Actions for Natural circulation under severe accident conditions [electronic resource].
Natural circulation under severe accident conditions [electronic resource].
- Published
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (23 pages) : digital, PDF file
- Additional Creators
- U.S. Nuclear Regulatory Commission and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- Research is being conducted to better understand natural circulation phenomena in mixtures of steam and noncondensibles and its influence on the temperature of the vessel internals and the hot leg, pressurizer surge line, and steam generator tubes. The temperature of these structures is important because their failure prior to reactor vessel lower head failure could reduce the likelihood of containment failure as a result of direct containment heating. Computer code calculations (MELPROG, SCDAP/RELAP5/MOD3) predict high fluid temperatures in the upper plenum resulting from in-vessel natural circulation. Using a simple model for the guide tube phenomena, high upper plenum temperatures are shown to be consistent with the relatively low temperatures that were deduced metallurgically from leadscrews removed from the TMI-2 upper plenum. Evaluation of the capabilities of the RELAP5/MOD3 computer code to predict natural circulation behavior was also performed. The code was used to model the Westinghouse natural circulation experimental facility. Comparisons between code calculations and results from experiments show good agreement.
- Report Numbers
- E 1.99:egg-m-92498
E 1.99: conf-9210204--3
conf-9210204--3
egg-m-92498 - Subject(s)
- Other Subject(s)
- Reactor Cooling Systems
- Thermodynamics
- Three Mile Island-2 Reactor
- Thermal Analysis
- Heat Transfer
- Reactor Accidents
- Temperature Measurement
- Accidents
- Cooling Systems
- Energy Transfer
- Enriched Uranium Reactors
- Power Reactors
- Pwr Type Reactors
- Reactor Components
- Reactors
- Thermal Reactors
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
01/01/1992.
"egg-m-92498"
" conf-9210204--3"
"DE93005245"
Water reactor safety information meeting, Washington, DC (United States), 21-23 Oct 1992.
Hanson, D.J.; Tung, V.X.; Chmielewski, S.V.; Pafford, D.J.
EG and G Idaho, Inc., Idaho Falls, ID (United States) - Funding Information
- AC07-76ID01570
View MARC record | catkey: 14366990