[en] Problems of underground disposal of high-level radioactive wastes and the basic ways of their resolution specified by the HWTS program developed by the US Department of Energy are discussed. Peculiarities of geological structure of the territories are considered, where storages for disposal of long-lived high-level radioactive wastes are supposed to be arranged as well as the underground storage facility design. Ways of practical use of some nuclides, which were earlier considered to be liable to disposal, are pointed out

[en] Investigations into application of small heating reactors are described. As expected, these investigations will result in construction of a 2 MWt prototype reactor, to heat large buildings, in 1984-1985. The slowpoke research reactor is considered as the construction base. Economical estimations of the prototype reactor show that the cost of thermal energy will be equal to 3.23 cent/kWt x h (in 1981 Canadian), investment 1040 thousand, every year fuel cost=146 thousand (import oil is 3.2, domestic oil-2.1, electricc power-29, natural gas-1.8 cent/kWt x h)

[en] Power reactors put in operation in 1981 are enlisted. The 17 reactors have a total generating capacity of approximately 15 MWe. The highest rates of nuclear engineering development are obserVed in France, where 7 poweu units at PWRS with total generating capacity of about 6.6 GWe commenced operation

[en] Considered are some operation peculiarities of UO₂ fuel elements with zirconium alloy cans under the conditions of variable power of NPP, and transition process effect on .fuel element stability. At 300-400 deg C zirconium alloy cans are subjected to cracking at tensile stress in the presense of corrosive fission products. The most probable reagents, causing corrosion cracking, are iodine and metallic cadmium. Corrosion cracking does not occur instantly, but after a certain soaking under tensile stress. That is why the danger of fuel can fracture at power increase is not determined only by mechanical interaction between the fuel and a can, but by the time of stress relaxation during operation on the stationary heat-generation level as well. Fuel core cracking is also an important factor in corrosion fracture of cans. It is shown that usual fuel element structures, developed for reference NPP regimes, will have decreased margins of safety under the conditions of variable regimes

[en] Characterized are the changes and given are the main technical and economical indexes for uranium mining and metallurgical industry. The data on uranium resources evaluation for a number of countries, as well as the data on the volume and costs of exploration and prospecting procedures are given. The exploitation methods for uranium ores and investment are characterized. The present status of hydrometallurgical concentration of uranium raw material is discussed. The data on the number of personnel and on the enterprises of the mining and metallurgical industry are given. The problems of radioactive-waste processing and disposal of hydrometallurgical uranium raw material processing are considered

[en] Production of negative ion beams for electrostatic accelerators is described. Considered are three methods of beam production: direct ion extraction, charge exchange, spattering by cesium ion beam. Described is an ion charge exchange chamber using alkaline metal vapours as well as given are the test results on an experimental stand with Na, Mg and K targets and experimental results obtained on the electrostatic accelerator. Also presented are the results of negative ion yield under the action of ammonia stream on aluminium. AlH₂^- ions with current up to 1.8 μA have been produced. Given are the data on ion yield from a pulverizing source with a reflected beam. Perspectivity of application of pulverizing sources in acceleration of ions of rare and radioactive iosotopes is shown. Experimental results on tritium ion acceleration in the electrostatic accelerator are presented. During acceleration used was charge exhange by means of carbon foil. Voltage of high-voltage electrode amounted to 6 and 8.5 MV. Triton current amounted to 0.25-1 μA

[en] A review of preliminary quantitative estimates of radiation hazard of thermonuclear reactors is presented. Main attention is given to three aspects: nonradiation effect on environment, radionuclide blow-ups at normal operation and emergency situations with their consequences. The given data testify to great radiological advantages of thermonuclear energetics as compared with the modern nuclear energetics with thermal and prospective fast reactors

[en] The principles of development of systems for electric power supply of in ectors in power thermonuclear devices are considered in the review by way of example with reference to thermonuclear installations operating, being constructed and designed abroad. For the most part, the review was prepared based on the data of symposia and conferences on engineering problems of thermonuclear investigations carried out in 1975-1978. High-voltage and low-voltage parts of the system for electric power supply of an ion source are described. Flowsheets of electric power supply for emission electrodes in the test facilities in Berkeley and Oak-Ridge, devices with use of higher frequences of supply voltage are presented. It is shown that diversity in circuits of high-voltage devices for electric power supply with identical parameters and purposes, leads to their necessary optimization

[en] A dependence of the counting rate c of CdTe semiconductor detectors on γ-radiation dose rate D has been studied. A ¹³⁷Cs source of 1.5 Ci (the γ-radiation energy of 0.67 MeV) was used, D being varied from 0.1 to 80 rad/hr. C has occurred to decrease with increasing D, the dependence substantially differing from linear one. It was found, that for the detectors possessing polarizing effects C decreases with time at large D (80 rad/hr), the time constant being equal to about 10² s. On decreasing D the depolarization is observed, i.e. C recovers to its initial value. The most probable explanation of the results is put forward as a decrease of the sensitive volume of the detectors due to thinning of the depleted layer

[en] The purpose of the paper is to make an attempt to answer the question, which of nuclear energy sources is it necessary to develope for long term necessities: thermonuclear breeder reactor (TBR), breader reactor on fast neutrons (FBR) or both. In the light of modern presentations TBR will be more safe and acceptable from social positions and from environmental preservation point of view as compared to FBR. In the problem of fuel sources, preference will be given to fusion, but fuel reserves and resources for both energy systems are so ''unexhaustible'' for the present generation, that there is no use to give preference to either of them. As for cost of electric energy, it will be scarcely cheaper in TBR. FBR is technologically simpler than TBR and it can be built earlier. At present it is reasonable to develope nuclear enginearing based on FBR as fast as possible. It will permit to prolong the present uranium sources for several centuries in case TBR would not be developed for some reasons. It is necessary to discuss constantly and compare these two main energy sources in order to plan well-foundedly and responsibly the stable and wholesome international energetic climate, in which future generations could succeed