Thermal-hydraulic analyses of pressurized-thermal-shock-induced vessel ruptures. [PWR] [electronic resource].
- Los Alamos, N.M. : Los Alamos National Laboratory, 1982.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: 20 : digital, PDF file
- Additional Creators:
- Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- A severe overcooling transient was postulated to produce vessel wall temperatures below the nil-ductility transition temperature which in conjunction with system repressurization, led to vessel rupture at the core midplane. Such transients are referred to as pressurized-thermal-shock transients. A wide range of vessel rupture sizes were investigated to assess the emergency system's ability to cool the fuel rods. Ruptures greater than approximately 0.015 m/sup 2/ produced flows greater than those of the emergency system and resulted in core uncovery and subsequent core damage.
- Report Numbers:
- E 1.99:la-ur-82-1718
E 1.99: conf-830103-9
- Other Subject(s):
- Published through SciTech Connect.
2. international topical meeting on nuclear thermalhydraulics, Santa Barbara, CA, USA, 11 Jan 1982.
- Funding Information:
View MARC record | catkey: 14368528