[en] Review on monograph of Vasilenko, I.Ya. Toxicology of nuclear fission (Moscow, Medicine, 1999) is presented. Data of longevity full-scale investigations during nuclear explosions on the Semipalatinsk test site are given. Classified, complex investigations into the effect of nuclear fission products mixtures on different kinds of laboratory animals are described, transfer of radiobiological researches to organism of man is scientific valid. The most complicate radiobiological problem of low dose is analyzed. The being investigated monograph contains unique scientific information and makes a heavy contribution in radiobiology

[en] The numerical analysis of temperature field in accordance to thermal conductivity equation in wide interval of its parameter was carried out. Satisfactory accord between the theory and experiment was achieved only after the incorporation of convective member in the equation at the rate of convection ν = 1.511 x 10^-4 m/c and nominal value of the rest parameters. The described problem was attacked by solving a method of putting in the system of ordinary differential equations and its integration by Runge-Kutta-Merson method of fourth-fifth orders

[en] Calculation of fission products exhaust from NPP containment shell with WWER-1000 reactors was accomplished by the following suppositions: the exhaust of volatile fission products by fuel heating up to 1300 deg C and above in one and a half hour and by fuel melting in four and a half hour was accounted for. It was assumed thereby that the exhaust of volatile fission products from the core equaled 100%. The calculational exhaust of radionuclides from the containment shell into the atmosphere was conducted for the time periods of two hours, half a day, one day and ten days from the accident beginning under supposition of retaining its integrity during the whole period of the accident. It is concluded that radionuclide release into the atmosphere during the first days after the accident is linearly connected with the vapour-gaseous medium leakage from the containment shell; the preservation of its integrity is an important task for controlling the beyond-the-project accidents and improvement of its airtightness will make it possible to decrease essentially the level of the population irradiation in the near-the-plant locations. 7 refs

[en] Results on previous estimates of nuclear fuel quantity in the destroyed power unit of the Chernobyl NPP are analyzed. Additional investigations in 1992 of fuel lava-like mass accumulation in pool-bubbler rooms provided for determination of exact boundaries of accumulations places. Presence of concrete, metal and lava-like fuel-containing mass in steam-discharge tubes was verified through vibration-acoustic method. According to the investigation results the nuclear fuel quantity in the lava-like mass of the pool-bubbler rooms showed be considered as equal to 6.6 ± 0.9 t of uranium dioxide instead of 9.5 ± 3.7 t of uranium. 5 refs., 4 tabs

[en] Limiting reloease of radionuclide products into the atmosphere in the case of severe accidents exceeding the design basis ones at NPPs calculated on the bases of exceeding the necessity for population evacuation is presented

[en] Methods for processing results of experiments simulating fuel emergency overheating from the positions of one- and two-group (activation) models are presented. Comparison of models was carried out on the basis of experiments performed in Germany according to the Sascha program. Brief description of the above studies is given

[en] Statistical and semi-empirical models are presented for transport of a radioactive impurity from a surface source. Calculations are fulfilled of ¹³⁷Cs resuspension, its transport and precipitation from a contamination spot with the area of 130 x 180 km. Coincidence of calculational and empirical data are satisfactory with account for the fact that maximal values of resuspension intensity and dry precipitation rate are used. The measurements show that weak winds and overmoistened soils of the accident zone promote small intensity of radionuclide resuspension

[en] An experience in operation of the GAMMA nuclear thermoelectric plant designed for experimental substantiation of the principles of development of small nuclear plants with direct conversion of reactor thermal power for decentralized consumer supply with electric energy and heat is described. The plant general description is given. The problems of operation stability, early diagnostics of the state basing on parameter noise analysis, water chemistry realization are discussed. The high degree of nuclear safety and ecological purity of the plant is emphasized

[en] Physical and thermophysical features are considered of a research reactor for group fuel element testing applied to high-temperature gas-cooled reactor improvement

[en] Experiments are described with the aim of investigations iof radioactive iodine isotopes deposition and removal from metal surfaces of the HTGR first circuit by means of their heating. It noted that graphite dust on the channel surface worsens iodine removal