Steam explosion analysis in support of the SRS reactor safety assessment [electronic resource]
This report describes the application of two steam explosion models in support of the Probabilistic Risk Assessment (PRA) for the Savannah River Reactors. Theoretical models are required to estimate steam explosion yields in terms of kinetic energy, pressure shock and steam generated by the event. T...
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Online Access |
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| Corporate Authors: | , |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Dept. of Defense ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
1992.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a Steam explosion analysis in support of the SRS reactor safety assessment |h [electronic resource] |
| 260 | |a Washington, D.C. : |b United States. Dept. of Defense ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 1992. | ||
| 300 | |a Pages: (57 p) : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 10/09/1992. | ||
| 500 | |a "wsrc-rp-92-720" | ||
| 500 | |a "DE93014750" | ||
| 500 | |a Smith, D.C.; Vonderfecht, B.E. | ||
| 520 | 3 | |a This report describes the application of two steam explosion models in support of the Probabilistic Risk Assessment (PRA) for the Savannah River Reactors. Theoretical models are required to estimate steam explosion yields in terms of kinetic energy, pressure shock and steam generated by the event. These quantities are used in the PRA to determine fission product barrier integrity in the reactor confinement following a hypothetical steam explosion. The basic preconditions for a steam explosion are that hot molten material come into contact with water, and that the material's temperature be high enough to both support film boiling at its surface, and remain molten until an explosion is initiated. In a number of PRA accident sequences, aluminum-uranium debris will be hot enough to participate in a steam explosion. The high pressure vapor produced, the shock waves, and the kinetic energy of material can all do destructive work on structures surrounding the explosion site. Fuel melting is possible during several postulated severe accident scenarios for the SRS reactors. In many cases, water will exist in the reactor primary system and/or on the confinement building floor. Steam explosions must be characterized by a few significant parameters that can be addressed in the PRA. These parameters are the quantity of steam produced, and the amount of mechanical work performed. The model must be both computationally efficient and realistic. The present work employs a bounding model based on the assumption of thermodynamic equilibrium within the explosion and a non-equilibrium model which accounts for irreversible processes to achieve more realistic results. | |
| 536 | |b AC09-89SR18035. | ||
| 650 | 7 | |a Safety. |2 local. | |
| 650 | 7 | |a Special Production Reactors. |2 local. | |
| 650 | 7 | |a Uranium. |2 local. | |
| 650 | 7 | |a Actinides. |2 local. | |
| 650 | 7 | |a Metals. |2 local. | |
| 650 | 7 | |a Explosions. |2 local. | |
| 650 | 7 | |a Reactors. |2 local. | |
| 650 | 7 | |a Reactor Safety. |2 local. | |
| 650 | 7 | |a Shock Waves. |2 local. | |
| 650 | 7 | |a Molten Metal-water Reactions. |2 local. | |
| 650 | 7 | |a Risk Assessment. |2 local. | |
| 650 | 7 | |a Probabilistic Estimation. |2 local. | |
| 650 | 7 | |a Production Reactors. |2 local. | |
| 650 | 7 | |a Energy Transfer. |2 local. | |
| 650 | 7 | |a Heat Transfer. |2 local. | |
| 650 | 7 | |a Fission Product Release. |2 local. | |
| 650 | 7 | |a Elements. |2 local. | |
| 650 | 7 | |a Accidents. |2 local. | |
| 650 | 7 | |a Steam. |2 local. | |
| 650 | 7 | |a Aluminium. |2 local. | |
| 650 | 7 | |a Confinement. |2 local. | |
| 650 | 7 | |a Reactor Accidents. |2 local. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |2 edbsc. | |
| 710 | 2 | |a Westinghouse Savannah River Company. |4 res. | |
| 710 | 1 | |a United States. |b Department of Defense. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Savannah River Site. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
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