Effect of creep on thermal fracturing in oxide crusts. [LMFBR]
Conference
·
OSTI ID:6703925
The stability of a fuel crust, especially on a molten sublayer such as steel, has been the subject of several papers. If the fuel crust is found to be unstable, the effect on a core-disruption accident could be far reaching: fuel would freeze more quickly in the structure above and below the core causing a plug and limiting the amount of early fuel dispersal, and high heat transfer to uninsulated walls, along with entrainment of cool steel droplets, would cool the fuel pool and reduce the amount of boilup. In a single subassembly accident, ablation of the walls would increase, thus increasing the amount of radial damage and the possibility of accident propagation. Conversely, a stable fuel crust would in general delay wall ablation and enhance upward fuel dispersal. It was recently proposed by Ostensen that a fuel crust would crack from thermal stress alone through as much as 75% of its thickness. In that paper, the effect of creep was left for future study. It is the purpose of this work to investigate that effect. A fuel crust growing on a layer of molten steel was considered.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 6703925
- Report Number(s):
- SAND-78-0255C; CONF-780622-4
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effect of thermal stress on oxide crusts
Transient freezing of a flowing ceramic fuel in a steel channel. [LMFBR]
Plugging of intersubassembly gaps by downward flowing molten steel. [LMFBR]
Conference
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Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7279264
Transient freezing of a flowing ceramic fuel in a steel channel. [LMFBR]
Journal Article
·
Sun Oct 31 23:00:00 EST 1976
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:7108336
Plugging of intersubassembly gaps by downward flowing molten steel. [LMFBR]
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6925799
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CORIUM
CRACKS
CREEP
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICAL PROPERTIES
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
CORIUM
CRACKS
CREEP
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICAL PROPERTIES
MECHANICS
MELTDOWN
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES