Boris Arsentevich Gabaraev

N.A. Dollezhal Research and Development Institute of Power Engineering | NIKIET

This paper discusses the results of a review of computational and experimental studies on the transport coefficients and thermodynamic properties of helium-xenon gas mixtures. The most promising in the authors’ opinion is a combination of approaches pertaining to the kinetic Chapman-Enskog theory and the theory of corresponding states of dense gas....

Calculation and experimental investigations of the transport coefficients and thermodynamic properties of a helium-xenonmixture are reviewed. It seems that a combination of approaches of the Chapman-Enskog kinetic theory and the theory of corresponding states of dense gas is most promising. This combined approach results in semiempirical relationsh...

Analytical review of numerous Russian and foreign sources of information on convective heat transfer to single-phase flows in circular pipes and rod bundles is represented. Formulas for calculation of heat transfer in circular pipes and rod bundles for different flow regimes of a binary gas mixture are proposed.

With regard to the global-scale development of desalination technologies and the stable growth demand for them, Russia also takes an active part in the development of these technologies. Two major aspects play a special role here: they are providing the desalination process with power and introducing new materials capable of making the production o...

The world development scenarios predict at least a 2.5 time increase in the global consumption of primary energy in the first half of the twenty-first century. Much of this growth can be provided by the nuclear power which possesses important advantages over other energy technologies. However, the large deployment of nuclear sources may take place...

Within the framework of an European Commission sponsored activity, an overall assessment of the deterministic safety technology of the ‘post-Chernobyl modernized’ RBMK has been completed. The accident analysis, limited to the area of design basis accident, constituted the key subject for the study; therefore, the notorious Chernobyl unit 4 event wa...

The RBMK core is constituted by more than one-thousand pressurized channels housed into stacked graphite blocks and connected at the bottom and at the top by small diameter (D) and long length (L) pipes (less than 0.01 and more than 10 m, respectively) that end up into headers and drum separators. Control valves are installed in the bottom lines. D...

Within the framework of an European Commission sponsored activity, an assessment of the deterministic safety technology of the ‘post-Chernobyl modernized’ Reactor Bolshoy Moshchnosty Kipyashiy (RBMK) has been completed. The accident analysis, limited to the area of Design Basis Accident, constituted the key subject for the study; events not includi...

Safeguarding of nuclear technologies, facilities and materials against unauthorised application and proliferation is very much on the agenda at present. The attention given to this issue is due not only to the increasing threat of terrorism but to the nuclear power renaissance as well. Many countries have declared the national energy strategies tha...

Large-scale development of nuclear central heating — a radical expansion of a sphere of application, large increase of cost-effectiveness and self-financing of the construction of nuclear sources of energy, increase of their fraction in the base part of the load schedule, and large-scale displacement of fossil fuel — is validated. Suggestions for a...

The place of research reactors in validating new energy technologies, which are being developed, and advances in science is analyzed. It is shown that research reactors are a verified effective and irreplaceable tool for advancement in nuclear power, fundamental science, and applied research and technologies for industry, biology, and medicine. Dir...

The expansion of space exploration requires the development of sufficiently powerful and reliable power facilities which can operate for a long time. Such facilities could be nuclear power systems and nuclear-powered propulsion systems with turbomachine energy conversion. The development of such systems at the present time is based on the results o...

The results of investigations performed by specialists at Research and Design Institute of Electrical Technology together with other enterprises, institutes, and organizations concerning the formulation of a strategy for the development of nuclear power in Russia in the first half of the 21st century are presented. The individual stages of the work...

The article presents an overview of the issues for ensuring safe operation of the Russian nuclear power plants with RBMK-1000 reactors.The operating data for such NPPs are included, the upgrading activities are described. The examples of the major implemented activities and their contribution to safety enhancement are given.The activities aimed at...

Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950's and 1960's in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with supercritical water (SCW) became attractive again as the ultimate development path for water-cooling. The main objectives of using...

The paper presents a review of the main principles for technologies and materials protection from unauthorized proliferation and application to be considered in nuclear reactors designing. Nuclear power features certain operations sensitive to nuclear weapons proliferation (such as separation of uranium isotopes (enrichment), long storage of spent...

A list of measures for extending the lifetime of power-generating units with RBMK reactors is presented. The normative approaches and criteria are indicated, an assessment of the technical possibility of lifetime extension, primarily for the critical components, of at least 15 years is examined. The technical measures for safe operation after the l...

The concept of a direct-flow channel reactor with supercritical-pressure water (CR-SCP) is presented. Neutron-physics, thermohydraulic, and strength calculations are used to substantiate the fundamental core design with a heavy-metal moderator which at supercritical pressure is competitive with other modern reactor designs with respect to fuel-cycl...

The conditions for attaining an operating regime with maximum burnup of nuclear fuel are examined. This can be a regime with steady continuous reloadings with the reactor replenished with fuel whose heavy atoms contain close to 50% of the fissioning material with average content 25% and burnup 35–50%. The possibility of improving the stability of t...

The results are summarized of investigations performed over the last 20 years which culminated in the current fundamental formulation of the problem of nuclear power based on fast reactors and the basic criteria for such nuclear power in the strategy for growth and which served as a scientific basis for the preparation of the initiative of the Pres...

It is suggested that long-lived 226Ra and 230Th be extracted from ore together with uranium and then transmuted to achieve radiation equivalence. The presence or absence of extraction of radium and/or thorium together with uranium strongly influences the danger of natural uranium. If the radionuclide enters the human body with water or food, the ra...

Computed estimates of the mass ratio of Am, Cm, Np, and plutonium for different burnup of VVÉR and RBMK fuel and the post-reactor holding time are presented. The holding time for which this ratio reaches the admissable value 0.32 is determined.

Results of calculations of the ratio of masses of Am, Np, Cm and fissile plutonium for different burnups of the WWER and RBMK fuels and their after-reactor coolings are presented. The cooling time, for which this ratio achieves admissible value of 0.32, is determined.

The possibility is examined of developing a vessel-type fast reactor cooled by water with supercritical parameters (BR-VSP) and a channel-type fast plutonium–water reactor cooled by boiling water, using the RBMK scheme, or water with supercritical parameters for burning weapons or power-production plutonium (RBMK-Pu). A reactor with construction si...

A methodology and preliminary results of a computational analysis of the processes occurring in the graphite masonry in RBMK channel reactors during the rupture of a fuel channel as a result of accidental overheating are presented. The methodology for the computational analysis is implemented using the U_STACK code, simulating the thermohydraulic a...

Heat transfer was studied for the case of autowave transition from metastable to stable boiling regimes. The boiling curves classification was proposed in dependence on the direction of the vectorial parameters, such as temperature gradient, flow and temperature wave velocity. According to the proposed hypothesis, considerable changes in heat trans...

The development of nuclear power with capacity up to 300 GW using thermal reactors and BREST fast reactors with small excess breeding (BR 1.05) and nuclear power operating potentially for up to 3750 yr using depleted uranium is examined on the basis of fuel materials balances. To examine the radiation balance, all wastes, which have accumulated by...

The development of NPE on the basis of thermal and fast reactors is considered at the NPE action potential to 3750 years and using the depleted uranium. Variation of the potential biological danger is calculated in dependence on the time of cooling all radioactive wastes. The possibility of beginning the thorium and radium extraction together with...

Possibilities are considered of developing the vessel FR with cooling the water with the SCP and channel water-plutonium FR with cooling the boiling water or SCP water. These reactors are intended for utilizing the arm or power plutonium. This aim may be achieved also by means of the reactor of the RBMK type, but without graphite moderator and zirc...

The goals of developing an MPGR reactor system are formulated and the basic advantages of the system are discussed. The results of verification of the computational methods on experimental parameters of the IGR prototype reactor and estimates of the physical characteristics of the MPGR system are presented.

The paper discusses the methodology and a computational exercise analyzing the processes taking place in the graphite stack of an RBMK reactor in case of a pressure tube rupture caused by overheating. The methodology of the computational analysis is implemented in integrated code U{sub S}TACK which models thermal-hydraulic and mechanical processes...

The proposal to organize and realize the international program on leasing of Nuclear Power Plant (NPP) reactor compartments is brought to the notice of potential partners. The proposal is oriented to the construction of new NPPs or to replacement of worked-out reactor units of the NPPs in operation on the sites situated near water area and to the u...

To proposal to organize and implement the international project on nuclear reactor leasing is oriented to both the construction of new Nuclear Power Plants (NPPs) and the replacement of phased-out reactor compartments. The performed technical and economic assessment of the project on leasing of nuclear power reactor units has shown the feasibility...

The results of a competition for the development and verification of a more accurate domestic integrated computer code for simulating processes occurring in the containment shell of a nuclear power plant with a VVR reactor are examined. The basic requirements for the competing codes, the results of the calculations performed on the basis of the sta...

The radiation characteristics of fuel cycles of various reactors – replacement candidates in the future nuclear power – are compared. Proceeding from the basic requirements (safety, fuel supply, and nonproliferation of fissioning materials), inherently safe fast reactors of the BREST type can be used as the basis for large-scale nuclear power. Ther...

Heat transfer is investigated under conditions of autowave change from a metastable boiling mode to a stable one. The classification of boiling curves is suggested that depends on the temperature gradient and on the directions of flow velocity and velocity of temperature wave motion. A hypothesis is advanced according to which a considerable variat...

On-site storage facilities, consisting of ponds with water, for irradiated RBMK-1000 fuel are now close to being filled. To continue operating nuclear power plants with RBMK reactors, it is necessary to select one possible method for handling irradiated fuel.A variant of long-term storage followed by reprocessing is examined and considerations are...

Radiation characteristics of the fuel cycles in different reactors are compared. Proceeding from the safety requirements the natural-safe fast reactors of the BREST type may be considered as the basis for large-scale nuclear power engineering of the future. The thermal reactors of the WWER-1000 and CANDU types may operate simultaneously with the BR...

Results are considered of the competition for development and verification of the domestic integral code of improved estimation for simulation of the processes in the NPP containment with WWER. Main demands to competition participants and results of carried out calculations within the framework of the standard safety problem are presented. Comparat...

A version of prolonged storage of the spent fuels from the RBMK-1000 and WWER-1000 reactors with the following reprocessing is considered. Reasons on the future using of the RMBK and WWER reprocessed spent fuel as the fuel for the initial charging of natural safe fast reactor are presented. When solving the problems the economic estimations and req...

The effect of the technology used to separate elements with nonaqueous radiochemical reprocessing of fuel on the radiation characteristics of the fuel and the wastes is examined. The study was conducted for the intrinsically safe BREST-1200 fast reactor. The conditions for achieving radiation equivalence between the raw material used for reactor op...

The possibilities for a fuel-channel pipe in RBMK, with nominal parameters, to rupture under internal and external loading caused by the rupture of a neighboring damaged channel, which becomes overheated for a general reason, are analyzed. The deformation of the masonry and the loads on the pipes are calculated using the R_SPACE code. The stress st...

Rupture of several technological channels in the reactor space formed by the metallic structures surrounding the graphite lining of the core is one of the emergency situations envisaged during the project stage of nuclear power plants incorporating the RBMK reactors. In order to avoid loss of integrity in such an event, a system releasing (ejecting...

The results of calculation of pressure dynamics in the reactor space in the case of the rupture of identical channels are reported. It is noted, that a non- simultaneous rupture of the channels result in a later reaching of the absolute maximum of pressure in the reactor space. The calculation results demonstrate, that increase in the time lag, giv...

1. Transverse-injection methods significantly reduce the critical flow rate of slightly underheated and saturated water; for stem-water mixture and steam, the effect is no more than 5–10%. 2. As an emergency coolant flow-rate limiter, the nozzle with transverse injection through attachments projecting into the flow cross section and the nozzle with...

Measured values of the hydraulic discharge coefficient and the critical mass flowrate are presented. Experiments have been carried out on three Laval nozzles over the following range of flow operating parameters at the inlet of the nozzle: pressure—4 and 8 MPa; water subcooling—from 0 to 50°C; quality of the two-phase mixture—from 0 to 1; and steam...

Six nozzles with various ways of cross-sectional injection into flow-through section are studied. The greatest effect of decreasing critical discharge was noted in case of outflow of weakly underheated and saturated water. The nozzle with cross-sectional injection through one-row system of tangential holes is more preferable for application as a li...

Discharge of boiling water and steam-water mixture through a convergent nozzle is encountered in the operation of hydraulic channels of modern power plants. The published experimental studies of this process are summarized in Table i. The table shows that the experiments were performed, excluding [3], with low pressure of the medium at the nozzle i...

Conclusions 1.It was found that the effectiveness of transverse injection as a method for reducing the critical discharge in all cases studied is maximum near the point (?i/r)in˜0 and can reach 25–40%. Increasing Pin from 4 to 8 MPa increases the effectiveness of transverse injection primarily for discharge of a steam-water mixture.2.Injection at a...

Transition to coolant of supercritical parameters allows for principle engineering-and-economic characteristics of light-water nuclear power reactors to be substantially enhanced. Russian experience in development of channel-type reactors with supercritical water coolant has demonstrated advantages and practical feasibility of such reactors. (autho...

The problem of forced computer codes development and validation became an urgent task in Russia due to some practical requirements. To solve this problem a coordination centre was established in Minatom of Russian Federation in late 1990s. Now new best-estimate code KORSAR and containment code KUPOL-M are brought into practice.

The co-generation nuclear power plant (CNPP) producing electricity and district-heating heat is planned to be constructed in Archangelsk Region of Russia. Following the "Letter of Intent" signed by Governor of Archangelsk region and by Minister of the Russian Federation for atomic energy the feasibility study of the Project has been done. The NPP w...