Reactor Complex

RIAR Research Complex is the only in Russia and one of few of such complexes in the world that has a unique combination of research reactors and material testing laboratories to solve comprehensively the tasks of the reactor material science on justification of fuel for nuclear power plants. Methods and facilities for post-reactor examination available at RIAR allow an overall analysis of changes in fuel under operation.


Research Fast Reactor BOR-60

This is the first sodium-cooled fast reactor facility designed in 1969 to try out the fast reactor technology and to justify experimentally promising types of fuel rods, fuel and absorbing and structural materials. At present, it is used to test reactor materials in hard neutron spectrum (fast neutron flux density achieves 3,7·1015 sm-2·s-1) at different temperatures. Further…

High-Flux Research Reactor SM

The high-flux research reactor SM is designed for experimental irradiation of reactor materials samples under the set conditions and studying the mechanisms of changes in different materials under irradiation. It is also used to produce a wide range of radionuclides, including far transuranics, to perform research in the field of nuclear physics. The idea of achieving high thermal neutron flux density in a moderating trap located in the core centre with hard neutron spectrum was implemented for the first time in the SM design (thermal neutron flux density achieves 5·1015 sm-2·s-1, fast neutron flux density achieves 2·1015 sm-2·s-1). Further…

Loop-Type Research Reactor MIR

The loop-type research reactor MIR is designed mainly for testing fuel elements, fuel assemblies and other core components of different types of operating and promising nuclear power reactors. Tests and experiments simulate both standard (steady-state and transient) conditions and the majority of the design-basis accidents. Tests can be carried out in several (up to 10) channels at a time, the neutron flux density being 4-5 times different from the average one. Further…

Pool-Type Reactor RBT-6

The reactor is designed to perform long-term experiments under stable parameters that do not require rapid achievement of neutron fluence. The peculiar feature of this reactor is that it uses fuel assemblies spent in the SM reactor. High content of 235U in such fuel assemblies provides neutron flux density of 1013 – 1014 sm-2·s-1; low rate of the reactivity decrease during the operation is related to the presence of gradually burning 149Sm accumulated in the SM reactor. Further…

Pool-Type Reactors RBT-10

The pool-type reactors RBT-10 are designed for experiments on examination of changes in materials under irradiation, accumulation of radionuclides and silicon doping. Further…

Critical Assembly SM-3

The critical assembly is used for physical simulation of the SM reactor core. The critical assembly is a physical mock-up of the reactor and the dimensions and composition of the core and reflector correspond to those of the reactor. Further…

Critical Assembly MIR.M1

The critical assembly is used for physical simulation of the MIR reactor core. The critical assembly is a physical mock-up of the reactor and the dimensions and composition of the core and reflector correspond to those of the reactor. Further…