


Том 125, № 4 (2019)
- Жылы: 2019
- Мақалалар: 12
- URL: https://bakhtiniada.ru/1063-4258/issue/view/15552
Article
Determination of the Core Power of a Critical Assembly by Different Methods
Аннотация
Experimental and computational methods of determining the physical power of a critical assembly are proposed. The experimental conditions and results on determining the coefficient of proportionality of the indications of the SCS apparatus and the power of the critical stand are described. The results obtained by different methods are in agreement with one another to within about 20%.



Decommissioning Features of BN-350, -600 Fast Reactors
Аннотация
The general features and strategies of decommissioning BN-350 are presented. The features of sodium purification by 137Cs removal, coolant drainage from the reactor vessel, and transfer of sodium into a passive state are presented. The plans for decommissioning BN-350 are presented. The possibility of using the BN-350 sodium-handling technologies for BN-600 is examined.



Method of Solving Problems of Two-Phase Heat- and Hydrodynamics with Sodium Coolant
Аннотация
A consistent computational method of modeling complex shockwave processes in two-phase media in the presence of surface-tension forces that makes it possible to model boiling, evaporation, and condensation was developed. The results of modeling cavitation and Soda’s problem with sodium as well as modeling heat and mass transfer in a vertical channel in the presence of sodium boiling under forced lift are presented. Good agreement with experiment is shown.



Small Autonomous kW-Level Power Generation Based on Radioisotope and Renewable Energy Sources for the Arctic Zone and the Far East
Аннотация
In the near future, the demand for autonomous kW-level electric power generating plants in the Arctic zone and in the Far East will number in the tens and hundreds. In the present article, the operational characteristics of radioisotope thermoelectric generators with direct conversion of heat into electricity, which are being decommissioned, are analyzed. Schemes for autonomous electric power plants based on renewable sources of energy and electrochemical cells are proposed as alternatives. The problems arising in the development of such plants are analyzed. The results achieved in meeting concrete orders from operating organizations are discussed. It is concluded that autonomous electric power plants with renewable sources of energy and fuel cells hold promise.



Allowing for the Stochastic Nature of Corrosion Damage in Marine-Based Objects Including Submerged Radiation-Hazardous Objects
Аннотация
A mathematical model of corrosion damage to the protective barriers of radiation hazardous marine-based objects, taking account of the stochastic nature of this process, is constructed. The rate of pitting corrosion is determined by many mutually independent factors containing random components. This makes it possible to model pitting corrosion as a random walk process in which the corrosion rate changes discreetly and remains constant for one computational time step. The Monte Carlo method is used to calculate the depressurization time of an object with one protective barrier. The obtained estimates agree with expeditionary observations.



Tritium in Nitride Fuel of Fast Reactors
Аннотация
The formation of tritium in reactors, its behavior in nitride fuel and possibility of bonding with fission products, and the characteristics of migration out of the fuel-element cladding are examined. It is shown by a computational method that owing to diffusion through the steel cladding the stationary content of tritium in a fuel element is established over several hours of operation and most of the formed tritium escapes through the cladding, some being retained in it. The presence of hydrogen (tritium) in structural reactor materials in the course of operation of the reactor and thermal vibrations of the structure can significantly degrade the strength of steel structural materials. In this connection, in the BREST facility, the emphasis on the problem of catching tritium is shifted from reprocessing of spent nuclear fuel to handling the lead coolant and the gas medium in the interior of the reactor.



Preparation for Decommissioning the U-5 Facility Building Complex at VNIINM
Аннотация
A range of preparatory tasks for decommissioning the U-5 facility at VNIINM was performed in 2010–2016. Comprehensive engineering and radiation inspections were conducted, and cartograms of contamination were constructed. Deposits in the special utility systems were investigated. A detailed investigation of the contamination of the building structures was performed. Radioactively contaminated process media, sources of ionizing radiation, and radioactive wastes from technological equipment and rooms were removed. Design documentation for decommissioning the U-5 facility was developed and a positive final report by a government environmental commission of experts, final sanitary-epidemiological reports, and licensing for decommissioning were obtained. The measures made it possible to increase the radiation safety of the facility and prepare it for decommissioning.



Composite Binders for Solidification of Spent Ion-Exchange Resins
Аннотация
New cement compositions for solidifying mixtures of spent ion-exchange resins in sodium, nitrate, and tetraboric-acid form were developed. Depending on the composition of the cement and the ionic form of the anionite, the proposed cements make it possible to incorporate into the matrix 22–83 wt.% more ionexchange resins compared with using conventional portland cement. The matrices with heightened content of ion-exchange resins meet the requirements of cemented radioactive waste in terms of strength, water resistance, and leaching of 137Cs.



Combined Filter for Purifying a Radioactive Steam-Gas Mixture
Аннотация
The design of a new fireproof combined filter for purifying a radioactive steam-gas mixture by removing volatile compounds of radioactive iodine during normal operation of NPP as well as during accidental depressurization of fuel rods is described. The filter consists of identical cylindrical sections, each of which possesses a top lid for anchoring spiral filtering elements with variable surface area and a bottom lid with a grid for anchoring sorbents. The first and closing sections along the course of the purified gas flow are filled with sorbent consisting of the inorganic material SiO2–Cu0 or KSKG brand silica gel or a mixture of the two. A granulated sorbent based on SKT-3I brand activated charcoal or Fizkhimin inorganic granulated sorbent based on silica gel is used as a filler in each of the intermediate sections to catch volatile forms of radioactive iodine. The size of the pores in the spiral filtering elements with variable surface area decreases in a direction from the first to the closing section along the course of the purified gas flow; there are at least three sections equipped with sorbent for purifying gases by removing radioactive iodine-containing impurities.



Radiation Risk and Features of Its Perception
Аннотация
The public perception of radiation risk, which intensified after the accident at the Fukushima NPP (Japan), is examined. Now not only is it necessary to increase the safety of nuclear power but serious attention must be devoted to the public response to radiation risk. Analysis of sociological studies shows that the information factor plays a decisive role in the intensification of the perception of radiation risk via the creation of a negative social stereotype in respect to nuclear power as a whole. It is proposed that the communication approach to risk assessment and interpretation when informing the public be closely tied to a level-3 probabilistic safety analysis of objects using atomic energy.



Features of the Modernization of the Control Systems of Hoisting Cranes at NPP
Аннотация
A method of partial modernization of the control systems of special hoisting cranes operating at NPP that is cheaper, in terms of the cost of and time required for complete replacement than the alternative of complete replacement, and meets the regulatory requirements is proposed. The method consists in equipping the cranes with multi-functional autonomous devices, such as operational parameter monitoring systems, anti-collision systems, load control, locking control, and guidance in one or another combination depending on which required functions are not being currently realized. The indicated devices are compatible with one another and can be quite simply built into existing crane control systems irrespective of their type (relay-contactor, frequency-controlled). A description of the devices is given. The proposed autonomous devices (systems) can also be effectively used in designing new cranes.



Scientific and Technical Communications
Transformation of Human Voxel Phantom for Proper Calculations of Acute Irradiation


