Published 1988
| Version v1
Report
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Four stream breakup of molten IFR [Integral Fast Reactor] metal fuel in sodium
Description
Tests have been conducted in which the breakup behavior of kilogram quantities of molten uranium, uranium-zirconium alloy, and uranium-iron alloy pour streams in 600C sodium was studied. A sodium depth of less than 0.3 m was required for hydrodynamic breakup and freezing of 25-mm pour streams of uranium and uranium-zirconium alloy with up to 400C melt superheat. The breakup material was primarily in the form of filaments and sheets with a settled bed voidage on the order of 0.9. The uranium-iron alloy with 800C melt superheat exhibited similar behavior except a sodium depth somewhat greater than 0.3 m was required for breakup and freezing of the particles
Availability note (English)
Available from NTIS, PC A02;3 as DE88010002.Files
19093514.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- CONF-880506--9
Conference
- Title
- Safety of next generation power reactors.
- Dates
- 1-6 May 1988.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19093514
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- EXPERIMENTAL DATA; FREEZING; HEAT TRANSFER; HYDRAULICS; IFR REACTOR; IRON; LIQUID METAL FUELS; LMFBR TYPE REACTORS; MELTING; MELTING POINTS; PARTICLE SIZE; SODIUM; URANIUM; URANIUM ALLOYS; ZIRCONIUM
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDES; ALKALI METALS; ALLOYS; BREEDER REACTORS; DATA; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; INFORMATION; LIQUID FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NUCLEAR FUELS; NUMERICAL DATA; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SIZE; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENTS; TRANSITION TEMPERATURE; ZERO POWER REACTORS