Possible ways for protecting fuel claddings from corrosion on the side of the heat-transfer lead sublayer

Analysis of corrosion processes in fuel element claddings under the action of neutron irradiation in the presence of the heat-transfer lead sublayer is performed. Threshold values of oxygen content in the lead are computed. The corrosion behavior of steel components is considered for an operating reactor. Results of tests of cladding material at 700°C under various conditions (in the presence and absence of UN fuel, in pure lead, and in lead alloyed with steel components, etc.) are presented. Methods for protecting the internal surface of fuel claddings from corrosion are suggested.