[en] The book incorporates the papers about scientific researches carried out at the Almaty branch of the Institute of Atomic Energy of National Nuclear Centre of Republic of Kazakstan on substation of re-start of the WWR-K research reactor that was reformed in 1998, after 10 years of short-down. Collection consists of Introduction and 12 papers

[en] Position of the WWR-K reactor site within regional geological structures is specified, internal structure of geological block is study as well as evolution of seismic safety on nuclear reactor site is given. In result of observations over long period (15,5 years) low seismic conditions on area with radius 25 km around reactor is pointed. It is made conclusion, that reactor is situated on pillar, where significant active breaks are absent

[en] Seismic stability for monolithic part of the WWR-K reactor constructive design is estimated under action of calculation earthquake with intensity of 10 balls. Maximum value for horizontal component of ground acceleration is accepted equal to 0,8 g. It is shown, that in all considerate constructions elastic work of concrete from compressed zone and armature have being projecting in spite to reduce of factual strength of concrete in comparison with project one. Possible local damages, in form microcracks, within concrete's stretched zone under calculation seismic action do not offer essential influence on carrier capacity, stability, tightness of constructive design

[en] According of factual characteristics a strength and deformation of over-land part of carrier constructions under construction movement is defined. Direct dynamical calculation of design elements under action of inertial loads from supports shifts shows, that seismic stability of enclosing construction is not ensured. Possibly practically total collapse of coating construction is possibly, under which following levels of damages of internal design constructions of reactor central room have been forecasted: 1. Fall of destroyed design construction on reactor vessel in time moment (1.56-1.59 s) after coming to building of earthquake seismic waves of 10 balls. 2. It is possibly cracks formation in radial direction in lower part of reactor cap, but destroying of cap does not incident; 3. It is possibly cracks formation within stretched concrete zone of reactor construction at the mark from - 0.859 up to 0.100. Destroy of concrete's compressive zone of reactor construction have not being expected. 4. Collapse of reactor first contour coating constructions have not being expected

[en] Principal results of physical start-up of the WWR-K reactor (after long stop) are sited. Main aims and tasks of physical start-up are stated. Methodic supplying of tests is described. Comparison of physical testing results with expected ones got on critical stand under simulation of reactor core is carried out. Under reactor core loading by 28 five-pipe and 6 tree-pipe fuel assemblies the reactivity reserve amounted 1.62% (ΔK/K), regulating devices of system of protection control efficiency - 4.56 % (ΔK/K), emergency protection devices efficiency 1,42 % (ΔK/K). Testing results of neutron-physical parameters of reactor core and calibration results of measuring channels of protection control system in absolute power values are sited

[en] Values of power release of spent nuclear fuel of WWR-K reactor are determined. This value is fixed equal to 2.48 W for fuel assemblies (FA) with maximum burnup of 40 % and duration of cooling in wet store of 10 years. Methodic of layers consistent removal from high-reactive spent FA with help of which is probed a depth of bedding fission products in fuel shell is carried out. On distant of 190 μm from surface to deep into of fuel element shell the traces of products fission have been revealed. Evolution time of fission products diffusion yield from fuel element shell outside showed that yield of fission products practically does not exerted influence of radiation safety of dry depository

[en] Analysis of initial compact loading of the WWR-K reactor is carried out. It is defined, that reactor reactivity supply should not exceed of 5,24 % (ΔK/K) under calculated efficiencies values of reactor control and protection control systems units in operation cycle start. Value of reactivity supply one should be corrected with taking into account real values of protection control system units efficiencies. Values of normal operation limits are defined by reactor power level in dependence of water expense in first contour and water temperature on entrance of reactor core. Values of reactor operation limits norms are chosen by reactor power (precautionary signalling (PS) setting). The PS setting of reactor core for thermo-hydraulic parameters monitoring is chosen as well

[en] System of reliable power supply of the WWR-K reactor complex is described, which completely provides safety operation of reactor equipment in the case of total voltage loss from external power transmission lines as well as under destruction of accumulation batteries by earthquake more than 6 balls. Switching on in operation of diesel-generators and system of constant current supply from accumulator batteries is occurred automatically under cessation of voltage supply from centralized power system. Reliable reactor dampening in case it work on capacity has been ensured. Reactor cooling under its emergency shutdown during both the partial or the total loss of coolant in first counter has been carried out. Under full coolant loss the system of emergency reactor cooling has been switched on in operation

[en] Description of RCP (system of reactor safety relating to 1 category of seismic stability) is sited. It is intended for to bring safety system in action and to control reactor conditions out limits of reactor building. The RCP carries out a control for rods position of reactor emergency protection by independent connection channels, for availability of chain reaction within reactor core, for water level and temperature in reactor vessel, for radiation situation in reactor room, for voltage availability in emergency power supply system. It is situated in separate building, carried away on 50 m from reactor building room, and it is located in incoming mine of ventilation system. Mine design constructions permits to preserve its integrity under earthquake of 9 balls by Msk-64 scale. The RCP system functioning in normal regime is described as well as devices failure in cases of both the normal regime and the reactor accident related with earthquake and other natural calamities

[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