Analysis of the late phases of core melt progression
Conference
·
OSTI ID:5530286
- Sandia National Labs., Albuquerque, NM (USA)
During severe light water reactor accidents like Three-Mile Island (TMI-2), the reactor core can suffer considerable damage. Of interest here are melt progression, oxidation and gas phase natural convection in the reactor core after the fuel rods suffer a significant loss of geometry. This study describes a two-dimensional porous medium model that considers the motion of three fields: vapor, melt, and solid. A base case solution is described and the effects of oxidation, melt relocation, and Fe-Zr interactions are discussed. 16 refs., 7 figs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- Sponsoring Organization:
- NRC
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5530286
- Report Number(s):
- SAND-89-0044C; CONF-891004--1; ON: DE89006863
- Country of Publication:
- United States
- Language:
- English
Similar Records
Review of experimental results of light water reactor core melt progression
Analysis of the late core melt progression phase of severe reactor accidents using the MELPROG code
Analysis of the late core melt progression phase of severe reactor accidents using the MELPROG (MELt PROGression) code
Journal Article
·
Sun Sep 01 00:00:00 EDT 1991
· Nuclear Technology; (United States)
·
OSTI ID:5667149
Analysis of the late core melt progression phase of severe reactor accidents using the MELPROG code
Conference
·
Thu Dec 31 23:00:00 EST 1987
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5781115
Analysis of the late core melt progression phase of severe reactor accidents using the MELPROG (MELt PROGression) code
Conference
·
Wed Jun 01 00:00:00 EDT 1988
·
OSTI ID:6808698
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ENRICHED URANIUM REACTORS
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GASES
HEAT TRANSFER
HYDRAULICS
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M CODES
MATHEMATICAL MODELS
MECHANICS
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METALS
OXIDATION
OXIDES
OXYGEN COMPOUNDS
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REACTOR CORES
REACTOR SAFETY
REACTORS
S CODES
SAFETY
THERMAL REACTORS
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