Fission gas release from irradiated fuels in contact with mixed reactor materials
Fission gas release (particularly Kr(85)) studies carried out for irradiated fuel samples of medium and high burnup have now been extended to releases in contact with reactor materials (304 L stainless steel, absorber rod alloy Ag-15In 5Cd and zircaloy 4 cladding material) under reducing atmospheres during slow heating ramps up to 1500 C. The samples will be examined by scanning electron microscopy and optical microscopy to see the interactions between the structural materials themselves and their interactions with the fuel. Comparison of these first results with the releases and micro structures of fuels heated without other reactor materials present will enable initial conclusions to be drawn concerning the effects of the metal-fuel interactions. This will provide insights into the fission gas release mechanisms under certain reactor accident conditions.
Bibliographic Reference: Paper presented: Workshop on Severe Accident Research (SARJ '93), Tokyo (JP), November 1-2, 1993
Availability: Available from (1) as Paper EN 37998 ORA
Record Number: 199410073 / Last updated on: 1994-11-28
Original language: en
Available languages: en