Pour stream breakup of molten IFR (Integral Fast Reactor) metal fuel in sodium
Conference
·
OSTI ID:5158815
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.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5158815
- Report Number(s):
- CONF-880506-9; ON: DE88010002
- Resource Relation:
- Conference: Safety of next generation power reactors, Seattle, WA, USA, 1 May 1988
- Country of Publication:
- United States
- Language:
- English
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BREEDER REACTORS
DATA
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MATERIALS
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NUCLEAR FUELS
NUMERICAL DATA
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PHYSICAL PROPERTIES
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