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Том 119, № 3 (2016)

Article

Investigation of Processes in Lead Coolant with Loss-of-Integrity of a Heat-Exchange Tube in a Brest-OD-300 Steam Generator

Abramov A., Kovalev E., Kolesnikov P., Mukhametov R., Naumenko M., Nikitin O., Petrov D., Stolbikov M., Yudov A., Afremov D., Lemekhov V., Tutukin A.

Аннотация

The results of an experimental investigation by means of pulse radiography of the outflow of a steam–water mixture below the level of lead melt are presented. The x-ray diffraction patterns of bubble and jet efflux of the steam–water mixture, x-ray photographs of the steam cavity appearing in the lead coolant under the action of a shock wave arising with the spontaneous collapse of the heat-exchange tube of the steam generator in the BREST-OD-300 reactor with stress concentrators are presented. A qualitative analysis of the experiments is given.

Atomic Energy. 2016;119(3):200-206
pages 200-206 views

Analysis of the Reasons for Damage in the Welded Assembly Joining the Hot Collector of First-Loop Coolant to the Du 1200 Tube of the Steam Generators in No. 5 Unit of the Novovoronezh NPP

Povarov V., Bakirov M.

Аннотация

The results of scientific research performed in search of the reasons for the high degree of damage in the welded joint connecting the hot coolant collector in the first loop to the Du 1200 connection piece of steam generators in the No. 5 unit of the Novovoronezh NPP with VVER-1000 (welded connection 111) are presented. The computational and experimental approach used to analyze the accumulation of actual operational damage in the metal in the zone of welded connection 111, adopted in the No. 5 unit of the Novovoronezh NPP, is described. The results of operating the continuous monitoring system for three fuel runs shed light on the high damage in the zone of the welded joint 111 owing to the influence of beyond design basis thermal power loads on the fillet of the annular pocket of the coolant manifold, where operational cracks start and grow. Measures to change the technical specifications for operating the blowdown system of the steam generators, which will make it possible to reduce the operational damage in the welded joint 111, have been developed and adopted in order to rule out beyond design basis actions.

Atomic Energy. 2016;119(3):153-162
pages 153-162 views

Preliminary Computational Analysis of Reactivity Effects Due to Heating of the Astra Critical Stand

Osipov A., Gol’tsev A., Nevinitsa V., Fomichenko P.

Аннотация

A computational model of the ASTRA critical stand with heating has been prepared for the purpose of studying the neutron-physical characteristics of modular reactors of the type GT-MGR. The reactivity input during heating and cooling of the stand is evaluated. It is shown that the behavior of the reactivity upon heating and cooling will be different because an electric heater is present at the center of the internal reflector and a layer of thermal insulation is present between the core and the outer reflector. A nonequilibrium contribution of different regions of the assembly in the integral temperature effect is found. It is suggested that this effect can be used in preparation for experiments performed on the critical stand.

Atomic Energy. 2016;119(3):163-168
pages 163-168 views

Analysis of Relations for Calculating Normal Heat Transfer to Supercritical Pressure Water Flow in Vertical Tubes

Deev V., Rachkov V., Kharitonov V., Churkin A.

Аннотация

The generalized relations for calculating the coefficient of normal heat transfer during forced motion of water at supercritical pressure in vertical tubes is analyzed. It is shown on the basis of a comparison with a large experimental database (more than 4000 experimental points from 20 domestic and foreign works) that the equation obtained by the present authors gives the best agreement between the computational and experimental results for regimes with normal heat transfer in water near the critical point.

Atomic Energy. 2016;119(3):169-176
pages 169-176 views

Stress–Strain Kinetics in Calculations of High-Temperature Strength and Longevity of Reactor Structures

Dragunov Y., Evropin S., Gadenin M., Makhutov N., Rebyakov Y., Chernyavskii A., Chernyavskii O.

Аннотация

The plastic properties of materials must be used more fully as working temperatures and temperature gradients increase. The results of tests performed on refractory chromium-nickel alloys with combined low-cycle strain with prescribed total amplitudes and strain increments per cycle are presented. The results are compared with those obtained with rigid, cyclic, sign-alternating, and monotonic strain. A method of constructing mathematical models of a material that take account of short- and long-time characteristics of a metal in combination with the possibility of their direct use in readily available packages implementing the finite-elements method is described.

Atomic Energy. 2016;119(3):177-189
pages 177-189 views

Investigation of Modified UO2 Fuel with Anomalously High Thermal Conductivity

Kurina I., Popov V., Rumyantsev V., Ryabyi V., Zakharova M., Gaiduchenko A., Kuz’min M., Kiknadze G., Kryukov F., Kuz’min S.

Аннотация

Pre- and post-reactor studies of the properties of modified uranium dioxide fuel fabricated by a modernized water technology, including cooling of ammonium polyuranate with large and nanosize particles obtained simultaneously followed by calcination, reduction, pressing, and sintering of pellets, were performed. The properties of such fuel are compared with those of fuel obtained by the standard water technology. It is found that the heat capacity and thermal conductivity of such fuel are 1.8–2 times higher than the reference values and that the fuel possesses high microstructural stability and capacity for retaining gaseous fission products during irradiation. This is due to special properties: the presence of nanodispersity in grains and metal clusters in which the uranium ions form U–U chemical bonds with one another.

Atomic Energy. 2016;119(3):190-199
pages 190-199 views

Calibration of Neutron-Multiplicity Detectors

Gorbunova A., Rogozhkin V.

Аннотация

A method of calibrating neutron-multiplicity detectors using standard samples, certified in terms of the effective mass of240Pu, is described. The proposed method has an advantage over calibration using252Cf samples certified in terms of the neutron flux – the systematic shift of the measurements that is associated with the approximate nature of the method is eliminated. The serviceability of the proposed method of calibration is confirmed experimentally. The accuracy of the measurements of the effective mass of240Pu by the neutron-multiplicity method is evaluated: the standard deviation is several tenths of a percent.

Atomic Energy. 2016;119(3):207-212
pages 207-212 views

Evaluation of the Effect of Radiation on the Biota Within the Regions of the Leningradskaya and Beloyarskaya NPPs

Karpenko E., Spiridonov S., Kurtmulaeva V., Sanzharova N., Panov A., Tsygvintsev P.

Аннотация

A comparative evaluation of the effect of ionizing radiation on the biota in the regions of the Leningradskaya and Beloyarskaya NPPs based on radioecological monitoring is made. The dose loads on the representative organisms of the biota are calculated. The indices of the radiation action on these organisms are evaluated taking account of the dose limits. The irradiation dose rate (10 μGy/h) on the components of the environment in the 30-km zone of the Beloyarskaya NPP is found to be slightly above the most stringent standard for the maximum dose rate.

Atomic Energy. 2016;119(3):213-217
pages 213-217 views

Articles

Subcriticality Monitoring System for the MBIR Reactor

Aleksandrov S., Koroleva T., Kryukov S., Lukasevich I., Postnikov V., Suvolokin D., Ozhegin I.

Аннотация

The MBIR multipurpose, sodium-cooled, fast reactor designed by NIKIET is supposed to be started up in 2019 on the grounds of NIIAR. The reactor will be used to study and test new types of nuclear fuel, coolant, and building materials. This article reviews the subcriticality monitoring system of the MBIR reactor facility. The purpose, composition, and mathematical software of the subcriticality monitoring system are described.

Atomic Energy. 2016;119(3):149-152
pages 149-152 views

Scientific and Technical Communications

Efficacy of Eutectic Modification of Liquid-Metal Coolants

Alekseev P., Shimkevich A.
Atomic Energy. 2016;119(3):218-219
pages 218-219 views

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