[en] For fast reactors cooling by sodium (BN-800) and by lead (BREST-300) has been investigated fast developing process proceeded under heavy accidents. Force of strong diversion explosion to reactor does not followed to runaway fast reactor and to energy isolation. Methodology of study and some results for IGRIK-type pulsed reactor and IGR reactors fuel elements behavior from uranium dioxide and uranium nitrates under heavy accidents, including case with fuel-melting and its interaction with liquid sodium and lead are presented

[en] In the work has been study the hematite monocrystals irradiated by neutrons, protons with energy 7 MeV and 30 MeV, alpha-particles with energy 29 MeV and 50 MeV. Low-voltage weak ferromagnetic phase is faint expressed under proton irradiation with energy 7 MeV. In monocrystals irradiated by alpha-particles it taken place fluently within broad temperature interval. Among samples irradiated by particles more abrupt character of transition have monocrystal irradiated by proton with energy 30 MeV. This phenomenon has been explained of growth of contributions of nuclear reactions to formation defects. It led to narrowing distributions of defects by its dimensions. Narrowest distributions of defects must be realized by fast neutrons because of absents coulomb interaction. In deed the narrowest transitions corresponds to this case. There is direct connection between width of low-temperature transition distributions of radiation defects dy dimensions, This connection confirms superparamagnetic mechanism of low-voltage weak ferromagnetic phase. 1 refs

[en] The some stages of working out and basic concepts of safety improvement of the native nuclear power plants are briefly given. On the first stage the correlation of the following results was generalized: - determination purpose parameters of safety; - classification of units of nuclear power plants by the levels their risk according the International nuclear event scale at NPP; - definition of the nuclear power plants concepts of acceptable, high, limit safety of units; - definition of possible strategic ways for safety increasing of the native nuclear power plants. The complex programme for problem of heavy accidents on NPP includes the ways completely or nearly completely use the 4-Th level reserve of protection. The system of correlate suppositions is one of approach to an analysis radio validity of the nuclear power plants safety. The

[en] The structure of saturated and non-saturated aluminium and copper solid solutions irradiated by neutron fluence was investigated. The samples irradiation had been conducted at the wet channel WWR-K reactor (E>0.1 MeV, T<80 deg C). The irradiation of saturated aluminium and copper solid solutions evokes the alloy separation into radiation-educed α-phase with FCC structure and lattice parameter 0.367 nm. The quantity of this phase is connected from the initial concentration, the neutron fluence and the rate of sample's limit deformation

[en] The results of the experiments on aluminium and copper samples for defining of correlation between on the one hand the of fluidity limit and electric conductivity on the other hand the width of electric fields gradients' distribution and the local variable fields intensification around different radiation defect structures. The macro-characteristics (fluidity limit, electrical conductivity, micro-hardness) has been defined by the traditional methods of the mechanical and electro-physic testing. The local fields' parameters was defined from spectrum of nuclear magnetic resonance. The analysis of received data indicates on existence of correlation between the fluidity limit and width of electrical fields gradients distribution, also between concentration and the time of nuclear spin dipole relaxation

[en] The stand complex Bajkal-1 was created in the end sixteenth and beginning of seventeenth at the territory of Semipalatinsk testing site and was intended to working out of experimental study of nuclear rocket engines of prototype-reactor with solid phase reactor core. During testing of reactor elements has being accumulated a considerable material on a radiation investigation and a radiation protection. In 1988 works by cosmic subject characterizing great exposure doses from working reactor and radionuclides yield to environment was stopped. But the perfect radiation monitoring system was saved. It was created in collaboration a specialists of former USSR and own personnel of the complex. The series of the organization and technical measures under exploitation of reactors allows achieved average irradiation dose of personnel equal up 0,3 Br per year. There is control of incorporated radionuclides in the human organism spectrometer. All personnel of the complex one time in year are inspecting on it. It necessary noted, that contents of Cs 137 isotope does not exceeded 0,01 from limit value. Now the first results of radon and it daughter products concentration in the air of working premises measuring are obtained. The working out of numerous of measuring allows choose optimal regime of the ventilation

[en] The neutron-physics control system of WWR-K research reactor core is described. The system consists of the two staff ionization chambers in water reflector, the thermal device and the additional radiation detectors. The staff devices fully provides necessary measuring accuracy of neuron flux under reactor working with electric power 1 MW and above. The additional detectors represents the rhodium detectors of direct charge placed in the experimental irradiation channels and the mobile feeler with thermal neutron detector are used for a neutron field of low power control and a its configuration defining by reactor core height. The using of additional detectors provides exacter to define the neutron flux parameters on experimental assemblies and to compose reactor core by such way that remove asynergy in its unevennesses. For measuring of neutron flux and additional detectors calibration was using the activation detectors. The neutron fluxes characteristics arising given

[en] Safe regime of NPP work with the using of subcritical reactor is discussed. Chain reaction of fission is reconstructed by the external powerful neutron flux, which is generated in the uranium or lead target by the proton beam with power up to several hundreds MeV. It is presented several technically proved schemes of linear accelerators on the power up to 1 GeV and the currents of proton beams up to 300 m A. It is proposed to lead the experimental control of new work regime on the active or build NPP. The expenses on modernization will not exceed 10 percents from NPP cost

[en] Short communication

[en] Results of studying of polycrystal aluminium's (99,99%) and copper's (99,95 and 99,99%) reactor creep are given. Reactor testing were carrying out in WWR-K reactor under temperature interval 473 - 693 K and by neutron flow density 1,4·10¹⁶ n/m²/c. On base of experimental data is established 3 fields: low, middle and high temperature with different deformation behaviour. Under low and high temperature velocity of creep linear increases. Comparison of reactor and non-reactor testing shows that irradiation influence is more marked in the field of low and it has great increasing of temperatures under irradiations. By middle temperature anomalous behaviour of reactor creep is observed and it independents from temperature for copper 99,95 %