Fundamental approaches to reprocessing spent fuel particles of high temperature gas-cooled reactors

Abstract

The present paper considers the basic diagram of the main operations developed for reprocessing spent fuel particles of a high-temperature gas-cooled reactor. The developed diagram is appropriate for using PUREX hydrometallurgical reprocessing technology in subsequent operations. Main operations of the diagram maintain the integrity of fuel particles for the longest time to ensure the minimal contamination of structural graphite with nuclear materials and fission products. The results of experimental verification of the proposed reprocessing operations on model spent fuel of a high temperature gas-cooled reactor are presented.