Some research and development of thorium fuel cycle

The results of experimental investigations into 232 U buildup and capabilities for production of 233 U with low concentration of the last are considered. It is shown that developments of the thorium-based fuel may be grounded on available and perspective technology. The results of experiments dealing with radiochemical processing of irradiated thorium are discussed. Different direction for thorium introduction into the reactors of different types are studied. The variant with utilization of mixed fuel consisting of plutonium, 233 U , thorium and 238 U in fast reactors has some specific features. Application of 233 U in space reactors may give favourable effect on their lifetime. The problems of nuclear data collections for thorium fuel cycle are considered, and the results of some integrated experiments are given