On the History of the Development of Neutronics Codes for CTR Analysis at the Kurchatov Institute and the Validation of Neutron Data in Integral Experiments with 14-MeV Neutron Sources (Review)

Abstract

The period of 1972–2004 considered in the review coincided with the time of the most intensive engineering studies of domestic CTR concepts such as the OTR and DEMO reactor concepts. The unavailability of adequate tools for calculating the neutronics characteristics of models with a 14-MeV neutron source at that time necessitated the development of in-house methods, codes, and neutron data libraries for the study of the neutron and gamma-ray transport in the fusion reactor blanket and the shielding. This work has resulted in creation at the Kurchatov Institute of the branched BLANK code family capable, with computing facilities available, of effectively solving the problems of conceptual research, designing the blanket and shielding, and analyzing integral experiments with a 14-MeV neutron source. To validate the computer codes and neutron data, numerous integral experiments with pure materials, various blanket and shield mock-ups, and activation studies of candidate materials for the ITER were conducted in cooperation with colleagues from Russian and foreign institutions. The aim of the review is to provide a brief summary of the work carried out and systematization of publications in which more detailed information can be found.