Recent results from the Sandia steam-explosion program
Description
The Sandia steam explosion program involves experiments at small and intermediate scale, and modelling and analysis, including estimates for the failure probability of the reactor pressure vessel and the containment building. Recent intermediate scale results show that molten corium A + R is as explosive as the molten simulant iron-alumina, with an average kinetic energy conversion ratio of approximately 2%. In addition, several iron-alumina tests produced rapidly sequential double steam explosions in which it appeared that the first explosion enhanced the coarse mixing process. Results at small scale indicate that the maximum pressure-volume product (the net work output) from the steam explosion of a single melt droplet increased four to five times for a ten-fold increase in ambient pressure. With the initial assumption that contact between molten core and coolant will produce a steam explosion, and futher assuming that such contact occurs in-vessel in the lower plenum, a Monte Carlo technique was used to calculate failure probabilities for a typical PWR
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE83001169.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- SAND--82-2269C
Conference
- Title
- 10. water reactor safety research information conference.
- Dates
- 12 - 15 Oct 1982.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14742123
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; CONTAINMENT BUILDINGS; CORIUM; EXPLOSIONS; FAILURES; FUEL-COOLANT INTERACTIONS; MELTDOWN; PRESSURE GRADIENTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; STEAM; STRESS ANALYSIS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-821037--10.