Abstract:The integral behavior of zirconium cladding materials was tested under design basis and beyond design basis accident conditions in the CODEX (COre Degradation EXperiment) facility. The test series included five experiments and covered the typical loss-of-coolant accident conditions for normal reactor operation, shutdown conditions, and wet storage in the spent fuel pool. The electrically heated experimental bundles were composed of seven rods with a hexagonal arrangement. Traditional and sponge-based E110 clad… Show more
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