Analysis of questions concerning the nonproliferation of fissile materials for low-and medium-capacity nuclear power systems

The principles used in the design of low- and medium-power nuclear power systems to decrease the proliferation risk for nuclear materials as well as the results of a comparative analysis of GT-MGR, KLT-40, ABV, and foreign-produced light-water PWRs from this standpoint are presented. The INPRO methodology and modified KAERI for examining the DUPIC fuel cycle are used for nonproliferation assessment. The results show that at the stage where fuel is used in a reactor the resistance to nonproliferation of nuclear materials for the facilities which are now being designed is close to that determined for PWR and is even higher for GT-MGR with low-enrichment uranium fuel. The principles used in designing low- and medium-power reactor systems for decreasing the proliferation risk for nuclear materials as well as the results of a comparative analysis of the characteristics of the reactor systems being designed are presented in this article from the standpoint of nonproliferation of fissile materials. The INPRO methodology [1] and the modified KAERI methodology [2] for examining the DUPIC (Direct Use of PWR Spent Fuel in CANDU) fuel cycle are used as the methodological basis for the nonproliferation assessment. Fuel Cycle of Low- and Medium-Power Reactors from the Standpoint of the Nonproliferation of Nuclear