Millisecond-Period Meltdown Experiments on Prompt - Burst Effects and Molten-Tin-Water Dropping Experiments
- 1. U.S. Nuclear Regulatory Commission - NRC, 9422 Hickory View Place Gathersberg, MD 20760 (United States)
- 2. Sandia Laboratories (United States)
- 3. University of California, Los Angeles (United States)
Description
The U.S. Nuclear Regulatory Commission has initiated a program of confirmatory research for the safety assessment of LMFBR plants. In the sodium-fuel interactions area, this research includes a series of real-time in-pile experiments on the pressure and work potential of prompt-burst excursions as well as laboratory dropping experiments with molten tin and water. The in-pile experiments are performed by Sandia Laboratories in the Annular Core Pulse Reactor (ACPR), which has a minimum period of 1.3 milliseconds. These single-pin experiments are performed in a piston-loaded, stagnant-sodium autoclave, that is conceptually similar to the one used in the S-11 TREAT test. Unlike the S-11 test, however, realistic radial temperature profiles are obtained in the fuel, the cladding, and the sodium by pre-pulsing the reactor about 1/2 second before the main pulse. A series of preparatory runs have been made with helium-filled capsules and at low energy with sodium-filled capsules. The first significant fuel-coolant interaction run is scheduled for late March 1976. This will be a double-pulsed run at 2700 j/gm UO2. A continuing series of experiments is planned with oxide and advanced fuels in both fresh and irradiated form. In molten-tin-water dropping experiments at UCLA, microsecond duration multi-flash photography has been used for event diagnostics. Transition or nucleate boiling was found to trigger energetic interactions or vapor explosions. Temperature stratification in the water was found to reduce the threshold tin temperature necessary to produce vapor explosions below that the predicted by the coolant homogeneous nucleation hypothesis. Interaction zone growth times of a few msec were measured
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41053139.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the third specialist meeting on sodium/fuel interaction in fast reactors
- Imprint Pagination
- 981 p.
- Journal Page Range
- p. 585-617
- Report number
- NEA-CSNI-R--1976-8
Conference
- Title
- 3. specialist meeting on sodium/fuel interaction in fast reactors
- Dates
- 22-26 Mar 1976
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41053139
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACPR REACTOR; AUTOCLAVES; CAPSULES; FUEL-COOLANT INTERACTIONS; HELIUM; LMFBR TYPE REACTORS; MELTDOWN; NUCLEATE BOILING; RISK ASSESSMENT; SANDIA LABORATORIES; SODIUM; TIN; URANIUM DIOXIDE; VAPOR EXPLOSIONS; WATER
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALKALI METALS; BOILING; BREEDER REACTORS; CHALCOGENIDES; CONTAINERS; ELEMENTS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPLOSIONS; FAST REACTORS; FBR TYPE REACTORS; FLUIDS; GASES; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; METALS; MIXED SPECTRUM REACTORS; NATIONAL ORGANIZATIONS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PULSED REACTORS; RARE GASES; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SANDIA NATIONAL LABORATORIES; SOLID HOMOGENEOUS REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs.
- Secondary number(s)
- PNC-N251--76-12