1986•University of North Texas Digital Library (University of North Texas)Open access

Recent metal fuel safety tests in TREAT

Arthur E. Wright, Theodore H. Bauer, R.K. Lo, William R. Robinson, R.G. Palm

Abstract

In-reactor safety tests have been performed on metal-alloy reactor fuel to study its response to transient-overpower conditions, in particular, the margin to cladding breach and the axial self-extrusion of fuel within intact cladding. Uranium-fissium EBR-II driver fuel elements of several burnups were tested, some to cladding breach and others to incipient breach. Transient fuel motions were monitored, and time and location of breach were measured. The test results and computations of fuel extrusion and cladding failure in metal-alloy fuel are described.

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Key concepts: Cladding (metalworking), Extrusion, Materials science, Nuclear engineering, Burnup, Fuel element failure, Nuclear fuel, Metallurgy