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AbstractAbstract
[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
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Представлена рецензия на монографию Василенко И.Я. Токсикология ядерного деления (Москва, Медицина, 1999). В книге приводятся материалы многолетних натурных исследований во время ядерных испытаний на Семипалатинском полигоне. Описаны систематизированные, комплексные исследования воздействия смесей продуктов ядерного деления на разные виды лабораторных животных, сделаны научные обоснования по переносу результатов радиобиологических исследований на организм человека. Подвергается анализу наиболее сложная радиобиологическая проблема малой дозы. Рассматриваемая монография содержит уникальную научную информацию и вносит весомый вклад в радиобиологиюOriginal Title
Retsenziya na knigu: Vasilenko I.Ya. Toksikologiya produktov yadernogo deleniya
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[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
[ru]
Проведено численное исследование поля температуры согласно уравнению теплопроводности в широком дапазоне его параметров. Удовлетворительное согласие теории и эксперимента достигнуто только после включения в уравнение конвективного члена при скорости конвекции ν = 1.511 х 10-4 м/с и номинальном значении остальных параметров. Описанная задача решалась методом приведения к системе обыкновенных дифференциальных уравнений и ее интегрированием методом Рунге-Кутты-Мерсона четвертого-пятого порядковOriginal Title
Vybor modeli nagreva bol'shoj svintsovoj misheni protonami ehnergiej 5 GehV
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[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
Original Title
Vozmozhnyj vybros radioaktivnykh produktov deleniya pri zaproektnykh avariyakh na aehs s vvehr-1000
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6. international scientific and technical conference of national nuclear society. ICND 95; 6. mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya natsional'nogo yadernogo obshchestva. MKYaR 95; Kiev (Ukraine); 3-7 Jul 1995
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[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
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Skol'ko zhe yadernogo topliva nakhoditsya v lavoobraznoj toplivosoderzhashchej masse 4-go ehnergobloka chernobyl'skoj aehs?
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6. international scientific and technical conference of national nuclear society. ICND 95; 6. mezhdunarodnaya nauchno-tekhnicheskaya konferentsiya natsional'nogo yadernogo obshchestva. MKYaR 95; Kiev (Ukraine); 3-7 Jul 1995
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[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
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Opredelenie predel'nogo vybrosa pri tyazhelykh zaproektnykh avariyakh na AEhS
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4. Annual Scientific and Technical Conference of the Nuclear Society; YaEh-93. Yadernaya ehnergiya i bezopasnost' cheloveka; Nizhnij Novgorod (Russian Federation); 28 Jun - 2 Jul 1993
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[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
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Metodika analiza ehksperimental'nykh dannykh po utechke produktov deleniya
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[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
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Vtorichnoe zagryaznenie 30-km zony Chernobyl'skoj AEhS i prilegayushchej territorii za schet vetrovogo pod''ema radionuklidov
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[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
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Opytnaya yadernaya termoehlektricheskaya ustanovka 'GAMMA' -proobraz NS ATEhS
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DISTRICT HEATING, DUAL-PURPOSE POWER PLANTS, ELECTRIC CONDUCTIVITY, NUCLEAR POWER PLANTS, RADIOACTIVE EFFLUENTS, REACTOR COOLING SYSTEMS, REACTOR MONITORING SYSTEMS, REACTOR NOISE, REACTOR OPERATION, REACTOR SAFETY, THERMOELECTRIC GENERATORS, WATER CHEMISTRY, WATER COOLED REACTORS, WATER MODERATED REACTORS
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[en] Physical and thermophysical features are considered of a research reactor for group fuel element testing applied to high-temperature gas-cooled reactor improvement
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Osobennosti fiziki i teplofiziki reaktora IRGIT
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[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
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Ehksperimental'noe issledovanie otlozhenij radioaktivnogo ioda na metallicheskikh poverkhnostyakh kanala s geliem
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ALLOYS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON ADDITIONS, CHROMIUM ALLOYS, CLEANING, CONTAMINATION, DAYS LIVING RADIOISOTOPES, ELEMENTS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HIGH ALLOY STEELS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IODINE ISOTOPES, IRON ALLOYS, IRON BASE ALLOYS, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, NONMETALS, NUCLEI, ODD-EVEN NUCLEI, RADIOISOTOPES, RARE GASES, REACTORS, SECONDS LIVING RADIOISOTOPES, STAINLESS STEELS, STEELS
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