The importance of natural convection in in-vessel melt coolability [electronic resource].
- Washington, D.C. : United States. Dept. of Energy, 1992.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- Pages: (4 pages) : digital, PDF file
- Additional Creators:
- Argonne National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- In the event of a core meltdown accident, one of the accident progression paths is fuel relocation to the lower reactor plenum. In the Heavy Water New Production Reactor (NPR-HWR) design, the reactor cavity is flooded with water. In such a design, decay heat removal to the water in the reactor cavity and thence to the containment may be adequate to keep the reactor vessel temperature below failure limits. If this is the case, the accident progression can be arrested by retaining a coolable corium configuration in the lower reactor plenum. The strategy of reactor cavity flooding to prevent reactor vessel failure from molten corium relocation to the reactor vessel lower head has been discussed in this document.
- Report Numbers:
- E 1.99:anl/cp-75293
E 1.99: conf-920606--17
- Other Subject(s):
- Fluid Flow
- Production Reactors
- After-Heat Removal
- C Codes
- Heat Transfer
- Heavy Water Cooled Reactors
- Heavy Water Moderated Reactors
- Reactor Safety
- Computer Codes
- Energy Transfer
- Fluid Mechanics
- Hydrogen Compounds
- Oxygen Compounds
- Reactor Accidents
- Published through SciTech Connect.
American Nuclear Society annual meeting, Boston, MA (United States), 7-12 Jun 1992.
Cho, D.H.; Tan, M.J.; Tzanos, C.P.
- Funding Information:
View MARC record | catkey: 14367010