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Molten fuel containment analysis for SLSF experiments. [LMFBR]

El-Genk, R.L. Moore

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Abstract

The Sodium Loop Safety Facility (SLSF) experiments are being conducted in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory to furnish information concerning the behavior of fast reactor fuel elements under a hypothesized loss-of-flow accident conditions. These experiments involve measurements and observations that will permit an assessment of the location and time of sodium void initiation, the nature of sodium expulsion and reentry, the time and nature of cladding failure and motion, the molten fuel motion, and the extent of flow plugging by molten fuel freezing at the axial extremities of the subassembly. Because such high energy experiments are being conducted in-pile within the ETR facility, extensive pretest analysis was required to ensure loop integrity. One aspect of this analysis, which is the subject of this paper, was the assessment of molten fuel relocation and refreezing on the wall of the SLSF.

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The Sodium Loop Safety Facility (SLSF) experiments are being conducted in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory to furnish information concerning the behavior of fast reactor fuel elements under a hypothesized loss-of-flow accident conditions. These experiments involve measurements and observations that will permit an assessment of the location and time of sodium void initiation, the nature of sodium expulsion and reentry, the time and nature of cladding failure and motion, the molten fuel motion, and the extent of flow plugging by molten fuel freezing at the axial extremities of the subassembly. Because such high energy experiments are being conducted in-pile within the ETR facility, extensive pretest analysis was required to ensure loop integrity. One aspect of this analysis, which is the subject of this paper, was the assessment of molten fuel relocation and refreezing on the wall of the SLSF.

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Available abstract

The Sodium Loop Safety Facility (SLSF) experiments are being conducted in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory to furnish information concerning the behavior of fast reactor fuel elements under a hypothesized loss-of-flow accident conditions. These experiments involve measurements and observations that will permit an assessment of the location and time of sodium void initiation, the nature of sodium expulsion and reentry, the time and nature of cladding failure and motion, the molten fuel motion, and the extent of flow plugging by molten fuel freezing at the axial extremities of the subassembly. Because such high energy experiments are being conducted in-pile within the ETR facility, extensive pretest analysis was required to ensure loop integrity. One aspect of this analysis, which is the subject of this paper, was the assessment of molten fuel relocation and refreezing on the wall of the SLSF.

Key concepts: Containment (computer programming), Nuclear engineering, Computer science, Engineering, Programming language

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