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Fission product release and fuel behavior of irradiated light water reactor fuel under severe accident conditions

Allen, Harlan W. Stockman, K.O. Reil, J.W. Fisk

Abstract

The annular Core Research Reactor (ACRR) Source Term (ST) Experiment program was designed to obtain time-resolved data on the release of fission products from irradiated fuels under well-controlled light water reactor severe accident conditions. The ST-1 Experiment was the first of two experiments designed to investigate fission product release. ST-1 was conducted in a highly reducing environment at a system pressure of approximately 0.19 MPa, and at maximum fuel temperatures of about 2490 K. The data will be used for the development and validation of mechanistic fission product release computer codes such as VICTORIA.

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Key concepts: Nuclear fission product, Light-water reactor, Fuel element failure, Fission products, Nuclear engineering, Nuclear reactor core, Environmental science, Spent fuel pool