Thermal- and ignition-type steam explosions of single drops of molten aluminum
Creators
- 1. Sandia National Lab., Albuquerque, NM (United States)
Description
The contact of aluminum-based melts with liquid water has been shown to be explosive in many experiments performed by the aluminum industry and in several nuclear reactor experiments and accidents including NRX, SL-1, and SPERT. To obtain quantitative information relating to the fuel/coolant interactions that might occur with aluminum-based fuel, a laboratory-scale experimental study is being performed at Sandia National Laboratories. The overall objective of this research program is to provide an understanding of the mechanism of steam explosions with the melt compositions expected in several hypothetical core meltdown accident scenarios in production reactors. In this program, it has been demonstrated that rapid exothermic metal-water reactions can accompany the steam explosions under certain conditions, resulting in enhanced energy release and in the concomitant generation of hydrogen
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Journal Page Range
- p. 378-379.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics.
- Dates
- 10-15 Nov 1991.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24016017
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; BUBBLES; EXPLOSIONS; IGNITION; MELTDOWN; MITIGATION; MOLTEN METAL-WATER REACTIONS; NRX REACTOR; PRODUCTION REACTORS; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; SANDIA LABORATORIES; SL-1 REACTOR; SPERT-1 REACTOR; SPERT-2 REACTOR; SPERT-3 REACTOR; SPERT-4 REACTOR; STEAM
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS TESTING REACTORS; METALS; NATIONAL ORGANIZATIONS; NATURAL URANIUM REACTORS; POOL TYPE REACTORS; POWER REACTORS; PROCESS HEAT REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SANDIA NATIONAL LABORATORIES; TANK TYPE REACTORS; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-911107--.