engineering, Montreal, Canada, 6 Sep 1983.
Chen, B.C.J.; Sha, W.T.; Kim, J.H.; Miao, C.C.; Sun, B.K.H.; Cha, B.K. - Funding Information
- W-31-109-ENG-38
View MARC record | catkey: 14370146