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AbstractAbstract
[en] The first author’s name should read A. K. Valter.
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Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 123(6); p. 432

Country of publication
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INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The radionuclide 99Mo was produced and separated in the process of irradiating powdered mixtures of molybdenum compounds and buffer particles by 30 MeV protons. The separation is based on the Szilard–Chalmers effect wherein 99Mo recoil particles are fixed in inert buffer particles. Two types of targets were investigated by using mixtures: soluble molybdenum compound–insoluble buffer and insoluble molybdenum compound–soluble buffer. 99Mo yield equal to 20% with enrichment coefficient 18.3 was obtained by using a target consisting of a mixture of submicron 100MoO3 and Al2O3 particles; the 99Mo yield was equal to 20% and the enrichment coefficient 18.3. For a target with the composition 100MoS2 + KCl, making it possible to separate 99Mo recoil atoms directly into solution, the 99Mo yield was equal to 8.7% and the enrichment coefficient 30.7.
Primary Subject
Secondary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 124(4); p. 261-265

Country of publication
ALKALI METAL COMPOUNDS, ALUMINIUM COMPOUNDS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CHALCOGENIDES, CHLORIDES, CHLORINE COMPOUNDS, DAYS LIVING RADIOISOTOPES, DISPERSIONS, ENERGY RANGE, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, HALIDES, HALOGEN COMPOUNDS, HOMOGENEOUS MIXTURES, INTERMEDIATE MASS NUCLEI, ISOTOPES, MEV RANGE, MIXTURES, MOLYBDENUM ISOTOPES, NUCLEI, OXIDES, OXYGEN COMPOUNDS, POTASSIUM COMPOUNDS, POTASSIUM HALIDES, RADIOISOTOPES, REFRACTORY METAL COMPOUNDS, STABLE ISOTOPES, TRANSITION ELEMENT COMPOUNDS
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] The maximum graphite temperature upon increasing the reactor power in the No. 1 unit of the Leningradskaya NPP to 80% of the nominal value in November–December 2013 after the restoration of the service life characteristics of the graphite stack is presented. A comparative analysis is made of the temperature regime of the graphite stack at power equal to 80 and 100% of nominal value before and after restoration of the service life characteristics at nominal helium content in the gas mixture blown through the reactor space. A comparison is made of the maximum temperature of the graphite stack of the reactors in the No. 1 unit of the Leningradskaya NPP and No. 2 unit of the Kursk NPP upon startup and assimilation of the power after restoration of the service life characteristics. The effect of the restoration of the service life characteristics on the thermohydraulic regime of the fuel channels in the reactor is studied.
Primary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 123(5); p. 326-331

Country of publication
CARBON, ELEMENTS, ENRICHED URANIUM REACTORS, FLUID MECHANICS, GRAPHITE MODERATED REACTORS, HYDRAULICS, LIFETIME, LWGR TYPE REACTORS, MECHANICS, MINERALS, NONMETALS, NUCLEAR FACILITIES, POWER PLANTS, POWER REACTORS, REACTOR CHANNELS, REACTOR COMPONENTS, REACTORS, THERMAL POWER PLANTS, THERMAL REACTORS, WATER COOLED REACTORS
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AbstractAbstract
[en] Research building B at the Bochvar High-Technology Research Institute for Inorganic Materials (VNIINM) located within the city limits of a dense residential development was decommissioned in 2013–2015. Radioactively contaminated equipment and utility services were disassembled and removed, building structures were decontaminated, the framework was dismantled, the grounds of the development site were restored, and radioactive waste was transferred to specialized organizations. The framework was liquidated in strict accord with the norms and regulations governing the use of atomic energy.
Primary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 123(4); p. 254-260

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] An approach to the comparative assessment of the impact of accidental radioactive emissions on the biota and radioecological validation of nuclear fuel cycle objects is presented. It is shown that the dose loads on woody tier in a coniferous forest as a result of severe accidents in NPPs with PWR-890, BWR-1412, and EPR-1600 significantly exceed the limit recommended by the ICRP. The impact of the radiation factor can result in serious disturbances in forest ecosystems in the immediate vicinity of NPPs.
Primary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 123(3); p. 202-208

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AbstractAbstract
[en] The main results of tests performed on VVER-1000 fuel elements with high burnup of fuel in a channel of the MIR channel reactor for LOC accident conditions are examined. The experimental setup contains one fuel element, which is arranged along the central axis. The aim of the tests is to determine the parameters of cladding depressurization. In the experiment, questions concerning fragmentation, axial displacement, and possible escape of fuel to outside the cladding were studied and the properties of the cladding material and fuel, which were subjected to the extreme parameters, were determined. The main parameters and the results of two experiments are presented. The conditions under which fuel-element depressurization occurred are determined.
Primary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 123(3); p. 159-166

Country of publication
ACCIDENTS, DEPOSITION, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, FUELS, MATERIALS, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SURFACE COATING, TANK TYPE REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] A linear-algebraic form of the equations of the method of characteristics, which is used to approximate the neutron transport equation, is obtained. It is shown on the basis of the obtained linear-algebraic form that the discrete form of the conjugate equation differs from the algebraically discrete problem constructed by linear-algebraic transformations of the discrete form of the normal problem. The reason for the discrepancy lies in the approximation of the volumes of the spatial cells in covering the working region by a network of characteristics. It is shown by means of test calculations that when the network of characteristics is refined the solution of the conjugate transport equation converges to the solution of the algebraically conjugate problem.
Primary Subject
Source
Copyright (c) 2017 Springer Science+Business Media, LLC; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 122(6); p. 369-376

Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] An economics-mathematical model for performing analytical calculations of the present value of separative work for uranium isotopes in a separation plant currently being designed using gas centrifuge technology is examined. Analytical expressions are obtained for the present value of the separative work, the internal rate of return, and the payback period of the separation plant as a function of its main engineering and economics parameters – productivity (capacity), capital investment, and operating expenses. Calculations of these criteria for investment efficiency are presented for a wide range of initial data. It is shown that the calculation of the present value of separative work must be performed in a complex with other investment efficiency criteria in order to determine their optimal combination.
Primary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 124(4); p. 279-286

Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] A problem in operating NPP with VVER is that waste solutions containing ethanolamine and ammonia from regeneration of ion-exchange filters from the second loop must be processed. The amount of ammonia in the regeneration solutions is equal to 85% of the total amount of the contaminating substances. The water chemistry regime of the second loop without ammonia or with ammonia replaced by dimethylamine is examined. It is shown that the use of dimethylamine makes it possible to increase the duration of the filtration cycle for ion-exchange filters of the purification systems, decrease the concentration of products of corrosion, reduce the environmental impact, and simplify the waste water purification technology.
Primary Subject
Secondary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 124(4); p. 255-260

Country of publication
CHEMICAL REACTIONS, CHEMISTRY, DIMENSIONLESS NUMBERS, ENRICHED URANIUM REACTORS, HYDRIDES, HYDROGEN COMPOUNDS, LIQUID WASTES, NITROGEN COMPOUNDS, NITROGEN HYDRIDES, NUCLEAR FACILITIES, OXYGEN COMPOUNDS, POWER PLANTS, POWER REACTORS, PWR TYPE REACTORS, REACTORS, SEPARATION PROCESSES, THERMAL POWER PLANTS, THERMAL REACTORS, WASTES, WATER, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] To ensure that technological installations using radionuclide sources of radiation operate at top efficiency, the effect of the irradiation system parameters on the radiation utilization factor was studied. It was found that the radiation utilization factor depends not on individual parameters of the irradiation system but rather on a certain combination of these parameters. A dimensionless criterion was determined on the basis of these investigations – a complex based on a set of parameters of installations with maximum radiation utilization factor. The radiation utilization factor was determined as a function of the irradiator–irradiated object distance. The numerical range of the criterion corresponding to the maximum radiation utilization factor is shown. Data by means of Monte Carlo calculations were selected by performing experimental studies using independent dosimetric systems.
Primary Subject
Source
Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature; http://www.springer-ny.com; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Atomic Energy (New York); ISSN 1063-4258;
; v. 124(3); p. 210-213

Country of publication
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