[en] Investigations of fuel subassemblies of the reactors BN-600, BN-350, VVER-440, and VVER-1000 were carried out using nondestructive techniques. The main factors affecting the subassembly lifetime were determined

[en] The main aspects of radiation behavior of fuel elements on the basis of UPuO₂ vibropac fuel are studied in particular, fuel swelling, thermal-mechanical and physical-chemical interaction of fuel with the cladding in stationary and transient operating conditions and fission products behavior. It was shown that fuel elements with a composition based on vibropac, have no corrosion damage of the internal surface of the cladding and that the availability of peripheral area with initial granulate provides a decrease in thermal-mechanical stresses. (R.P.)

[en] Presented are the main results of the comprehensive investigations on the utilization of high background power-generating plutonium in Russia conducted at SSC RIAR facilities. The usage of new technologies based on the pyroelectrochemical methods of nuclear fuel reprocessing, vibropacking technology and automated remotely controlled processes was shown to provide efficient utilization of radiotoxic power-generating plutonium with a high radiation safety of the personnel and minimum ecological impact. (author)

No abstract available

[en] The main results on investigations of fast reactor fuel pins with (UPu)O₂ vibropac fuel to substantiate their serviceability up to the super-high burnups are presented. The BOR-60 reactor fuel pins radiation behaviour in stationary, transient and designed emergency conditions has been determined from the fuel pins dimensional stability analysis having regard to the results of investigation fuel and cladding swelling as well as estimations of fuel and cladding thermal-mechanical and physico-chemical interactions. It is shown that the change of the outer diameter is minimum in fuel pins with VMOX fuel with a getter-metallic uranium powder and ferrito-martensite steel cladding, and the corrosion damage of the cladding inner surface is absent up to 26% h.a. The experiments with over-heating of the irradiated fuel pins cladding up to 850 deg. C did not lead to any changes in pins integrity. The availability of the periphery area of the vibropac fuel cure initial structure provides the minimum level of the thermal-mechanical stress at transient conditions of reactor operation. (author)

No abstract available

[en] The RIAR installations capabilities for solving problems of nuclear power engineering development, safety ensuring, environmental acceptability, efficiency and effectiveness are described in the report. Examples of RIAR international collaboration and proposals on development of international collaboration on the basis of the research nuclear reactors are given