[en] Method for determining stressed-strained state of fuel cans and hexagonal fuel assembly shroud under their simultaneous deformation in a fast reactor core is presented. Mathematical formulation of thee-dimensional problem of determining equilibrium fuel element configuration in a fuel assembly is given. The solution of the problem is inportant both for strength and thermal-hydraulic analysis. Descriptions of algorithms, computing program complex and results of test calculations are presented. The developed technique and program complex enable to determine fuel element displacement inside fuel assembly and contact forces among adjoining fuel elements, corresponding to equilibrium, configuration of fuel element cluster in hexagonal fuel assembly shroud; geometric characteristics of equilibrium configuration of fuel element cluster (squares of flow sections for the coolant), necessary for thermal-hydraulic calculation of fuel assembly; stressed-strained state of fuel assembly elements (fuel cans spacing wire, shroud) under simultaneous deformation of the shroud and fuel element cluster

[en] Methods for calculating deformations and interaction forces of heat-generating assemblies (HGA) of fast reactor core with account for the effect of control and protection system (CPS) elements at the reactor operation and change of interaction efforts between HGA at the reactor shutdown, are described. The results of testing the suggested methods on example of estimate of HGA behaviour of the BN-350 reactor are presented. For estimating the effect of CPS elements on HGA bending the sector model has been used. It is assumed that HGA deformation inside each sector is independent of HGA deformation of other sectors. A higher calculation accuracy is attained by means of laying out of sectors into regions of preferable influence of emergency protection elements and compensating packets. When determining deformation and interaction efforts between HGA caused by temperature change in the course of shutdown it is supposed that the HGA deformation is purely elastic. The methods described are realized in the form of ABRI-CPS and ABRI-HOL programs written in FORTRAN for the BESM-6 computer. The results of HGA calculations of the BN-350 reactor core show that CPS elements decrease contact efforts in the middle of the central packet, increase contact efforts in the peak of the central packet, increase contact efforts in the peaks of packets from the eight row to the periphery and increase contact efforts in the middles of packets from the 5th to 9th row

[en] Deformations of hexagonal tubes of fuel assemblies (steel 08 Cr16Ni11MZT) and pin claddings (steel 0 Cr16Ni15MZB) from the BN-600 reactor are examined after irradiation at a maximal dose of about 70 DPA. Effects of radiation dose at 430-450⁰C on swelling, temperature dependence of creep, fuel can diameters are determined

[en] An approach to assessment of fast reactor fuel assembly performance has been considered. A concept of passive restraint of fuel assemblies in a reactor adopted in the USSR is described. Some methods for calculating the interassembly interactions during operation are briefly outlined, some calculated results are presented. A problem of fuel assembly performance during refuelling taking into account the refuelling line capabilities is considered. Some results from fuel assemblies operation experience in the BN-600 reactor are given. (author)

[en] The paper presents results of the analysis of data on the deformation of the BN-600 reactor irradiated fuel subassemblies hexagonal ducts which are made of austenitic cold-worked and ferritic-martensitic steels, and of data on the deformation of fuel pin cladding which is made of austenitic cold-worked steels. Some results of subassemblies withdrawal force measurements are also presented. (author)

[en] Description of solid sanitary and technogenic waste reprocessing technology; heat diagram of heat recovery of waste reprocessing process; description of facility operation fundamental modes; requirements to basic systems and materials of facility of technogenic and sanitary industrial waste high-temperature reprocessing; standard-technical documents according to which facility designing, building and operation is conducted are presented in the report. There have been demonstrated the capability for creation of facility of high-temperature sanitary and technogenic waste recovery. There have been selected structure materials with operation lifetime of not less than 10 years at the parameters obtained in the furnace. There have been shown that systems of heat-sink cooling with sodium coolant created in atomic energetic are applicable for heat recovery of melting furnace and outgoing gases in high-temperature sanitary and technogenic waste reprocessing facilities with bubbling flux bath