No abstract available

[en] The aim of this work is search of dosimetric methodic for the neutron capture therapy in the HEC-1 channel of the WWR-K reactor. In the work the thermal and fast neutrons measurements were carried out with application of the activation detectors. Determination of absorbed dose were conducted by the EPR methods. In the study the tissue-equivalent alanine pellet dosimeters (APD), APD with boron, as well as teeth enamel samples sensitive to gamma-radiation were used. Besides the capacity of gamma-radiation dose was measured with clinical dosimeters use. The calculation were carried out with help of the Monte-Carlo method within 3-D geometry. The results showing the perceptiveness of the EPR method for the local absorbed dose assessment in the different parts of the reactor channel, and in particular for the neutron capture therapy

[en] Neutron characteristics on the fast thermionic converting reactor with electrical power 400 to 500 kW and reflector-moderator are considered. In particular, the initial reactivity margin, comprising ∼ 5.44%Δ k/k; total efficiency of CPS control drums, 14.1%Δ k/k. The dependence of efficiency of control drums on its turning angle is found. The characteristics of power flux field in an active zone of a reactor are calculated. Consequences of two postulated emergencies - the reactor environment with an additional infinite reflector from water and, in addition to previous, the hit of the water in a canal of the coolant as a result of destruction of reactor case are considered. (author)

[en] The modern concept of safety for transportation Nuclear Power Facilities (NPF) does not allow hoping to create the safety system for such NPF basing only the passive principle in close future. Therefore, it is of create importance to determine the redundancy margins for such system as well as to define the optimal proportion between the active and passive facilities used in safety systems. The overlook of the modern complex safety conception the transportation NPF that provides nuclear and radiation types of Safety in potential accidents is presented. The conception is base on application of both active and passive type safety systems. The principle schemes of the facilities that ensure such for transportation NPS are given in the report. The specific difference between the ordinary (ground-based) and space-based transportation NPF has been marked

[en] It is known, that measurement of critical assemblies heat power is actual technical task. The calorimeter method is proposed, where in capacity of calorimeter has been used composition identical by its isotope content and nuclear density to fuel material assemblies of nuclear reactor. Irradiation channel not excited neutron spectra has being created on critical stand in which calorimeter measurements were conducted. The heat power is defined on results of detail power distribution within volume of reactor core by numerical integration. The uranium of 90% enriched by ²³⁵ U isotope dioxide fine disperse powders, depleted uranium oxides U₃ O₈, polyethylene band with thickness 0,1 mm and aluminium band of same thickness were used as samples. Polyethylene is chosen in capacity of water imitator. Checking of methodic reliability was worked out under the WWR-K reactor start-up and loading its core zone with fresh fuel

[en] Results of calculation studies on substation of usage of beryllium reflector in existing core of the WWR-K reactor are presented. Removal of 20 FAs from the core periphery and installation of 23 beryllium pieces is implied. Distribution of the generated power over the core fuel assemblies and the neutron flux density values in irradiation channels are calculated, as well as two 21-day cycles of reactor operation. Heat -hydraulic calculation for the hottest FA of the core is performed. Heat-engineering reliability of the core with beryllium reflector is shown to be assured. (author)

[en] Reactions of reactor regulating devices (RR) , reactor core and reserve control panel (RCP) on seismic action are studied. Under experiments conducting on maximum frequency 1.6 Hz channels of regulating devices kept its constructive integrity, deformation signs and wedging of rots hangers have not being observed. Possible reactor power drift cause by rots shifts is defined. Results of full scale experimenters by WWR-K RC breakdown on critical stand with use of standard reactor fuel assemblies are sited. It is shown, that RC breakdown up to angles 2 deg from symmetry axis corresponds to increase of equivalent water clearance up to 9 mm and practically does not influence on k_ef of critical assembly. Further increase of angel clearance conducting to monotonous fall of k_ef and bringing of reactor to safety status. RCP test on special vibration stand shows it reliable serviceability as well

[en] Results of study for validity of possibility conducting resource testing of high-enriched thermionic assemblies for space reactor on fast neutrons in the WWR type testing reactor core are given. Using of control system with absorption gas - He 3 allows achieve conditions maximum approximate to natural one by such parameters as absolute value and profile of energy isolations in fuel compositions, neutron field spectra etc. Experiments made up on critical testing stand. Brief description of experimental devices and using methods are given

No abstract available

[en] On a base of WK-50 type reactor a concept for creation of the frame boiling water reactor (BWR) with improved safety characteristics for small-power NPP has been introduced. The modified scheme of WKR-50 reactor characterised by improved technological parameters is proposed. Besides, in this reactor version steam separation at centrifugal separators is implied instead of gravitation separation. A liquid-metal system is proposed to be used for the elements of the control and compensation system. The Gutry alloy with melting temperature 45 deg C has been chosen as the absorbing material, providing it's convey into the gap between fuel assemblies. A floater type system is proposed as candidate for a role of the emergency protection system. The system provides the most effective reactivity suppression at the maximum rate for lower location of control rods. At the reactor a safeguard frame inserted into a water-flooded mine. Mine usage to insert the reactor creates an extra safety barrier. The materials have a conceptual character and could be serve as a base for subsequent developments