About neutron capture therapy method development at WWR-SM reactor in institute of Nuclear Physics of Uzbekistan Academy of Sciences

International Nuclear Information System (INIS)

Abdullaeva, G.A.; Baytelesov, S.A.; Dosimbaev, A.A.; Koblik, Yu.N.; Gritsay, O.O.

2006-01-01

Full text: Neutron capture therapy (NCT) is developing method of swellings treatment, on which specialists set one's serious hopes, as at its realization the practical possibilities of the effect on any swellings open. The essence of method is simple and lies in the fact that to the swelling enter preparation containing boron or gadolinium, which one have a large capture cross-section of the thermal and slow neutrons. Then the swelling is irradiated once with the slow (epithermal) neutron beam with fluency about 10 9 neutrons /sm 2 s for a short time and single. As a result of thermal neutrons capture by the boron (or gadolinium) nuclei secondary radiation which affecting swelling cells is emitted. NCT of oncologic diseases makes the specific demands to physical parameters of neutron beams. Now research reactors are often used for NCT. However, research reactor WWR-SM (INP, Uzbekistan AS, Tashkent) doesn't provide with the epithermal neutron beams and to develop this technique the reactor, first of all, needs for obtaining the epithermal neutron beams with energy spectrum in range from 1 eV up to 10 keV and with intensity ∼ 10 9 neutron /sm 2 s. Practically it is connected with upgrade of at least one of existed reactor channels, namely with equipping with the special equipment (filters), forming from the reactor spectrum the beam of necessary energy neutrons. It requires realization of preliminary model calculations, including calculations of capture cross-sections, of filters types and their geometrical parameters on the basis of optimal selected materials. Such calculations, as a rule, are carried out on the basis of Monte-Carlo method and designed software for calculation of nuclear reactor physical and technical characteristics [1]. In this work the calculation results of devices variants and problems discussion, related with possibility of WWR-SM reactor using for NCT are presented. (author)

Production of the sealed gamma-radiation sources of with iridium-192 radionuclide at the WWR-K research reactor

International Nuclear Information System (INIS)

Petukhov, V.K.; Chernayev, V.P.; Chabeyev, N.T.; Ermakov, E.L.; Chakrov, P.V.

2005-01-01

Full text: Conversion orientation of the WWR-K research reactor activity was established after renewal of its operation in 1997. A priority in reactor works was determined in the decision of tasks of practical use of nuclear technologies in a national economy in the next directions: in an industry, public health services and agriculture. The items of prime tasks: development and introduction of radiation technologies and manufacturing of radioisotopes for industry. This task included both scientific and technical program in the list of works of the Republican goals. At the WWR-K reactor within the framework of the this task solution the works on pilot production of the sealed sources of radioactive radiations (SSRR) with Ir-192 radionuclide for an industry of Republic of Kazakhstan were made. Organizational questions related to the Kazakhstan authority body and the regulating documentation were solved the first of all. The second stage was the development of the techniques of creating of devices providing an samples irradiation in reactor, control of sources sealing, measurements of the equivalent radiation doze from sources and high-quality support of SSRR manufacture over all technological way. At the third stage was made a little quantity SSRR with Ir-192 radionuclide, such as GIID-A1 (G6), for 'TEKOPS-660' Gammaray Projectors. This work served as experimental check of the decisions correctness, and has allowed to remove those lacks, to find out which it was possible only during direct manufacturing of radioactive sources. During performance of all these works the following was carried out: development and release of the documents and specifications regulating work on SSRR manufacture at the Institute of Nuclear Physics; personnel preparation and certification; preparation and equipment providing of reactor hot chambers by additional devices for work with irradiated iridium samples; development and manufacturing of the devices for iridium samples irradiation in

Some aspects related to radioprotection during decommissioning of the WWR-S research reactor

International Nuclear Information System (INIS)

Pantazi, Doina; Stan, Camelia

2007-01-01

Radiological safety management ensures protection of personnel, public and environment. During decommissioning of a WWR-S type research reactor, besides other specific industrial problems, radiation and/or contamination sources will be produced and their effects have to be kept under control. In any decommissioning operation that implies working in a radioactive environment, the main concern being the minimization of the total dose received by the workers. To minimize the possible dose that an individual could receive, prior entering the working area, a definite set of stages of a radiation protection plan, developed according to ALARA principle, should be implemented. Of major interest is estimation the effective dose which operators will receive during a year, considering all operations in that he is involved and all the different possible paths of irradiation or contamination (inhalation, skin penetration, injury, etc.). The estimation of doses received by operating personnel will take into consideration the following steps: - the determination of jobs and events which could involve a significant radiation dose exposure; - whole body and extremities exposure doses should be assessed taking into consideration that the likelihood of contact with radiation and/or contamination sources is higher for hands and legs; - all possible paths of exposure will be identified (external irradiation is the most expected while the internal exposure due to intake could happen following an accidental inhalation of radionuclides or an injury in contaminated medium); - technological controls and administrative measures for exposure minimization will be rigorously implemented; - estimated doses will be compared with maximum permissible levels. The paper describes some general methodologies for computing the total effective doses received by workers involved in decommissioning operations, as well as their application for few special situations, that could contribute significantly to

Study of the WWR-S IFIN-HH reactor main components stare, after 40 years working, using nondestructive methods

International Nuclear Information System (INIS)

Dragolici, A. C.; Zorliu, A.; Ripeanu, R.; Petran, C.; Mincu, I.

2000-01-01

The main goal of these investigations was to establish the security level after 40 years of working of the WWR-S research reactor of Horia Hulubei National Institute of Research and Development for Physics and Nuclear Engineering, Bucharest-Magurele. The purpose of these investigations was: checking the functionality and the physical integrity of the main components of the reactor. The physical integrity of the components is usually affected by slow processes, such as: corrosion, erosion, aging, deformations and initially hidden flaws with very slow evolutions. The methods used to determine the effects of these processes and to infer conclusions about the physical integrity of the facility are: visualizations by optical means (endoscopy and video camera), examination using ultrasounds and gammagraphy. The objective of the endoscopic checking was the view of the state of interior surfaces of the tubes and pipes, specially the inaccessible areas of the non-dismantling parts of the reactor. Big size components, such as reactor vessel, the biologic protection vessel and the main large diameter pipes of the primary cooling system, were investigated using a special device that contains a video camera connected to a PC. To obtain more information regarding the evolution of the corrosion spots, scratches and harmed areas on the investigated surfaces, their depth was checked by ultrasounds, and the welding seams structure was determined by gammagraphy. A table is given with some significant results obtained from ultrasound measurements in different points of reactor vessel, thermal column, horizontal tubes, etc. After these tests, the conclusions are: the maximum corrosion depth is 0.2 mm; - scratches are superficially, not exceeding 0.2-0.5 mm; - the traces of harmed areas are produced by the electromagnetic device utilization used for manipulation of aluminium capsules which contain irradiated substances. They are superficial, with maximum area of about 1 cm 2 ; the

Accuracy of WWR-M criticality calculations with code MCU-RFFI

International Nuclear Information System (INIS)

Petrov, Yu.V.; Erykalov, A.N.; Onegin, M.S.

1999-01-01

The scattering and deviation of fuel element parameters by manufacturing, approximations of the reactor structure in the computer model, the partly inadequate neutron cross sections in the computer codes etc. lead to a discrepancy between the reactivity computations and data. We have compared reactivity calculations using the MCU-RRFI Monte Carlo code of critical assemblies containing WWR-M2 (36 enriched) an WWR-M5 (90%) fuel elements with benchmark experiments. The agreement was about Δρ≅±0.3%. A strong influence of the water ratio on reactivity was shown and a significant heterogeneous effect was found. We have also investigated, by full scale reactor calculations for the RETR program, the contribution to the reactivity of the main reactor structure elements: beryllium reflector, experimental channels irradiation devices inside the core, etc. Calculations show the importance of a more thorough study of the contributions of products of the (n, α) reaction in the Be reflector to the reactivity. Ways of improving the accuracy of the calculations are discussed. (author)

Accuracy of WWR-M criticality calculations with code MCU-RFFI

Energy Technology Data Exchange (ETDEWEB)

Petrov, Yu V [Petersburg Nuclear Physics Institute RAS, 188350 Gatchina, St. Petersburg (Russian Federation); Erykalov, A N; Onegin, M S [Petersburg Nuclear Physics Institute RAS, 188350 Gatchina, St. Petersburg (Russian Federation)

1999-10-01

The scattering and deviation of fuel element parameters by manufacturing, approximations of the reactor structure in the computer model, the partly inadequate neutron cross sections in the computer codes etc. lead to a discrepancy between the reactivity computations and data. We have compared reactivity calculations using the MCU-RRFI Monte Carlo code of critical assemblies containing WWR-M2 (36 enriched) an WWR-M5 (90%) fuel elements with benchmark experiments. The agreement was about {delta}{rho}{approx_equal}{+-}0.3%. A strong influence of the water ratio on reactivity was shown and a significant heterogeneous effect was found. We have also investigated, by full scale reactor calculations for the RETR program, the contribution to the reactivity of the main reactor structure elements: beryllium reflector, experimental channels irradiation devices inside the core, etc. Calculations show the importance of a more thorough study of the contributions of products of the (n, {alpha}) reaction in the Be reflector to the reactivity. Ways of improving the accuracy of the calculations are discussed. (author)

Power reactor noise measurements in Hungary

International Nuclear Information System (INIS)

Pallagi, D.; Horanyi, S.; Hargitai, T.

1975-01-01

An outline is given of the history of reactor noise research in Hungary. A brief description is given of studies in the WWR-SM reactor, a modified version of the original WWR-S thermal reactor, for the detection of in-core simulated boiling by analysis of the noise of out-of-core ionization chambers. Coolant velocity measurements by transit time analysis of temperature fluctuations are described. (U.K.)

Review of the book: Yurkevich, G.P. Energetic reactor control systems. Editing by N.S. Khlopkin. Moscow, 2001, 344 p

International Nuclear Information System (INIS)

Kondrat'ev, V.V.

2002-01-01

Review of the book: Yurkevich, G.P. Energetic reactor control systems. Editing by N.S. Khlopkin. Moscow, 2001, is presented. Advantages of the book, specifically, easy of presentation of sophistical physical processes, new, practical and valid theoretical ways of decision of the problems are discussed. New and original decisions proposed by the author of the book are discussed. The book is beneficial for wide round of specialists [ru

Seismic safety review mission Almaty WWR 10 MW research reactor Almaty, Kazakhstan. Final report

International Nuclear Information System (INIS)

Gurpinar, A.; Slemmons, D.B.; David, M.; Masopust, R.

1995-06-01

On the request of the government of Kazakhstan and within the scope of the TC project KAZ/0/004, a seismic safety review mission was conducted in Almaty, 8-19 May 1995 for the WWR 10 Mw research reactor. This review followed the fact finding mission which visited Almaty in November 1993 together with an INSARR mission. At that time some information regarding the seismotectonic setting of the site as well as the seismic capacity of the facility was obtained. This document presents the results of further work carried out on both the issues. It discusses technical session findings on geology, seismology, structures and equipments. In the end conclusions and recommendations of the mission are given. 4 refs, figs, tabs, 18 photos

Seismic examination for assessment of safety of location of atomic energy objects (by the example of the WWR-K reactor, Ala-Tau village)

International Nuclear Information System (INIS)

Belyashova, N.N.

2001-01-01

In the Republic of Kazakhstan there are 3 research reactors (the fourth one is temporarily stopped). One of the reactors in 1998 (WWR-K, situated in the Ala Tau village, nearby Almaty city) was conserved because of a number of reasons. Including the reason of the earth crust geological structure insufficient study for the ensuring the seismic safety of the reactor site location. In 1994-1996 a number of geological-geophysical studies was carried out by Kazakhstan specialists confirming the the geological-geophysical conditions in the reactor site location in view of its safety. These condition are meeting to IAEA requirements and up-to-date standards acting in Kazakhstan

Experiment on search for neutron-antineutron oscillations using a projected UCN source at the WWR-M reactor

Science.gov (United States)

Fomin, A. K.; Serebrov, A. P.; Zherebtsov, O. M.; Leonova, E. N.; Chaikovskii, M. E.

2017-01-01

We propose an experiment on search for neutron-antineutron oscillations based on the storage of ultracold neutrons (UCN) in a material trap. The sensitivity of the experiment mostly depends on the trap size and the amount of UCN in it. In Petersburg Nuclear Physics Institute (PNPI) a high-intensity UCN source is projected at the WWR-M reactor, which must provide UCN density 2-3 orders of magnitude higher than existing sources. The results of simulations of the designed experimental scheme show that the sensitivity can be increased by ˜ 10-40 times compared to sensitivity of previous experiment depending on the model of neutron reflection from walls.

Decommissioning of the research nuclear reactor WWR-S Magurele - Bucharest. General presentation of the project

International Nuclear Information System (INIS)

Dragulescu, Emilian; Dragusin, Mitica; Popa, Victor; Boicu, Alin; Tuca, Carmen; Iorga, Ioan; Vrabie, Ionut; Mustata, Carmen

2003-01-01

A decommissioning project was worked out concerning the nuclear facility research reactor WWR-S Magurele-Bucharest to remove the radioactive and hazardous materials and so to exclude any risk for human health and environment. The project involves the four phases named assessment, development, operations and closeout. There are two major parts to the assesment phase: preliminary characterisation and the review and decision-making process. Characterisation is needed to develop project baseline data, which should include sufficient chemical, physical, and radiological characterisation to meet planning needs. Based on the conclusions of these studies, possible decommissioning alternative will be analyzed and: the best alternative chosen, final goal identified, risk assessments are evaluated. Also, taken into account are: regulations supporting assessment, land use considerations, financial concerns, disposal availability, public involvement, technology developments. After a decommissioning alternative was chosen, detailed engineering will begin following appropriate regulatory guidance. The plan will include characterisation information, namely: review of decommissioning alternatives; justification for the selected alternative; provision for regulatory compliance; predictions of personnel exposure, radioactive waste volume, and cost. Other activities are: scheduling, preparation for decommissioning operations; coordination, documentation, characterization report, feasibility studies, Decommissioning Plan, project daily report, radiological survey, airborne sampling records, termination survey of the site. The operations imply: identification and sequencing the operations on contaminated materials, storing on site the wastes, awaiting processing or disposal, and packaging of materials for transport to processing or disposal facilities.The key operations are: worker protection, health and safety program, review of planing work, work area assessment, work area controls

Neutronic feasibility studies using U-Mo dispersion fuel (9 Wt % Mo, 5.0 gU/cm3) for LEU conversion of the MARIA (Poland), IR-8 (Russia), and WWR-SM (Uzbekistan) research reactors

International Nuclear Information System (INIS)

Bretscher, M.M.; Deen, J.R.; Hanan, N.A.; Matos, E.

2000-01-01

U-Mo alloys dispersed in an Al matrix offer the potential for high-density uranium fuels needed for the LEU conversion of many research reactors. On-going fuel qualification tests by the US RERTR Program show good irradiation properties of U-Mo alloy dispersion fuel containing 7-10 weight percent molybdenum. For the neutronic studies in this paper the alloy was assumed to contain 9 wt % Mo (U-9Mo) with a uranium density in the fuel meat of 5.00 gU/cm 3 which corresponds to 32.5 volume % U-9Mo. Fuels containing U-9Mo have been used in Russian reactors since the 1950's. For the three research reactors analyzed here, LEU fuel element thicknesses are the same as those for the Russian-fabricated HEU reference fuel elements. Relative to the reference fuels containing 80-90% enriched uranium, LEU U-9Mo Al-dispersion fuel with 5.00 gU/cm 3 doubles the cycle length of the MARIA reactor and increases the IR-8 cycle length by about 11%. For the WWR-SM reactor, the cycle length, and thus the number of fuel assemblies used per year, is nearly unchanged. To match the cycle length of the 36% enriched fuel currently used in the WWR-SM reactor will require a uranium density in the LEU U-9Mo Al-dispersion fuel of about 5.4 gU/cm 3 . The 5.00 gU/cm 3 LEU fuel causes thermal neutron fluxes in water holes near the edge of the core to decrease by (6-8)% for all three reactors. (author)

Waste generated by the future decommissioning of the Magurele VVR-S Research Reactor

International Nuclear Information System (INIS)

Dragolici, F.; Turcanu, C.N.; Dragolici, A.C.

2001-01-01

Nuclear Research Reactor WWR-S from the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei', Bucharest-Magurele, was commissioned in July 1957 and it was shut down in December 1997. At the moment the reactor is in conservation state. During its operation this reactor worked at an average power of 2MW, almost 3216 h/year, producing a total thermal power of 230 x 10 3 MWh. No major modifications or improvements were made during the 40 years of operation to the essential parts of the reactor, respective to the primary cooling system, reactor vessel, active core and electronic devices. So, all components of the measure, control and protection systems are old, generally at the technical level of the 1950s, therefore a reason why in December 1997 the operation was ceased. At present, the reactor can be considered, by IAEA definition in the first stage (reactor shut down, but the vital functions are maintained and monitored). The survey is related to the second stage - restrictive use of the area. To develop a real decommissioning project, it was first necessary to evaluate the volume and the characteristics of the radioactive waste which will be generated. Radioactive waste generated during the decommissioning of Magurele WR-S research reactor may be classified as: Activated wastes (internal structures, horizontal channels and thermal column, biological shield); Contaminated wastes (primary circuit non-activated components, hot cells, some technological rooms as main hall, pumps room, radioactive material transfer areas, ventilation building and stack); Possibly contaminated materials from any area of reactor building and ventilation building. After 40 years of nuclear research activities, all such areas are suspected of contamination. The volume of wastes that will result from WWR-S Research Reactor decommissioning is summarized

Generation of the problem-dependent data libraries for IFIN-HH WWR-S spent fuel storage criticality and dose calculation

International Nuclear Information System (INIS)

Ene, Daniela; Tigau, F.

1998-01-01

The methods used for the radioactivity inventory calculation and dose evaluation of the fuel elements irradiated in the WWR-S IFIN-HH reactor are discussed in this work. A particular attention is paid to the processed problem-dependent nuclear libraries. SAS2H, a complex sequence of the SCALE-4.3 code system containing the modules BONAMI - NITAWL - XSDRNPM - COUPLE - ORIGEN-S - XSDOSE, has been assimilated on the IFIN-HH computer and applied to update the ORIGEN-S libraries by producing problem-dependent processed data libraries needed to perform the depletion and shielding analysis. This sequence uses one of the eight associated data libraries of the SCALE-4.3 system according to the choice of the user. The method consists in the following analysis processes: i) lattice cell neutron analysis to produce the flux weighting spectrum for activation library updating; ii) update of the nuclear data constants of the ORIGEN-S libraries; iii) depletion and decay analysis for a specified fuel assembly and irradiation history in order to generate gamma and neutron source strength and spectra. iv) one-dimensional radial shielding calculation for the evaluation of the angular neutron and gamma flux at the surface of a spent fuel shipping cask and further calculation of the dose rates at various points outside the cask. An efficient alternative of the calculation sequence mentioned above is the ARP (Automatic Rapid Processing) method conceived in order to generate independently ORIGEN-S libraries and to reduce substantially the running time. The substance of this method is the generation of the problem-dependent libraries from basis libraries a priori created by SAS2H for specific fuel assembly type and further interpolation of two independent variables, enrichment and burnup. Specific applications concerning WWR-S spent fuel were performed: i) generation of three problem-dependent libraries for the S-36 fuel assembly taking into account the maximum value of the burnup of this

Calculational investigations and analysis of characteristics of research reactor WWR-M as a source of neutrons for solution of scientific and applied tasks

International Nuclear Information System (INIS)

Vorona, P.M.; Razbudej, V.F.

2010-01-01

Calculational studies and analysis of the neutron fields of WWR-M research reactor of the Institute for Nuclear Research, National Academy of Sciences of Ukraine, as a basic nuclear facility for performing the fundamental and applied investigations and for experimentalindustrial production of radioisotope products for various spheres of application are carried out. The calculations are carried out by the method of statistic tests (Monte Carlo) applying the computer program MCNP-4C. The data on the spectra and the neutron flux density values at the 10 MW reactor power for all technological facilities designed for the works with neutrons: 19 vertical experimental channels for irradiation of specimens and 10 horizontal channels for beams extraction from the reactor are obtained. The effect of the neutron traps (water cavities) mounted in the core on the characteristics of the extracted from the reactor beams is demonstrated. Recommendations associated with optimization of the reactor core are adduced for amplification of its capabilities as a neutron source in experimental researches.

Encapsulation technology of MR6 spent fuel and quality analysis of the EK-10 and WWR-SM spent fuel stored more than 30 years in wet conditions

Energy Technology Data Exchange (ETDEWEB)

Borek-Kruszewska, E.; Bykowski, W.; Chwaszczewski, S.; Czajkowski, W.; Madry, M. [Institute of Atomic Energy, Otwock -Swierk (Poland)

2002-07-01

The research reactor MARIA has been in operation for more than twenty years and all the spent fuel assemblies used since the first commissioning of the reactor are stored in wet facility on site. The present paper deals with the spent fuel MR-6 encapsulation technology in MARIA reactor. The encapsulated spent MR-6 fuel will be stored under water in the same pool unless some other solution is available. The capsules made of stainless steel are capable to accommodate one MR-6 fuel assembly. The encapsulation process is performed in the hot cell by the MARIA reactor. The spent fuel having its leg cut off is loaded to the transport cylinder manually and next transferred to a trolley. The trolley is moving to a position directly below the entrance to the hot cell and the spent fuel is entering the hot cell. The spent fuel assembly is then put into the drying cell. Dried out spent fuel is moved into the capsule mounted on the grip of the machine. Next, the capsule lid is pressed in and welded. After the leak test and filling up with helium the capsule returns from the hot cell to the pool. The hermetic capsule is sunk back into the water and positioned in the separator . The results presented earlier show, that the limiting time of WWR-SM and Ek-10 type spent fuel residence in wet storage is about 40-45 years. Therefore, the systematic quality investigation of all Ek-10 fuel elements and WWR-SM fuel assemblies discharged from EWA reactor in the period of 1959-1969 was performed. Altogether, about 2500 Ek-10 fuel elements and 47 WWR-SM fuel assemblies were investigated. The results of these investigations are presented in the present work. The sipping test, visual investigation and ultrasonic techniques were used for that purpose. The radioactive isotope Cs-137 was used as the indicator of fission product release from the fuel assembly. Taking into account the value of Cs-137 release from damaged WWR-SM fuel assembly the criteria of damaged fuel assembly were proposed. It

Radiologic states of the WWR-S Bucharest Reactor following definitive shutdown

International Nuclear Information System (INIS)

Garlea, C.; Kelerman, C.; Mocioiu, D.; Garlea, I.

2001-01-01

The definitive shutdown of a reactor raises problems related to the management of the radioactive inventory. To define the radioactive inventory contained in the burned nuclear fuel and in the neutron activated structural materials computation methods are to be used. Besides the radioactive inventory contained in the main block of the reactor, the one due to the primary circuit contaminated mainly with fission products and corrosion products activated in the reactor core, transported and deposed on the components of the cooling primary circuit should be added. Also another component of the radioactive inventory intervenes, namely, the one due to the contamination of the technological rooms used for various operations the nuclear activities (hot cells, pump room, reactor hall, passage ways to the hot cells and for radioactive source, radioisotope and radioactive waste transport). The activities which made used of the neutron and gamma fluxes for radioisotope production, materials irradiation, research, component testing, resulted in radioactive waste, technological or accidental contaminations of the technological rooms of the reactor. Inspections and current repair interventions resulted also in radioactive waste an contaminations. Consequently systematic measurements with qualified equipment dedicated to alpha, beta, gamma contamination measurements as well as to dose rates determinations for the personnel exposed are necessary. Irrespective of the duration of the reactor conservation or shutdown, the radiologic monitoring should continue. This work presents the results obtained by the research group 'Restoration of Nuclear Sites', working with the IFIN-HH, regarding both the radioactive inventory calculation and measurements of contamination of technological rooms and environment in the reactor vicinity

Calculation of prefabricated part of WWR-K reactor building

International Nuclear Information System (INIS)

Belyashova, N.N.; Aptikaev, F.F.; Kopnichev, Yu.F.

1998-01-01

According of factual characteristics a strength and deformation of over-land part of carrier constructions under construction movement is defined. Direct dynamical calculation of design elements under action of inertial loads from supports shifts shows, that seismic stability of enclosing construction is not ensured. Possibly practically total collapse of coating construction is possibly, under which following levels of damages of internal design constructions of reactor central room have been forecasted: 1. Fall of destroyed design construction on reactor vessel in time moment (1.56-1.59 s) after coming to building of earthquake seismic waves of 10 balls. 2. It is possibly cracks formation in radial direction in lower part of reactor cap, but destroying of cap does not incident; 3. It is possibly cracks formation within stretched concrete zone of reactor construction at the mark from - 0.859 up to 0.100. Destroy of concrete's compressive zone of reactor construction have not being expected. 4. Collapse of reactor first contour coating constructions have not being expected

Investigation of neutron fluence using fluence monitors for irradiation test at WWR-K

International Nuclear Information System (INIS)

Romanova, N.K.; Takemoto, N.

2013-01-01

Irradiation test of a Si ingot is planned using WWR-K in Institute of Nuclear Physics Republic of Kazakhstan (INP RK) to develop an irradiation technology for Si semiconductor production by Neutron Transmutation Doping (NTD) method in the framework of an international cooperation between INP RK and Japan Atomic Energy Agency (JAEA), Japan. It is possible to irradiate the Si ingot of 6 inch in diameter at the K-23 irradiation channel in the WWR-K. The preliminary irradiation test using 4 Al ingots was performed to evaluate the actual neutronic irradiation field at the K-23 channel in the WWR-K. Each Al ingot has the same dimension as the Si ingot, and 15 fluence monitors are equipped in it. Iron wire and aluminum-cobalt wire are inserted into them, and it is possible to evaluate both fast and thermal neutron fluxes by measurement of these radiation activities after irradiation. This report described the results of the preliminary irradiation test and the neutronic calculations by Monte Carlo method in order to evaluate the neutronic irradiation field in the irradiation position for the silicon ingot at the channel in the WWR-K. (authors)

Determination of the gamma-ray flux of the stopped WWR-SM reactor by color center production in LiF

International Nuclear Information System (INIS)

Mussaeva, M.A.; Kalannov, M.U.; Ibragimova, E.M.; Karabaev, Kh.Kh.

2004-01-01

Full text: Gamma-radiation with a wide energy spectrum, accompanying neutron flux in the nuclear reactor, is known to result in radiation heating of materials. It is usually detected either by calorimetry or by an ionizing chamber maintained in the active zone while the reactor works and high-energy neutrons also contribute into ionization. The aim of this research was to separate the gamma-component from the neutron flux upon stopping the WWR-SM reactor and to determine the gamma-intensity both with the ionization chamber and the well-known dosimeter LiF crystal, and also by comparing with the effect of monochromatic 60 Co gamma-radiation of the known flux and dose. For LiF with small Z the photoelectric effect is weak, and Compton scattering prevails. Both the optical absorption and photo-luminescence techniques together with micro-hardness and X-ray diffraction analysis were used for measuring the structure defect generation rate in the irradiated crystals, which is proportional to the gamma-intensity. Fluorine vacancy trapping electron is the well-known stable F-center responsible for the isolated absorption band at 250 nm and induced by radiolysis mechanism. The sequential irradiations and measurements were done within 150 hours after the moment of the reactor quenching. The dose dependence of the absorption band was found to be linear up to the dose of 10 6 R. The F-center concentration as a measure of an accumulated dose was calculated by the Smakula formula. At higher doses another band at 440 nm appears like that for 60 Co irradiation, which is responsible for unstable F 2 and F 3 centers formed due to coagulation of F-centers. X-diffraction analysis revealed twin structure in (111) plane. Yet the micro-hardness of the gamma-irradiated samples did not change noticeably. For higher doses the photo-luminescence band at 650 nm was also used as a dosimetric item. The luminescence kinetics has a fast nanosecond scale component and a weak tail in a microsecond

[Radiation ecological environment in the Republic of Kazakhstan in the vicinity of the reactors and on the territory of the Semipalatinsk Test Site].

Science.gov (United States)

Kim, D S

2012-01-01

The results of research into the environmental conditions in the regions of location of the pressurized water reactor WWR-K, fast neutron breeder BN-350 and on the territory of the Semipalatinsk Test Site are represented. The effects of the exposure to aerosol emissions from WWR-K and BN-350 reactors on the environment are summarized. We present some arguments in favor of the safe operation of fission reactors in compliance with the rules and norms of nuclear and radiation protection and the efficient disposal of radioactive waste on the territory of the Republic.

Feasibility study for LEU conversion of the WWR-K reactor at the Institute of Nuclear Physics in Kazakhstan using a 5-tube fuel assembly

International Nuclear Information System (INIS)

Hanan, N.A.; Liaw, J.R.; Matos, J.E.

2005-01-01

A feasibility study by the RERTR program for possible LEU conversion of the 6 MW WWR-K reactor concludes that conversion is feasible using an LEU 5-tube Russian fuel assembly design. This 5-tube design is one of several LEU fuel assembly designs being studied (Ref. 1) for possible use in this reactor. The 5-tube assembly contains 200 g 235 U with an enrichment of 19.7% in four cylindrical inner tubes and an outer hexagonal tube with the same external dimensions as the current HEU (36%) 5-tube fuel assembly, which contains 112.5 g 235 U. The fuel meat material, LEU UO 2 -Al dispersion fuel with ∼ 2.5 g U/cm 3 , has been extensively irradiation tested in a number of reactors with uranium enrichments of 36% and 19.7%. Since the 235 U loading of the LEU assemblies is much larger than the HEU assemblies, a smaller LEU core with five rows of fuel assemblies is possible (instead of six rows of fuel assemblies in the HEU core). This smaller LEU core would consume about 60% as many fuel assemblies per year as the current HEU core and provide thermal neutron fluxes in the inner irradiation channels that are ∼ 17% larger than with the present HEU core. The current 21 day cycle length would be maintained and the average discharge burnup would be ∼ 42%. Neutron fluxes in the five outer irradiation channels would be smaller in the LEU core unless these channels can be moved closer to the LEU fuel assemblies. Results show that the smaller LEU core would meet the reactor's shutdown margin requirements and would have an adequate thermal-hydraulic safety margin to onset of nucleate boiling. (author)

Computerized reactor power regulation with logarithmic controller

International Nuclear Information System (INIS)

Gossanyi, A.; Vegh, E.

1982-11-01

A computerized reactor control system has been operating at a 5 MW WWR-SM research reactor in the Central Research Institute for Physics, Budapest, for some years. This paper describes the power controller used in the SPC operating mode of the system, which operates in a 5-decade wide power range with +-0.5% accuracy. The structure of the controller easily limits the minimal reactor period and produces a reactor transient with constant period if the power demand changes. (author)

The Rossendorf research reactor. Operating and dismantling from a point of view of the emission control; Der Rossendorfer Forschungsreaktor. Betrieb und Rueckbau aus Sicht der Emissionsueberwachung

Energy Technology Data Exchange (ETDEWEB)

Bauer, B.; Beutmann, A.; Kaden, M.; Scheibke, J. [VKTA, Dresden (Germany); Boessert, W.; Jansen, K.; Walter, M.

2016-07-01

The Rossendorf research reactor went in operation in 1957 as GDR's first nuclear reactor and Germanys second after FRM Garching. It was a heterogeneously structured, light-water moderated and cooled tank-reactor of the Soviet type WWR-S. During his time of operation, he served both the research and the production of radioisotopes. The history of exhaust air emission monitoring and its results are presented. With view to the decommissioning time selected results are discussed. The estimated discharges are compared by the actually recognized.

The application of calorimetrical methods in nuclear technology and dosimetry

International Nuclear Information System (INIS)

Kott, J.; Krett, V.; Novotny, J.; Kovar, Z.; Jirousek, V.

1985-01-01

The report reviews theoretical as well as experimental research activities devoted to the possibilities of measuring reactor neutron and photon fields using thermic detectors based on calorimetric principle. There have been worked out theoretical principles of a reactor measuring probe intended in the first place to measuring neutron fluxes under operational temperatures inside power and research reactors, and a new philosophy of measurement has been elaborated. In addition, the report presents the experimental results as obtained on research reactors WWR-S, WWR-SM, RA, and Czechoslovak power reactor A-1 and GDR power reactor WWR-2. These results are given in connection with a newly proposed technique of reactor neutron field detection. The second part of the report presents results of works concerning beam dosimetry with the use of calorimeters

WWER-1000 reactor simulator. Workshop material

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series 12, 'Reactor Simulator Development' (2001). Course material for workshops using a pressurized water reactor (PWR) Simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication: Training Course Series No. 22 'Pressurized Water Reactor Simulator' (2003) and Training Course Series No. 23 'Boiling Water Reactor Simulator' (2003). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation. N. V. Tikhonov and S. B. Vygovsky of the Moscow Engineering and Physics Institute prepared this report for the IAEA

THE MOSCOW AMBULANCE STATION. FROM THE SOURSE TO THE PRESENT

Directory of Open Access Journals (Sweden)

N. F. Plavunov

2017-01-01

Full Text Available This article is devoted to 130th anniversary and publication of academic writings of Alexander Puchkov — Doctor of Med. Sci., Honored Doctor of Russian Soviet Federative Socialist Republic. He was permanent leader of Moscow Ambulance Station from 1923 to 1952. Data presented in Puchkov’s articles were used to compare performance of work of Moscow ambulance in it’s formative period and our days. This article shows specificities, characteristics and environment of Moscow ambulance in 1926 and 2016. For example, the number of brigades had increased by 67,9 times (from 15 in 1926 to 1018 in 2016. Average time of arrival to accident is 10-12 minutes is same for 1926 and 2016. The proportion of pediatric interventions (from birth to 15 years old had increased. Analysis of indicators allows to look at development of Moscow ambulance station from it’s formative period to our days. Fundamental principles laid down by A. Puchkov last in many cases in work of Moscow Ambulance in our days. Ambulance doctors continue to provide medical assistance promptly in the framework spelt out more than 90 years ago.

Irradiation facilities for the production of radioisotopes for medical purposes and for industry at the Rossendorf Research Reactor

International Nuclear Information System (INIS)

Hieronymus, W.

2007-01-01

In 1955, the Government of the German Democratic Republic initiated radioisotope production. With that decision, the following plants received their go ahead: - Research reactor with its user facilities; - Cyclotron with its specific facilities; - Institute for radiochemistry; - Library, lecture hall, workshops and administration buildings supporting the necessary scientific and administrative environment. The Zentralinstitut fuer Kerntechnik (ZfK), also known as the Central Institute for Nuclear Technology, was founded at Rossendorf near Dresden, Germany, to house all those plants. The Rossendorf Research Reactor (RFR) was constructed in 1956-1957. That endeavour was enabled by the technological support of the former USSR under a bilateral agreement which included the delivery of a 2 MW research reactor of the WWR-S design

Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

International Nuclear Information System (INIS)

Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

2004-01-01

Full text: The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by (1) implementing safety upgrades, or (2) assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

International Nuclear Information System (INIS)

Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

2004-01-01

The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by implementing safety upgrades, or assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

Creation of reactor's reliable system of emergency energy supply

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Brovkin, A.Yu.; Petukhov, V.K.; Chekushin, A.I.; Chernyaev, V.P.; Yagotinets, N.A.

1998-01-01

System of reliable power supply of the WWR-K reactor complex is described, which completely provides safety operation of reactor equipment in the case of total voltage loss from external power transmission lines as well as under destruction of accumulation batteries by earthquake more than 6 balls. Switching on in operation of diesel-generators and system of constant current supply from accumulator batteries is occurred automatically under cessation of voltage supply from centralized power system. Reliable reactor dampening in case it work on capacity has been ensured. Reactor cooling under its emergency shutdown during both the partial or the total loss of coolant in first counter has been carried out. Under full coolant loss the system of emergency reactor cooling has been switched on in operation

Fuel Management at the Dalat Nuclear Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Pham, V.L.; Nguyen, N.D.; Luong, B.V.; Le, V.V.; Huynh, T.N.; Nguyen, K.C. [Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat City (Viet Nam)

2011-07-01

The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed in 1982 from the old 250 kW TRIGA-MARK II reactor. The spent fuel storage was newly designed and installed in the place of the old thermalizing column for biological irradiation. The core was loaded by Russian WWR-M2 fuel assemblies (FAs) with 36% enrichment. The reconstructed reactor reached its initial criticality in November 1983 and attained it nominal power of 500 kW in February 1984. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 highly enriched uranium (HEU) FAs. The third fuel reloading by shuffling of HEU FAs was executed in June 2004. After the shuffling the working configuration of reactor core kept unchanged of 104 HEU FAs. The fourth fuel reloading was executed in November 2006. The 2 new HEU FAs were loaded in the core periphery, at previous locations of wet irradiation channel and dry irradiation channel. After reloading the working configuration of reactor core consisted of 106 HEU FAs. Contracts for reactor core conversion between USA, Russia, Vietnam and the International Atomic Energy Agency for Nuclear fuel manufacture and supply for DNRR and Return of Russian-origin non-irradiated highly enriched uranium fuel to the Russian Federation have been realized in 2007. According to the results of design and safety analyses performed by the joint study between RERTR Program at Argonne National Laboratory and Vietnam Atomic Energy Institute the mixed core configurations of irradiated HEU and new low enriched uranium (LEU) FAs has been created on 12 September, 2007 and on 20 July, 2009. After reloading in 2009, the 14 HEU FAs with highest burnup were removed from the core and put in the interim storage in reactor pool. The works on full core conversion for the DNRR are being realized in cooperation with the organizations, DOE and IAEA. Contract for Nuclear fuel manufacture and supply of 66 LEU FAs for DNRR

Russian RERTR program as a part of Joint US DOE-RF MINATOM collaboration on elimination of the threat connected to the use of HEU in research reactors

International Nuclear Information System (INIS)

Arkhangelsky, N.

2002-01-01

The Russian RERTR Program started at the end of 70's, the final goal of the program is to eliminate supplies of HEU in fuel elements and assemblies for foreign research reactors that were designed according to Russian projects. Basic directions of the work include: completion of the development of the fuel elements and assemblies on a basis of uranium dioxide; development of the fuel on a basis of U-Mo alloy; and development of pin type fuel elements. Fuel assemblies of WWR-M2 type with LEU were developed and qualified for using in foreign research reactors that use such type of fuel assemblies. These assemblies are ready for the supplying several operating foreign research reactors. There are more than 20 sites in Eastern European countries, former Soviet republics and another countries that have big amount of Russian origin HEU in fresh and spent fuel. The problem of the shipment of SNF from sites of research reactors is also very important for domestic Russian research reactors. More than ten years from its beginning the Russian RERTR program developed practically independently from the international RERTR program and only at the begin of 90's the Russian specialists started to contact with foreign scientists and the exchange of the scientific information has become more intensive. In September 1994, representatives of Minatom and DOE signed a protocol of intent to reduce an enrichment of uranium in research reactors. The main aspects of collaboration involve: Several domestic Russian research reactors such as WWR-M, IR-8 and others were investigated from the point of view of possibility of reducing of enrichment; financial support of the program from US DOE which is insufficient. The important part of international collaboration is the import of Russian origin spent and fresh fuel of research reactors to Russia. In August 2002 an impressive result of the Russian-American collaboration with support of IAEA and with the help and assistance of Yugoslavian side was

Neutron flux calculations for the Rossendorf research reactor in (hex)- and (hex,z)-geometry using SNAP-3D

International Nuclear Information System (INIS)

Koch, R.; Findeisen, A.

1986-04-01

The multigroup neutron diffusion theory code SNAP-3D has been used to perform time independent neutron flux and power calculations of the 10 MW Rossendorf research reactor of the type WWR-SM. The report describes these calculations, as well as the actual reactor configuration, some details of the code SNAP-3D, and two- and three-dimensional reactor models. For evaluating the calculations some flux values and control rod worths have been compared with those of measurements. (author)

Transient behaviour study program of research reactors fuel elements at the Hydra Pulse Reactor

International Nuclear Information System (INIS)

Khvostionov, V.E.; Egorenkov, P.M.; Malankin, P.V.

2004-01-01

Program on behavior study of research reactor Fuel Elements (FE) under transient regimes initiated by excessive reactivity insertion is being presented. Program would be realized at HYDRA pulse reactor at Russian Research Center 'Kurchatov Institute' (RRC 'K1'). HYDRA uses aqueous solution of uranyl sulfate (UO 2 SO 4 ) as a fuel. Up to 30 MJ of energy can be released inside the core during the single pulse, effective power pulse width varying from 2 to 10 ms. Reactor facility allows to investigate behaviour of FE consisting of different types of fuel composition, being developed according to Russian RERTR. First part of program is aimed at transient behaviour studying of FE MR, IRT-3M, WWR-M5 types containing meats based on dioxide uranium in aluminum matrix. Mentioned FEs use 90% and 36% enriched uranium. (author)

CIVIL ENGINEERING IN MOSCOW IN 1918–1921

Directory of Open Access Journals (Sweden)

Panteleeva Tatyana Leonidovna

2018-03-01

Full Text Available The scope of research: the scope of research is the engineering in Moscow in the first years after the October Revolution of 1917. Purpose: to determine what effect the economic policy of the Bolsheviks government had on the state of the civil engineering, how the central government’s orders were implemented in practice at the regional level. Materials and methods: the documents from the Central State Archives of Moscow are used, the methodology is based on the principles of historicism, objectivity, reliance on historical sources, analysis and presentation of the material used a problem-chronological method. Results: the study of concrete historical material allowed to give an objective description of the state of construction in Moscow in 1918–1921, to consider the structure, tasks and major activities of the Moscow Committee of State Structures. Data are given on the nature of the works performed, including the reconstruction of theatrical buildings, which can be used to further study the history of engineering and architecture of the Soviet period. Conclusions: the work of the Moscow Committee of State Structures was held in the conditions of acute shortage of material and human resources and was aimed at the gradual liquidation of private property and entrepreneurship in engineering. It was not possible to solve this problem completely, private construction cooperatives participated in the repair and reconstruction of public buildings. Particular attention was paid to the objects of education, health, social welfare and culture.

Status of Dalat research reactor and progress of new reactor plan in Vietnam

International Nuclear Information System (INIS)

Dien, Nguyen Nhi; Vien, Luong Ba

2005-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500-kW pool-type reactor loaded with the Soviet WWR-M2 Fuel Assemblies (FA), moderated and cooled by light water. The reactor was reconstructed from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The first criticality of the renovated reactor was achieved on 1 st November 1983, and then on 20 March 1984 the reactor was officially inaugurated and its activities restarted. During the last twenty years, the DNRR has played an important role as a large national research facility to implement researches and applications, and its utilization has been broadened in various fields of human life. However, due to the limitation of the neutron flux and power level, the out-of date design of the experimental facilities and the ageing of the reactor facilities, it cannot meet the increasing user's demands even in the existing utilization areas. In addition, the utilization demands of the Research Reactor (RR) will be increased along with the development of the nation's economy growth. In this aspect, it is necessary to have in Vietnam a new high performance multipurpose RR with a sufficient neutron flux and power level. According to the last draft of a national strategy for atomic energy development submitted to the Government for consideration and approval, it is expected that a new high power RR would be put into operation before 2020. The operation and utilization status of the DNRR is presented and some preliminary results of the national research project on new reactor plan for Vietnam are discussed in this paper

Text of the Moscow nuclear safety and security summit declaration Moscow, 19-20 April 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-04

As requested by the Resident Representatives to the International Atomic Energy Agency of France and the Russian Federation, the two States -Co-Chairmen of the summit meeting held in Moscow from 19-20 April 1996, the text of the Moscow Nuclear Safety and Security Declaration is being circulated.

Text of the Moscow nuclear safety and security summit declaration Moscow, 19-20 April 1996

International Nuclear Information System (INIS)

1996-01-01

As requested by the Resident Representatives to the International Atomic Energy Agency of France and the Russian Federation, the two States -Co-Chairmen of the summit meeting held in Moscow from 19-20 April 1996, the text of the Moscow Nuclear Safety and Security Declaration is being circulated

Radon Moscow: internationalisation of experience

International Nuclear Information System (INIS)

Nevejkin, P.P.; Grishin, O.E.; Rakov, S.M.

2011-01-01

Since the early 1990s, SIA Radon Moscow has been an active participant in the international technical cooperation to resolve the current issues of radiation safety and radwaste management. The article presents the experience of such cooperation. Examples of Radon's participation in the international projects on the assessment of safety, the international education network DISPONET and implementation of TACIS projects are given [ru

Experience in reactor research and development programs as educational system for thermohydraulic engineering

International Nuclear Information System (INIS)

Zaki, G.M.; Fikry, M.M.

1977-01-01

A reactor development program within a research reactor facility can be used for personnel training on the operation of power reactors and research in the different fields of nuclear science and engineering. A training program is proposed where reactor maintenance and operation, in addition to conducting development programs and executing projects, are utilized for forming specialized groups. The paper gives a short survey of a heat transfer program where out of pile and in-core studies are conducted along with two-phase flow investigations. This program covers the main requirements for WWR (water cooled and moderated reactor) power uprating and furnishes basic knowledge on power reactor thermal parameters. The major facilities for conducting similar programs devoted to education are mentioned

Exarh of the Bulgarian Church metropolitan Stephen and the Moscow Patriarchy

Directory of Open Access Journals (Sweden)

Kostriukov Andrei

2013-02-01

Full Text Available The article covers the last period of church-administrative activity of the Sofia’s metropolitan Stephаn (Shokov. The author describes the testimonies of contemporaries about the character and personal qualities of this ambiguous hierarch. In 1945–1948 metropolitan Stephan was the exarch of the Bulgarian Orthodox Church and participated in the Meeting of heads and representatives of Autocephalous Orthodox Churches in 1948. The author considers the circumstances of the dismissal of metropolitan Stephаn and his exile as especially important and interesting ones. The meeting of 1948 became the critical event in the exarch’s destiny. Being the supporter of ecumenism, metropolitan Stephen tried unsuccessfully to convince Patriarch Alexis of his rightness in order not to allow the condemnation of ecumenical contacts by the Moscow meeting. However Moscow looked on ecumenism differently in those days. In Moscow the Soviet management aspired to establishment of the centre of World Orthodoxy and tried to cite the Moscow Patriarchy against Constantinople that was under the influence of the USA and the Great Britain. As the Constantinople Patriarchy approved the ecumenical movement, the Moscow Patriarchy has been forced to take of an opposite position. Therefore, the participation of the Russian Church and Churches of the socialist countries in the ecumenical movement was impossible. Metropolitan Stephan, supporting the superiority of the Moscow Patriarchy in the World Orthodoxy, supported the active participation of all Local Churches in the ecumenical movement. The communistic management applied the maximum force to the exarch in order he has not made undesirable statements at the meeting. The fate of metropolitan Stephan has been decided after this meeting. In 1948 he was fired and exiled. The Moscow Patriarchy did not exclude the possibility of moving of metropolitan Stephаn to Russia and his location in any monastery. However metropolitan

Estimation of the outlooks for large-scale transmutation of fission-produced iodine

CERN Document Server

Galkin, B Y; Kolyadin, A B; Kocherov, N P; Lyubtsev, R I; Hosov, A A; Rimskij-Korsakov, A A

2002-01-01

To obtain data necessary for estimating sup 1 sup 2 sup 9 I transmutation efficiency in nuclear reactors the effective neutron capture cross section on sup 1 sup 2 sup 9 I isotope in neutral spectrum of the WWR-M reactor was determined. The calculated value of sup 1 sup 2 sup 9 I capture cross section, averaged by neutron spectrum in beryllium reflector of the WWR-M reactor, made up 17.8+-3.2 barn. On the basis of experimental data and estimations it was shown that in neutron flux 10 sup 1 sup 4 1/(cm sup 2 s) transmutation of iodine -129 loaded in the course of one year can amount to approximately 25%

Upgrading of Sergiev Posad department of Moscow NPO Radon

International Nuclear Information System (INIS)

Debieve, Pierre; Delecaut, Gregory; Vanleeuw, Daniel

2007-01-01

Available in abstract form only. Full text of publication follows: BELGATOM and IRE Consortium has been awarded by the European Commission end of 2005 to conduct a project entitled 'Upgrading of Sergiev Posad Department of Moscow NPO Radon and the assessment of the radiological impact in the area nearby'. The main aims to achieve in the frame of this Europe-aid Project are: - Improvement of the performance and the safety level of the present radwaste management system, taking into account the additional waste expected from the Kurchatov Institute rehabilitation and from the forecast decommissioning of Research Reactors on the territory of Moscow. - Basic design and assistance for the procurement of upgrading equipment related to: - radwaste sorting and pretreatment - replacement of the hydraulic system of the existing super-compactor - characterisation system for radwaste 'Support for preparing the PSAR and PEIAR for new licensing' Assessment of the radiological impact in an area of 50 km radius around Sergiev Posad Department. - The initial duration of this Project is 3 years, starting beginning of 2006. This paper describes the difficulties encountered to start and implement the Project and its status at the half of the planned time schedule. (authors)

The activity of Moscow Engineering Physics Institute

International Nuclear Information System (INIS)

Levedev, L.

1994-01-01

Various information about Moscow Engineering Physics Institute (MEPhI) structure and scientific activity are discussed. The four main faculties of MEPhI: the faculty of theoretical and experimental physics, the faculty of technical physics, the faculty of automatics and electronics and the faculty of cybernetics are being written in this report. The information about the research reactors and the scientific research laboratories is also presented. The participation of MEPhI in the state scientific technological programs such as 'High energy physics', 'High-temperature superconductivity', 'Controlled thermonuclear synthesis and plasma processes'. 'Informatization', 'Security of population and industrial objects on account of hazard of natural and technogenic accidents', 'Ecology of Russia', 'Synchrotron radiation and its application', 'Future technologies, machines and productions' and others are presented too. (author)

Moscow University professor M. S. Korelin and student movement at the Moscow University in the late 19 th century (according to the diary

Directory of Open Access Journals (Sweden)

N. ILYASHENKO

2014-02-01

Full Text Available The article examines the attitude of the Moscow University Professor M. S. Korelin to the student movement. Analysis of the views of Korelin is made on the basis of nonpublished diary of Professor, which preserved in the Central State archive of Moscow. Actually Korelin considers the student activity during the period (1889—1896 of the particularly interesting from the point of view of the formation of the student movement in Russia. The author comes to the conclusion that Korelin held an active position in relations with youth, sought to get closer acquainted with the students, to find a contact with them, and common interests, to understand their environment. Using the trust part of the students he could learn more about the life and the essence of illegal student corporations. sympathizing with noble motives students fight against immorality — Korelin rejected terroristic methods of struggle. However, he believed that the unifying factor for professors and students can only be established in the scientific activity. Korelin points out that the cause of the student movement was the University Law of 1884 which made the administration of the University powerless against the student movements. The analysis of the views of Korelin allows to expand the idea of relationship between professors and students of that time, provides new information on the history of the student movement in Russia and about the history of the faculty-student relationships in the end of XIX century.

Deadlock Before Moscow

National Research Council Canada - National Science Library

Roncero, Matias

2001-01-01

This Strategy Research Project intents to offer not a new interpretation of the decisive Battle of Moscow during World War Two, but rather a evaluation of German strategies, their success or failure...

New reactor type proposed

CERN Multimedia

2003-01-01

"Russian scientists at the Research Institute of Nuclear Power Engineering in Moscow are hoping to develop a new reactor that will use lead and bismuth as fuel instead of uranium and plutonium" (1/2 page).

Anthropogenic heat fluxes over Moscow agglomeration and other Russian and world cities

Science.gov (United States)

Belova, Iya; Ginzburg, Alexander

2010-05-01

]. References: Ginzburg A., Raspletina N. Anthropogenic heat fluxes estimation for metropolitan areas and urban regions // Geophysical Research Abstracts of EGU General Assembly 2008, Vol. 10, EGU2008-A -02526; SRef-ID: 1607-7962/gra/EGU2008-A-02526. The 2009 Little Green Data Book. 2009. World Bank. Russian regions: Basic city socio-economic indexes. 2008 Statistical digest. Moscow. Rosstat. 2008. 375 p. Martynov A.S., Artyukhov V.V., Vinogradov V.G. Web-atlas: Environment and health of population of Russia. 1997. http://www.sci.aha.ru/ATL/ra32b.htm. Ginzburg A.S., D.P. Gubanova, V.M. Minashkin. 2009. Influence of natural and anthropogenic aerosols on global and regional climate. Russian Journal of General Chemistry, Volume 79, Number 9, pp. 2062-2070.

Twelfth night of 1917 and the Moscow art theatre Twelfth night of 1917 and the Moscow art theatre

Directory of Open Access Journals (Sweden)

Arkady Ostrovsky

2008-04-01

Full Text Available On 15 September, 1917, in a letter to Nemirovich-Danchenko, Stanislavsky renounced the stage of the Moscow Art Theatre: I cannot think about any other roles, because I will never be able to do anything, at least in the Moscow Art Theatre. Maybe in some other area or some other place I will be able to rise. Of course I do not mean in other theatres, but in the studios. Othello — free!...1 After the tragedy Stanislavsky had endured with Selo Stepanchikovo, he threw himself into Studio work. He started rehearsing Twelfth Night, a play he had put on at the Society of Art and Literature in 1897. The Studio production of Twelfth Night was played on 25 December 1917, two months to the day after the Revolution. A few months later, Nikolai Efros published a book about the First Studio. It was dedicated to The Cricket on the Hearth but the words Efros used to describe the atmosphere in which Dickens’s production had opened were equally suitable for Twelfth Night: ‘You remember what sort of days those were? On 15 September, 1917, in a letter to Nemirovich-Danchenko, Stanislavsky renounced the stage of the Moscow Art Theatre: I cannot think about any other roles, because I will never be able to do anything, at least in the Moscow Art Theatre. Maybe in some other area or some other place I will be able to rise. Of course I do not mean in other theatres, but in the studios. Othello — free!...1 After the tragedy Stanislavsky had endured with Selo Stepanchikovo, he threw himself into Studio work. He started rehearsing Twelfth Night, a play he had put on at the Society of Art and Literature in 1897. The Studio production of Twelfth Night was played on 25 December 1917, two months to the day after the Revolution. A few months later, Nikolai Efros published a book about the First Studio. It was dedicated to The Cricket on the Hearth but the words Efros used to describe the atmosphere in which Dickens’s production had opened

The feasibility of using a Fourier RTOF spectrometer at a low-power research reactor

International Nuclear Information System (INIS)

Maayouf, R.M.A.; Priesmeyer, H.G.; Kudryashev, V.A.

1991-01-01

The present situation of Fourier time-of-flight (TOF) spectrometry is discussed using the FSS spectrometer as example. The use of the Fourier reverse TOF spectrometry, as an efficient tool for studying condensed matter, at a 2 MW (WWR-S type) reactor is also assessed. The arrangement of the RTOF spectrometer, which could be successfully used at such type of reactor, is introduced. The suggested arrangement applies a neutron guide tube of 24 m length and allows for effective luminosity 2.4.10 6 at a flight path distance of 3.6 m. The number of neutrons scattered from a sample (5 cm 3 in volume) and incident on the detector system, as estimated for the suggested arrangement, is ∝1.6.10 3 n/sec. Such high counting rate allows to measure a diffraction spectrum within less than an hour. (orig.) With 12 figs [de

Fungal diseases of tree stands under urbanized conditions of Moscow

Directory of Open Access Journals (Sweden)

Smirnova Oksana G.

2013-01-01

Full Text Available Phytosanitary and ecological estimation of tree-stands has been con­ducted at the Forest Experimental Station of Moscow Agricultural Academy and parks of Northeast of Moscow in 2007-2011. Fomes fomentarius was proved to be a very serious pathogen of trees under conditions of Moscow, Piptoporus betulinus, Phellinus igniarius, and Fomitopsis pinicola also occurred and caused damage to trees. This rather bad phytosanitary situation depends on alarming ecological situation in Moscow. At the Forest Experimental Station of Moscow Agricultural Academy a number and cover of lichens decreased. In general, all trees in Moscow are in dynamic equilibrium with the urbanized environment. In connection with this, the following classification of tree-stands was proposed for the urbanized environment: 1 - healthy trees, 2 - affected trees which can be managed, 3 - dry woods, 3a - very diseased. Many tree-stands in investigated regions of Moscow are found to belong to the groups 2 and 3c. All tree-stands must be carefully monitored and managed in order to provide a well-timed decision on the support system for preservation of trees as ‘lungs of city’ and avoid unpredictable tree falling which put people and traffic at risk.

The Battle of Moscow - Turning Point of World War II

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V M Falin

2015-12-01

Full Text Available The article is dedicated to the Battle of Moscow in October- December, 1941. Author analyzes the causes of the failure of German army, who tries to encircle and capture Moscow, the events taking place on the outskirts of Moscow, German troops attempts to encircle Moscow. The author presents data on the speech by Adolf Hitler in Berlin on October 5, 1941, in which he acknowledged the failure of the Blitzkrieg and the Battle for Moscow and its suburbs. The researcher uses the documents of the Wehrmacht High Command, which stated that after the Battle of Moscow, German troops could not on any further stage of the war to restore the quality and morale of the armed forces, with whom Reich rushed to a campaign for world domination. The author, a prominent public and political figure of the USSR, also relies on personal recollections, interviews with prominent generals of World War II, including I. Konev.

Spatial Structure of Modern Moscow

Directory of Open Access Journals (Sweden)

Daria V. Goloukhova

2015-01-01

Full Text Available The article is focused on the spatial structure of modern Moscow and features distinguishing it from the cities of Western Europe and the US. The city has hybrid spatial structure combining elements which emerged on different stages of the city development. In the 14th century two tendencies appeared: the prestige of the city centre and opposition of Western districts as more prestigious to Eastern districts as less prestigious. Crucial spatial characteristics emerged in the Soviet era and up to now they define the image of Moscow. Firstly, it's a peculiar density profile. Population density in post-socialist cities tends to increase as we move further from the city centre while in Western European cities population density is the highest in central districts. Secondly, elementary units of Moscow spatial structure are so called micro-districts (neighbourhoods. The concept of a microdistrict was very popular with Soviet urban planners and widely applied in the residential construction. Another peculiarity of Moscow spatial structure is social heterogeneity of districts and absence of ethnic quarters or ghettos. Furthermore, significant part of the city area is occupied by former industrials zones which are not used anymore and need to be reconstructed. With transition to market economy a number of spatial changes emerged. They were partly related to the large-scale privatization, infill construction and lack of effective urban planning policy. In conclusion the article states the need for the new model of spatial organization which would take into account the specifics of Russian reality.

Neutron spectra measurements and neutron flux monitoring for radiation damage purposes

International Nuclear Information System (INIS)

Osmera, B.; Petr, J.; Racek, J.; Rumler, C.; Turzik, Z.; Franc, L.; Holman, M.; Hogel, J.; Kovarik, K.; Marik, P.; Vespalec, R.; Albert, D.; Hansen, V.; Vogel, W.

1979-09-01

Neutron spectra were measured for the TR-0, WWR-S and SR-0 experimental reactors using the recoil proton method, 6 Li spectrometry, scintillation spectrometry and activation detectors in a variety of conditions. Neutron fluence was also measured and calculated. (M.S.)

Aspects of intellectual property related to the TRIGA reactor in Romania

International Nuclear Information System (INIS)

Chirita, Ion

2008-01-01

Full text: A TRIGA - type research reactor has been operating in Pitesti since 1979. In Romania, the first research reactor - of the WWR-C type - has been operating since 1957. Both these reactors have contributed to the formation of well - trained specialists, whose works constitute an important intellectual and industrial property. Institute for Nuclear Research (formerly INT, then INPR) is the holder of several published patents, such as: Procedure for decontamination of water and primary circuits of irradiation devices; Reconditioning of ion exchangers; Nozzle for flow water gaugers; Oscillating electromagnetic pump; Facility for determining nuclear fuel burnup; Portable monitor for contamination measurements; Cable joints with biological protection; Anti-seismic and thermal connection; Automatic facility for nuclear fuel irradiation testing; Method for determining power distribution specific for research rector fuel elements; Tight end-fittings; Cooling damage facility, etc. Many of these have been applied or can be applied to reactors of the TRIGA family or are already installed or under installation to research reactors of other types. (authors)

Jakub Sobieski’s Description of the Moscow Campaign (based on the Diariusz ekspedycyjej moskiewskiej dwuletniej królewica Władysława Anno Domini 1617 [The Diary of the Two-Year Moscow Campaign by Royal Prince Władysław in 1617

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Piotr Borek

2013-01-01

Full Text Available The essay discusses Jakub Sobieski’s diaries and memories, which belong to the finest specimens of such writing in Polish Baroque. The diary and memoirs of the Moscow campaign of 1617-1618 have survived in only a few copies, with the most important ones in Biblioteka Czartoryskich in Cracow. Reconstruction of Prince Władysław’s struggle for the Russian crown is mostly based on a handwritten testimony called Diariusz ekspedycyjej moskiewskiej dwuletniej królewica Władysława A. D. 1617 [The Diary of the Two-Year Moscow Campaign by Royal Prince Władysław in 1617]. The events described in the diary span from April 5th, 1617 to December 28th, 1618. The author has arranged the material chronologically, focusing on the text as historical evidence. The conclusion of the text, where Sobieski quotes a fragment of Tacitus’s Annals, points out to the argumentative function of the work, which was supposed to explain to Poles (the king, the sejm and senate, the nobility that commissaries were right in signing the Truce of Deulino, regarding the safety of the homeland threatened by Turks and Tatars, and the budgetary difficulties of the Crown and Lithuania. The second work by Sobieski is more of a Baroque memoir, composed as a temporal sequence (some fragments have the structure of diary. The author reconstructs the events of the Moscow campaign, beginning with the death of tsar Ivan the Terrible (1584, and leads the narrative to the end of 1618, when the Truce of Deulino. The work is characterized by greater coherence in presentation of facts, their selection, and a more general point of view, pointing out to the failure of Polish dynastic policy. Sobieski seems to be critical of the Polish intervention and the Polish raison d’état in this respect. He is also critical of the young prince’s campaign of 1617-1618; he was a commissioner for treaties with Moscow during the campaign.

Investigation of material removal rate (MRR) and wire wear ratio (WWR) for alloy Ti6Al4 V exposed to heat treatment processing in WEDM and optimization of parameters using Grey relational analysis

International Nuclear Information System (INIS)

Altug, Mehmet

2016-01-01

The study examines the changes of the microstructural, mechanical and conductivity characteristics of the titanium alloy Ti6Al4 V as a result of heat treatment using wire electrical discharge machining, and their effect on machinability. By means of optical microscopy and scanning electron microscopy (SEM), analyses have been performed to determine various characteristics and additionally, microhardness and conductivity measurements have been conducted. Material removal rate (MRR) and wire wear ratio (WWR) values have been determined by using L18 Taguchi test design. The microstructures of the samples have been changed by thermal procedures. Results have been obtained by using the Grey relational analysis (GRA) optimization technique to solve the maximum MRR and minimum WWR values. The best (highest) MRR value is obtained from sample E which was water quenched in dual phase processing. The microstructure of this sample is composed of primary α and α' phases. The best (lowest) WWR value is obtained from sample A.

Investigation of material removal rate (MRR) and wire wear ratio (WWR) for alloy Ti6Al4 V exposed to heat treatment processing in WEDM and optimization of parameters using Grey relational analysis

Energy Technology Data Exchange (ETDEWEB)

Altug, Mehmet [Inonu Univ., Malatya (Turkey). Dept. of Machine and Metal Technologies

2016-11-01

The study examines the changes of the microstructural, mechanical and conductivity characteristics of the titanium alloy Ti6Al4 V as a result of heat treatment using wire electrical discharge machining, and their effect on machinability. By means of optical microscopy and scanning electron microscopy (SEM), analyses have been performed to determine various characteristics and additionally, microhardness and conductivity measurements have been conducted. Material removal rate (MRR) and wire wear ratio (WWR) values have been determined by using L18 Taguchi test design. The microstructures of the samples have been changed by thermal procedures. Results have been obtained by using the Grey relational analysis (GRA) optimization technique to solve the maximum MRR and minimum WWR values. The best (highest) MRR value is obtained from sample E which was water quenched in dual phase processing. The microstructure of this sample is composed of primary α and α' phases. The best (lowest) WWR value is obtained from sample A.

Experience of work with radioactive materials and nuclear fuel at the reactor WWR-K

International Nuclear Information System (INIS)

Maltseva, R.M.; Petukhov, V.K.

1998-01-01

In the report there are considered questions concerning the handling with fresh and spent fuel, experimental devices, containing high enriched uranium, being fissile materials of the bulk form, radioisotopes, obtained in the reactor, and radioactive waste, formed during the operation of the reactor, and organization of storage, account and control of radioactive and fissile materials is described. (author)

CONTROLLING STREET DOG POPULATION IN MOSCOW

OpenAIRE

ZHULENKO A.S.; POLYNOVA G.V.

2016-01-01

The issue represents the analysis of the fundamentals and world-wide best practices of controlling street dog population in Moscow and other global cities. Actions proposed to improve the strategy of managing free-ranging dogs in Moscow.Some reasons of increase in number of stray dogs and “pet overpopulation” ware studied. There are ecological types of stray dogs characterized the types of running wild of dogs and foraging (food procurement) strategy of animals.The analysis of the basic princ...

DPT Researchers’ Visit to Moscow

DEFF Research Database (Denmark)

Singla, Rashmi; Popova, Margarita

2018-01-01

to three colleagues from MSUPE. Our staff members’ presentations focused on presenting Problem-oriented Project Learning and group work, RUC’s Social Psychology of Everyday Life study program, as well as research on diversity, migration and cross-cultural psychology in the joint seminars with MSUPE staff......Four researchers from our department (DPT/IMT) Hans S. Andersen, Margarita Popova, Niklas Chimmiri & Rashmi Singla spent five intellectually, geographically and socially stimulating days at Moscow State University of Psychology and Education (MSUPE), as part of an Erasmus+ staff knowledge exchange...... visit. Conceptually grounded discussions of psychological and educational research projects building on the Cultural-Historical School of Psychology, founded in Russia (L. S. Vygotsky, A. N. Leontiev, A. R. Luria), formed the main framing for the visit. In April 2017, RUC had already acted as host...

Research of heat releasing element of an active zone of gaseous nuclear reactor with pumped through nuclear fuel - uranium hexafluoride (UF6)

International Nuclear Information System (INIS)

Batyrbekov, G.; Batyrbekov, E.; Belyakova, E.; Kunakov, S.; Koltyshev, S.

1996-01-01

The purpose of the offered project is learning physics and substantiation of possibility of creation gaseous nuclear reactor with pumped through nuclear fuel-hexafluoride of uranium (Uf6).Main problems of this work are'. Determination of physic-chemical, spectral and optical properties of non-equilibrium nuclear - excited plasma of hexafluoride of uranium and its mixtures with other gases. Research of gas dynamics of laminar, non-mixing two-layer current of gases of hexafluoride of uranium and helium at availability and absence of internal energy release in hexafluoride of uranium with the purpose to determinate a possibility of isolation of hexafluoride of uranium from walls by inert helium. Creation and research of gaseous heat releasing element with pumped through fuel Uf6 in an active zone of research nuclear WWR-K reactor. Objects of a research: Non-equilibrium nuclear - excited plasma of hexafluoride of uranium and its mixtures with other gases. With use of specially created ampoules will come true in-reactor probe and spectral diagnostics of plasma. Calculations of kinetics with the account of main elementary processes proceeding in it, will be carried out. Two-layer non-mixed streams of hexafluoride of uranium and helium at availability and absence of internal energy release. Conditions of obtaining and characteristics of such streams will be investigated. Gaseous heat releasing element with pumped through fuel - Uf6 in an active zone of nuclear WWR-K reactor

Mary Poppins and the Soviet Pilgrimage: P.L.Travers's Moscow Excursion (1934

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John McNair

2013-02-01

Full Text Available Like the journey it chronicles, Moscow Excursion, P.L.Travers’s account of her 1932 visit to Russia, was in part inspired by the genre it effectively parodies: the ‘Soviet pilgrimage’ ‘truth about Russia’ narrative characteristic of the Stalin decades and exemplified (in the Australian context by Katharine Susannah Prichard’s The Real Russia, also published in 1934. The paper examines the ways in which Travers’s book is written against this genre to produce an avowedly ‘un-political’ record whose narrator rejects the restrictions of organized travel, and whose idiosyncratic and critical observations on Soviet reality contrast with the admiration of her more orthodox fellow-travellers for the usual showcase institutions on the official itinerary. At the same time, it is argued that in its blend of self-deprecating irony, whimsy and disillusioned idealism Moscow Excursion suggests parallels with Travers’s personal quest for ‘the truth’ and even with Mary Poppins, published only two months later.

Sanitary-epidemiological assessment of quality of atmospheric air in Moscow

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E.E. Andreeva

2016-12-01

Full Text Available The results of the comparative assessment of the sanitary and epidemiological quality of the ambient air in Moscow and the Russian Federation, that demonstrate a decrease of the air pollution level in 2014 in comparison with 2012, both in Moscow and in the Russian Federation, are presented in this study. It has been noted that most of the excess of hygienic air quality standards in the areas of Russian cities are recorded on stationary observation stations situated close to the motorway, located in residential areas, and in Moscow – in the zones of industrial enterprises’ impact. It has been revealed that the tendency to the reduction of the negative impact from industrial enterprises on air pollution is registered in the whole of the Russian Federation and in Moscow. It is demonstrated that the high-priority contaminating agents, the content of which for the year 2014 in the Russian Federation exceeded the hygienic daily average standards in 5 and more times, are mainly: benzo (a pyrene, suspended substances, sulfur dioxide, benzene, formaldehyde, nitrogen dioxide, hydrogen sulfide, etc. To assess the quality of the ambient air in Moscow, the method of "inverse distance" and inter- and extrapolation of the data obtained from the observation stations on the whole territory of Moscow has been used. The study shows that the air quality of the individual administrative districts of Moscow varies considerably, and is determined by the traffic load level as well as by the volume of emissions of the industrial enterprises and the wind rose. As high-priority contaminating agents affecting the air quality, nitrogen dioxide, ammonia, benzene, suspended substances, ozone and formaldehyde are distinguished. It is noted that close to the highway near Moscow there is an excessive concentration of nitrogen dioxide, formaldehyde, phenol, and carbon monoxide, and in areas close to industrial zones – nitrogen dioxide, phenol formaldehyde and benzo (a

Vitamin D Insufficiency in Adolescents: Results of Year-Round Screening in Moscow

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I. N. Zakharova

2015-01-01

Full Text Available Goal. Study of vitamin D sufficiency in children of puberty and pre-puberty age in Moscow. Methods. We examined children aged from 10 to 17 years living in Moscow. In order to appraise seasonal changes in the blood vitamin D status, we determined the average level of the main vitamin D metabolite — 25(OHD — in different months of the year. The criteria for involving children into a laboratory examination were age (11–17 years, absence of organic or genetic pathology, permanent residence in Moscow, no intake of calcium and active vitamin D metabolite preparations at the time of examination. Results. The study involved 360 children (i. e. 30 children were examined every month aged from 10 to 17 years. Analysis of the obtained data demonstrated differences in vitamin D sufficiency in the examined children in winter, spring, summer and autumn months. The serum concentration of vitamin D was significantly higher in summer months than in winter months. We did not reveal sex-related differences in vitamin D sufficiency among Moscow adolescents. Diet evaluation demonstrated that children extremely rarely consume fish as the main food source of vitamin D. Conclusions. Special attention should be given to the development of effective methods of correction of low vitamin D status and prevention thereof. Maintenance of the optimal vitamin D status in winter is infeasible due to insufficient exposure to sunlight, short duration of children’s walking during the schoolyear and absence of cholecalciferol sources in children’s diets. Special attention should be given to vitamin D intake by means of prescribing enriched food additives. 

Moscow Theatre 1935 and 1970: This Is Where I Came In

Science.gov (United States)

Houghton, Norris

1971-01-01

Compares findings of what is happening in Russian theatre today with what was being done in the 30's. Particularly discusses the work of Georgi Tovstonogov, Director of the Gorki Theatre in Leningrad, and Yuri Liubimov, Director of the Taganka Theatre in Moscow. (RB)

Hygienic characteristics of the priority environmental media and risk assessment of their influence: case study in Moscow city

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Е.Е. Andreeva

2015-12-01

Full Text Available On the base of the comparison of pollutional indexes in the environmental media of the Russian Federation and Moscow city the priority pollutants in ambient air and in water from centralized drinking water supply of Moscow have been established. A hygienic study of the population in Moscow was conducted to assess health risk related to chemical pollution of the ambient air and water from the systems of the centralized drinking water supply. The results of hygienic characteristics of the habitat’s pollution and health risk assessment among the population in Moscow have revealed that the priority risk factors negatively effecting the population are: benzene, nitrogen dioxide, weighed substances, formaldehyde, nitrogen oxide, ozone – for ambient air, and also arsenic and chrome (IV – for water from the systems of the centralized drinking water supply.

IMPROVING SYSTEMS OF POWER COLLECTION OF THE MOSCOW MONORAIL TRANSPORT SYSTEM

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O. A. Sydorov

2010-01-01

Full Text Available The disadvantages of existing current collection system for the Moscow monorail transport system are considered in the article. A new system differing in the contact geometry is proposed. Also the calculation of interaction of the offered current collection system based upon the Lagrange’s equations of second kind.

Assessment of structural materials inside the reactor pool of the Dalat research reactor

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Luong Ba Vien; Nguyen Minh Tuan; Trang Cao Su

2010-01-01

Originally the Dalat Nuclear Research Reactor (DNRR) was a 250-kW TRIGA MARK II reactor, started building from early 1960s and achieved the first criticality on February 26, 1963. During the 1982-1984 period, the reactor was reconstructed and upgraded to 500kW, and restarted operation on March 20, 1984. From the original TRIGA reactor, only the pool liner, beam ports, thermal columns, and graphite reflector have been remained. The structural materials of pool liner and other components of TRIGA were made of aluminum alloy 6061 and aluminum cladding fuel assemblies. Some other parts, such as reactor core, irradiation rotary rack around the core, vertical irradiation facilities, etc. were replaced by the former Soviet Union's design with structural materials of aluminum alloy CAV-1. WWR-M2 fuel assemblies of U-Al alloy 36% and 19.75% 235 U enrichment and aluminum cladding have been used. In its original version, the reactor was setting upon an all-welded aluminum frame supported by four legs attached to the bottom of the pool. After the modification made, the new core is now suspended from the top of the pool liner by means of three aluminum concentric cylindrical shells. The upper one has a diameter of 1.9m, a length of 3.5m and a thickness of 10mm. This shell prevents from any visual access to the upper part of the pool liner, but is provided with some holes to facilitate water circulation in the 4cm gap between itself and the reactor pool liner. The lower cylindrical shells act as an extracting well for water circulation. As reactor has been operated at low power of 500 kW, it was no any problem with degradation of core structural materials due to neutron irradiation and thermal heat, but there are some ageing issues with aluminum liner and other structures (for example, corrosion of tightening-up steel bolt in the fourth beam port and flood of neutron detector housing) inside the reactor pool. In this report, the authors give an overview and assessment of

Russian research reactor fuel return program starts shipping fuel to Russia

International Nuclear Information System (INIS)

Dedik, T.; Bolshinsky, I.; Krass, A.

2003-01-01

For almost four years the United States (U.S), the Russian Federation (R.F.), and the International Atomic Energy Agency (IAEA) have been discussing an initiative to return Soviet/Russian-origin research reactor fuel to the Russian Federation. In a series of bilateral and trilateral meetings in Vienna and Moscow, considerable progress has been made toward defining the Russian Research Reactor Fuel Return Program as well as obtaining the necessary technical data to facilitate the return. More than 20 research reactors in 17 countries that have Soviet- or Russian-supplied fuel have identified. Most of these reactors have stocks of both fresh and irradiated HEU fuel that must be carefully stored and managed for many years to come. On September 21, 2003 the Russian Research Reactor Fuel Return program shipped 14 kg of fresh Russian-origin HEU fuel from Romania to the nuclear fuel fabrication facility in Russia, which represented the beginning of the practical implementation of the program. (author)

Main results and status of the development of LEU fuel for Russian research reactors

International Nuclear Information System (INIS)

Vatulin, A.; Morozov, A.; Suprun, V.; Dobrikova, I.

2005-01-01

VNIINM develops low enrichment uranium (LEU) fuel on base U-Mo alloys and a novel design of pin-type fuel elements. The development is carried out both for existing reactors, and for new advanced designs of reactors. The work is carried on the following main directions: - irradiate LEU U-Mo dispersion fuel (the uranium density up to 6,0 g/cm 3 ) in two Russian research reactors: MIR (RIAR, Dimitrovgrad) as pin type fuel mini-elements and in WWR-M (PINP, Gatchina) within full-scaled fuel assembly (FA) with pin type fuel elements; - finalize development of design and fabrication process of IRT type FA with pin type fuel elements; - develop methods of reducing of U-Mo fuel --Al matrix interaction under irradiation; - develop fabricating methods of fuel elements on base of monolithic U-Mo fuel. The paper generally reviews the results of calculation, design and technology investigations accomplished by now. (author)

Children's Infectious Disease in Moscow: Problems and Solutions

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L. N. Mazankova

2016-01-01

Full Text Available Based on statistical data, a comparative analysis of infectious morbidity and mortality in Moscow in 2015 and 2014 revealed a whole, the decline in these indicators. Made significant progress in reducing infectious morbidity in Moscow due to the vaccination of children, including — increased regional calendar of preventive vaccinations. However, analysis of the work of medical institutions indicates the feasibility of the development and introduction of technologies of management of patients with post-infectious syndromes, as well as improving the health care system for children with infectious diseases based on a multidisciplinary approach in close cooperation infectious disease and pediatricians of different specialties. To solve these problems is proposed a plan to improve the effectiveness of children's infectious diseases services relating to the reorganization of hospital beds and outpatient care, ensure the continuity of the different health facilities, implementation of modern methods of etiological diagnosis of infections, the organization of continuous vocational training of paediatricians in Moscow on a specialty «Infectious diseases».

Mo-99 production on a LEU solution reactor

International Nuclear Information System (INIS)

Brown, R.W.; Thome, L.A.; Khvostionov, V.Y.

2005-01-01

A pilot homogenous reactor utilizing LEU has been developed by the Kurchatov Institute in Moscow along with their commercial partner TCI Medical. This solution reactor operates at levels up to 50 kilowatts and has successfully produced high quality Mo-99 and Sr-89. Radiochemical extraction of medical radionuclides from the reactor solution is performed by passing the solution across a series of inorganic sorbents. This reactor has commercial potential for medical radionuclide production using LEU UO 2 SO 4 fuel. Additional development work is needed to optimize multiple 50 kilowatt cores while at the same time, optimizing production efficiency and capital expenditure. (author)

Analyses for inserting fresh LEU fuel assemblies instead of fresh HEU fuel assemblies in the Dalat Nuclear Research Reactor in Vietnam

International Nuclear Information System (INIS)

Hanan, N. A.; Deen, J.R.; Matos, J.E.

2005-01-01

Analyses were performed by the RERTR Program to replace 36 burned HEU (36%) fuel assemblies in the Dalat Nuclear Research Reactor in Vietnam with either 36 fresh fuel assemblies currently on-hand at the reactor or with LEU fuel assemblies to be procured. The study concludes that the current HEU (36%) WWR-M2 fuel assemblies can be replaced with LEU WWR-M2 fuel assemblies that are fully-qualified and have been commercially available since 2001 from the Novosibirsk Chemical Concentrates Plant in Russia. The current reactor configuration using re-shuffled HEU fuel began in June 2004 and is expected to allow normal operation until around August 2006. If 36 HEU assemblies each with 40.2 g 235 U are inserted without fuel shuffling over the next five operating cycles, the core could operate for an additional 10 years until June 2016. Alternatively, inserting 36 LEU fuel assemblies each containing 49.7 g 235 U without fuel shuffling over five operating cycles would allow normal operation for about 14 years from August 2006 until October 2020. The main reason for the longer service life of the LEU fuel is that its 235 U content is higher than the 235 U content needed simply to match the service life of the HEU fuel. Fast neutron fluxes in the experiment regions would be very nearly the same in both the HEU and LEU cores. Thermal neutron fluxes in the experiment regions would be lower by 1-5%, depending on the experiment type and location. (author)

Moscow City Telephone Network

Science.gov (United States)

1976-12-23

CONTENTS PAGE FOREWORD 1 I. INTRODUCTION 2 II. 1881-1901. The Bell Society Concession h III. 1901-1918. The Concession...concerning the work. Readers should send their letters to Svyaz’izdat Press (Moscow, Kirov Street, 40). The Authors I. INTRODUCTION In 1876, Graham Bell... sweatshop conditions of labor. Whereas earlier, under the concessioners, operators were forbidden to marry, and pregnancy was grounds for immediate

Towards the Story of the Parishes’ Reunion of the West European Exarchate with the Moscow Patriarchy in Post-War Years (1945–1946

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Kostriukov Andrei

2014-12-01

Full Text Available The article covers the circumstances of the consolidation of parishes of Russian tradition in the West European exarchate with the Moscow Patriarchy in 1945. The author has analyzed the subsequent circumstances that assisted the parties with the rupture of relations in 1946. On the basis of the documents the author has drawn the conclusion about the primary fragility of the first consolidation that was hasty made, nonmetering specific jurisdictional features of the West European exarchate. Serious problems on the way to unity have arisen in August, 1945, when the representative of the Moscow Patriarchy, metropolitan Nicolay (Jarushevich, had arrived to Paris. Objections against the consolidation have run as follows: the Church in the USSR continued to be in enslavement by the atheistic government. Despite the arguments of association’s opponents, metropolitan Evlogy has agreed to be the part of the Moscow Patriarchy. The next months the positions of the opponents have become stronger because of metropolitan Evlogy who remained the exarch of both Ecumenical and Moscow Patriarchs. In February, 1946 at the ceremony of ordination, bishop Nikon (Greve has sworn not to Moscow, but to the Constantinople patriarch. The decree of the Presidium of the Supreme council of the USSR from June, 14th, 1945 about citizenship that was granted to Russian emigrants in France became the serious strike on the unity. In the Exarchate the delimitation between those who has accepted the Soviet citizenship and those who has refused has begun. Thus the diocesan council, being afraid of freedom’s infringement, prepared a soil for the future separation from the Moscow Patriarchy. In July, 1946 the diocesan council made the memorandum that the policy of the further rapprochement with the USSR and the Moscow Patriarchy threatened the Exarchate with split. After metropolitan Evlogy’s death the division became the accomplished fact.

U.S. and foreign breeder reactors

International Nuclear Information System (INIS)

Hill, E.H.

1977-01-01

The running battle between Congress and the Administration over the Clinch River Breeder Reactor Plant (CRBRP) Project has provoked an increased interest in domestic and foreign breeder reactor programs. Perhaps an understanding of the history of breeders here and abroad will serve to place the CRBRP in perspective and allow some analysis of how the U.S. appears on the global canvas. Breeder reactor technology has, for the most part, settled down to concentration on the liquid metal fast breeder reactor (LMFBR). This is the result of 32 years of experience with reactors employing a fast neutron flux and even longer experience with liquid metal coolants. However, a number of U.S. utilities are sponsoring a gas cooled fast reactor program as an alternative technology to the LMFBR. This development program is supported by the U.S. Department of Energy

Radiation protection planning for decommissioning of research reactor facilities

International Nuclear Information System (INIS)

Jackson, Roger; Harman, Neil; Craig, David; Fecitt, Lorna; Lobach, Yuri; Gorlinskij, Juri; Kolyadin, Vyacheslav; Pavlenko, Vytali

2008-01-01

The MR reactor at the Russian Research Centre Kurchatov Institute (RRCKI), Moscow was a 50 MW multipurpose material testing and research reactor equipped with nine experimental loop facilities to test prototype fuel for various nuclear power reactors being developed. The reactor was shut down in 1993 and de-fuelled. The experimental loops are located in basement rooms around the reactor. The nature of the research into the characteristics of fuel design and coolant chemistry resulted in fission products and activation products in the test loop equipment. Decommissioning of the loops therefore presents a number of challenges. In addition the city of Moscow has expanded such that the RRC KI is now surrounded by housing which had to be taken into account in the radiological protection planning. This paper describes the techniques proposed to undertake the dismantling operations in order to minimise the radiation exposure to workers and members of the public. Estimates have been made of the worker doses which could be incurred during the dismantling process and the environmental impacts which could occur. These are demonstrated to be as low as reasonably achievable. The work was funded by the UK Department of Business Enterprise and Regulatory Reform (DBERR) (formerly the Department of Trade and Industry) under the Nuclear Safety Programme (NSP) set up to address nuclear safety issues in the Former Soviet Union. (author)

[A large-scale epidemic of diphtheria in Moscow in recent years: patterns of development].

Science.gov (United States)

Chistiakova, G G; Filatov, N N; Korzhenkova, M P; Solodovnikov, Iu P; Lytkina, I N; Maksimova, N M; Markina, S S

2001-01-01

Data on the dynamics of diphtheria morbidity in Moscow in 1958-1999 are presented. The last epidemic which started at the end of the 1980s and reached its peak in 1994, giving a 59-fold rise in morbidity in comparison with the pre-epidemic period, is characterized in detail. During the epidemic 12,267 persons fell ill, 454 of them died (mortality rate was 4%). Having started in Moscow, the epidemic gradually spread not only over the territory of Russia, but also over some other republics of the former Soviet Union (Ukraine, Belarus, etc.). Possible causes of this epidemic emergency are considered. The ever increasing share of adult population among persons affected by the epidemic (75%) is noted. The infection adults is characterized by severity of clinical manifestations and increased morbidity among adults, is shown. Under complicated social and economic conditions (crisis situation) the increase of groups of high risk which included unemployed adults of working age, retirees as well as socially non-adapted persons, was registered. Mainly these groups determined tense epidemiological situation in diphtheria in Moscow.

Test reactor: basic to U.S. breeder reactor development

International Nuclear Information System (INIS)

Miller, B.J.; Harness, A.J.

1975-01-01

Long-range energy planning in the U. S. includes development of a national commercial breeder reactor program. U. S. development of the LMFBR is following a conservative sequence of extensive technology development through use of test reactors and demonstration plants prior to construction of commercial plants. Because materials and fuel technology development is considered the first vital step in this sequence, initial U. S. efforts have been directed to the design and construction of a unique test reactor. The Fast Flux Test Facility, FFTF, is a 400 MW(t) reactor with driver fuel locations, open test locations, and closed loops for higher risk experiments. The FFTF will provide a prototypic LMFBR core environment with sufficient instrumentation for detailed core environmental characterization and a testing capability substituted for breeder capability. The unique comprehensive fuel and materials testing capability of the FFTF will be key to achieving long-range objectives of increased power density, improved breeding gain and shorter doubling times. (auth)

A Monstrous Moscow. The Dinosaur in Moscow Postmodern Production

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Giulia Imbriaco

2017-02-01

Full Text Available The article offers an interpretation of the dinosaur in the Moscow imagery of the late 20th century as an allegory of the state in which the Marxist-Leninist ideology found itself in those years: more and more inflated with rhetoric, while more and more devoid of contents. In V. Aksyonov's The Burn (1975-76, in the paintings of the duo Komar and Melamid (Ancestral Portraits, Bolsheviks Returning Home After a Demonstration, 1978-82, in D. Prigov's drawing Horror (1990s and verses “For the Little George”, in V. Erofeyev's Russian Beauty (1990, and in V. Sorokin's Ice (2002, the prehistoric monster in its different inflections is the embodiment of a black humour, characterized by an ambiguity typical of both the postmodern parody described by L. Hutcheon and the grotesque realism analyzed by M. Bachtin. The artist's effort in becoming another to himself, simultaneously engaging his own culture and disengaging himself from it by way of a sharp irony, is portrayed in Prigov's Bestiary (1977-2004, where his colleagues are the more 'monstrous' the more they are 'geniuses'. The monster creates a tragicomic and destabilizing clash on different levels, thus prompting reflection about a tormented historical period and about Art's willy-nilly complicity in the rhetorical construction of the official discourses.

Moscow and St. Petersburgpsychological schools: from opposition to friendship

Directory of Open Access Journals (Sweden)

Victor M. Allakhverdov

2016-09-01

Full Text Available The paper is an attempt to summarize the interaction of the two largest schools of psychology in Russia: the psychological schools of Moscow and St. Petersburg. The paper is a sketch dedicated to the 50th anniversary of the psychological faculties of Moscow and St. Petersburg, and should not be appreciated as a historical treatise. Tense ties between the psychological schools, that originate in the distant past, have gone through different historical stages. Slavophilevs Westernizer traditions affected the initial difference in these schoolsemerging into the opposition: either the human being is studied entirety with his/her vast subjective experience, but losing the reliability of our statements (peculiarity of Moscow school, or we study the human being accurately using objective methods, but losing the integrity of our ideas (peculiarity of St.-Petersburg school. Both psychological schools, having gone through the ups and downs, have retained their identity and their emphasis on research. Moscow scholars in their studies are aimed to larger issues and still rely on large-scale Vygotsky-Leontiev approach. Scholars of St.-Petersburgtouch upon more specific issues using empirical methods, but still continue with nostalgia and hope making plans about creating a common concept of human individual according to Ananiev. Nowadays between the two schools there is no opposition, but only one mutual love.

The modification of the Rossendorf Research Reactor

International Nuclear Information System (INIS)

Gehre, G.; Hieronymus, W.; Kampf, T.; Ringel, V.; Robbander, W.

1990-01-01

The Rossendorf Research Reactor is of the WWR-SM type. It is a heterogeneous water moderated and cooled tank reactor with a thermal power of 10 MW, which was in operation from 1957 to 1986. It was shut down in 1987 for comprehensive modifications to increase its safety and to improve the efficiency of irradiation and experimentals. The modifications will be implemented in two steps. The first one to be finished in 1989 comprises: 1) the replacement of the reactor tank and its components, the reactor cooling system, the ventilation system and the electric power installation; 2) the construction of a new reactor control room and of filtering equipment; 3) the renewal of process instrumentation and control engineering equipment for reactor operation, equipment for radiation protection monitoring, and reactor operation and safety documentation. The second step, to be implemented in the nineties, is to comprise: 1) the enlargement of the capacity for storage of spent fuel; 2) the modernization of reactor operations by computer-aided control; 3) the installation of an automated measuring systems for accident and environmental monitoring. Two objects of the modification, the replacement of the reactor tank and the design of a new and safer one as well as the increase of the redundancy of the core emergency cooling system are described in detail. For the tank replacement the exposure data are also given. Furthermore, the licensing procedures based on national ordinances and standards as well as on international standards and recommendations and the mutual responsibilities and activities of the licensing authority and of the reactor manager are presented. Finally, the present state of the modifications and the schedule up to the reactor recommissioning and test operation at full power is outlined

Irradiation test plan of oxidation-resistant graphite in WWR-K Research Reactor

International Nuclear Information System (INIS)

Sumita, Junya; Shibata, Taiju; Sakaba, Nariaki; Osaki, Hirotaka; Kato, Hideki; Fujitsuka, Kunihiro; Muto, Takenori; Gizatulin, Shamil; Shaimerdenov, Asset; Dyussambayev, Daulet; Chakrov, Petr

2014-01-01

Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor (HTGR) which is a graphite-moderated and helium gas-cooled reactor. In the case of air ingress accident in HTGR, SiO_2 protective layer is formed on the surface of SiC layer in TRISO CFP and oxidation of SiC does not proceed and fission products are retained inside the fuel particle. A new safety concept for the HTGR, called Naturally Safe HTGR, has been recently proposed. To enhance the safety of Naturally Safe HTGR ultimately, it is expected that oxidation-resistant graphite is used for graphite components to prevent the TRISO CFPs and fuel compacts from failure. SiC coating is one of candidate methods for oxidation-resistant graphite. JAEA and four graphite companies launched R&Ds to develop the oxidation-resistant graphite and the International Science and Technology Center (ISTC) partner project with JAEA and INP was launched to investigate the irradiation effects on the oxidation-resistant graphite. To determine grades of the oxidation-resistant graphite which will be adopted as irradiation test, a preliminary oxidation test was carried out. This paper described the results of the preliminary oxidation test, the plan of out-of-pile test, irradiation test and post-irradiation test (PIE) of the oxidation-resistant graphite. The results of the preliminary oxidation test showed that the integrity of the oxidation resistant graphite was confirmed and that all of grades used in the preliminary test can be adopted as the irradiation test. Target irradiation temperature was determined to be 1473 (K) and neutron fluence was determined to be from 0.54 × 10"2"5through 1.4 × 10"2"5 (/m"2, E>0.18MeV). Weight change, oxidation rate, activation energy, surface condition, etc. will be evaluated in out-of-pile test and weight change, irradiation effect on oxidation rate and activation energy, surface condition, etc. will be evaluated in PIE. (author)

SSC RIAR is the largest centre of research reactors

International Nuclear Information System (INIS)

Kalygin, V.V.

1997-01-01

The State Scientific Centre (SSC) ''Research Institute of Atomic Reactors'' (RIAR) is situated 100 km to the south-east from Moscow, in Dimitrovgrad, the Volga Region of the Russian Federation. SSC RIAR is the largest centre of research reactors in Russia. At present there are 5 types of reactor facilities in operation, including two NPP. One of the main tasks the Centre is the investigations on safety increase for power reactors. Broad international connections are available at the Institute. On the basis of the SSC RIAR during 3 years work has been done on the development of the branch training centre (TC) for the training of operation personnel of research and pilot reactors in Russia. (author). 3 tabs

SSC RIAR is the largest centre of research reactors

Energy Technology Data Exchange (ETDEWEB)

Kalygin, V V [State Scientific Centre, Research Inst. of Atomic Reactors (Russian Federation)

1997-10-01

The State Scientific Centre (SSC) ``Research Institute of Atomic Reactors`` (RIAR) is situated 100 km to the south-east from Moscow, in Dimitrovgrad, the Volga Region of the Russian Federation. SSC RIAR is the largest centre of research reactors in Russia. At present there are 5 types of reactor facilities in operation, including two NPP. One of the main tasks the Centre is the investigations on safety increase for power reactors. Broad international connections are available at the Institute. On the basis of the SSC RIAR during 3 years work has been done on the development of the branch training centre (TC) for the training of operation personnel of research and pilot reactors in Russia. (author). 3 tabs.

From USA operation experience of industrial uranium-graphite reactors

International Nuclear Information System (INIS)

Burdakov, N.S.

1996-01-01

The review on materials, presented by a group of the USA specialists at the seminar in Moscow on October 9-11, 1995 is considered. The above specialists shared their experience in operation of the Hanford industrial reactors, aimed at plutonium production for atomic bombs. The purpose of the above visit consisted in providing assistance to the Russian specialists by evaluation and modernization of operational conditions safety improvement of the RBMK type reactors. Special attention is paid to the behaviour of the graphite lining and channel tubes with an account of possible channel power interaction with the reactor structural units. The information on the experience of the Hanford reactor operation may be useful for specialists, operating the RBMK type reactors

Experiences of activity measurements of primary circuit materials in a WWR-SM research reactor

International Nuclear Information System (INIS)

Elek, A.; Toth, M.; Bakos, L.; Vizdos, G.

1980-01-01

The activity of water and gas samples taken from the primary circuit have been measured nondestructively for more than two years to monitor the technological parameters of the reactor. In the primary water samples 17 fission products and seven activated traces, as well as six radioactive conponents in the gas samples were determined routinely by Ge/Li gamma-spectrometry. (author)

Theory and Practice of New Music in the Academic Courses of the Moscow State Conservatory

Directory of Open Access Journals (Sweden)

Svetlana Savenko

2015-12-01

Full Text Available Soviet cultural politics was completely determined in the 1930s and remained unchangeable almost until the collapse of the USSR (1991. Musical creativity was subject to the dictates of the strict ideological standards of socialist realism, which left no room for free artistic experimentation. This situation continued in more liberal times, which began after Stalin’s death.The development of the Russian post-war avant-garde began in the second half of the 1950s, with the first dodecaphonic work dating from 1956: Musica Stricta for piano by Andrei Volkonsky. The truly new works gradually penetrated into concert halls; new music became known and even popular among concertgoers, who perceived it as a symbol of spiritual freedom.All this had no relation yet to educational institutions and to teaching, which remained hopelessly conservative. The real institutional changes came only after the collapse of the USSR in the 1990s. Back then, there were three main directions associated with new music: first of all, the establishment of new composers’ associations, such as the Association of Modern Music and the Centre for Contemporary Music; secondly, festivals of contemporary music, such as the festival Moscow Autumn and the annual international festival of contemporary music Moscow Forum; thirdly, the performing collectives connected to them, such as the ensemble Studio for New Music.These institutions were established in the Moscow State “Tchaikovsky” Conservatory, and therefore played a crucial role in the formation of new teaching principles for contemporary music.

[The work of Moscow communities of Sisters of Charity in own medical institutions].

Science.gov (United States)

Zorin, K V

2011-01-01

The article analyses the medical activities of Moscow communities of Sisters of Charity in curative and educational institutions organized by the communities themselves. The social ministration of communities on the territory of Moscow is considered.

U.S. Domestic Reactor Conversion Programs

International Nuclear Information System (INIS)

Woolstenhulme, Eric

2008-01-01

The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

Burnable absorber for the PIK reactor

International Nuclear Information System (INIS)

Gostev, V.V.; Smolskii, S.L.; Tchmshkyan, D.V.; Zakharov, A.S.; Zvezdkin, V.S.; Konoplev, K.A.

1998-01-01

In the reactor PIK design a burnable absorber is not used and the cycle duration is limited by the rods weight. Designed cycle time is two weeks and seams to be not enough for the 100 MW power research reactor equipped by many neutron beams and experimental facilities. Relatively frequent reloading reduces the reactor time on full power and in this way increases the maintenance expenses. In the reactor core fuel elements well mastered by practice are used and its modification was not approved. We try to find the possibilities of installation in the core separate burnable elements to avoid poison of the fuel. It is possible to replace a part of the fuel elements by absorbers, since the fuel elements are relatively small (diameter 5.15mm, uranium 235 content 7.14g) and there are more then 3800 elements in the core. Nevertheless, replacing decreases the fuel burnup and its consumption. In the PIK fuel assembles a little part of the volume is occupied by the dumb elements to create a complete package of the assembles shroud, that is necessary in the hydraulic reasons. In the presented report the assessment of such a replacement is done. As a burnable material Gadolinium was selected. The measurements or the beginning of cycle were performed on the critical facility PIK. The burning calculation was confirmed by measurements on the 18MW reactor WWR-M. The results give the opportunity to twice the cycle duration. The proposed modification of the fuel assembles does not lead to alteration in the other reactor systems, but it touch the burned fuel reprocessing technology. (author)

Distribution of polychlorinated biphenyls, phthalic acid esters, polycyclic aromatic hydrocarbons and organochlorine substances in the Moscow River, Russia

International Nuclear Information System (INIS)

Eremina, Natalia; Paschke, Albrecht; Mazlova, Elena A.; Schüürmann, Gerrit

2016-01-01

The purpose of this study was to investigate the levels of polychlorinated biphenyl (PCB), phthalic acid esters (PAE), polycyclic aromatic hydrocarbons (PAH) and organochlorine substances (OCP) in the Moscow River water. Some studies have reported the occurrence of these substances in the soil of the Moscow region; however, no study has yet established an overview for these compounds in the Moscow River water. In this study the Moscow River water contamination with PAEs, PAHs and OCPs was determined. Obtained results were associated with the resident area located on the river bank, and the possible contamination sources were considered. The obtained data were compared with the data on the contamination of the different world-wide rivers. This research indicates the further study necessity of the Moscow region to cover more contaminated sites and environmental compartments. - Highlights: • The monitoring system creation of the Moscow River is necessary. • The wastewater plant is the source of the river contamination with triclosan. • The Moscow River is contaminated with the low chlorinated biphenyls. • There is a background contamination of the Moscow River with phthalates. - The organic pollutants contamination levels of the Moscow River were investigated.

City Marketing : Case: Moscow

OpenAIRE

Kuzina, Irina

2017-01-01

Nowadays cities compete with each other for attracting investments and people, which make them implement new city marketing and city branding strategies. There are many factors that can influence city image and its perception in customers’ minds. The purpose of this thesis is to realize how a well-selected city marketing strategy benefits the city and gain a deeper understanding of city marketing possibilities. The final goal is to offer suggestions for the city of Moscow, which can help to i...

Recent U.S. reactor operating experience

International Nuclear Information System (INIS)

Stello, V. Jr.

1977-01-01

A qualitative assessment of U.S. and foreign reactor operating experience is provided. Recent operating occurrences having potentially significant safety impacts on power operation are described. An evaluation of the seriousness of each of these issues and the plans for resolution is discussed. A quantitative report on U.S. reactor operational experience is included. The details of the NRC program for evaluating and applying operating reactor experience in the regulatory process is discussed. A review is made of the adequacy of operating reactor safety and environmental margins based on actual operating experience. The Regulatory response philosophy to operating reactor experiences is detailed. This discussion indicates the NRC emphasis on the importance of a balanced action plan to provide for the protection of public safety in the national interest

Current status of operation and utilization of the Dalat research reactor

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Le Van So

2004-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor using the Soviet WWR-SM fuel assembly with 36% enrichment of U-235. It was upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analyses and research purposes. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for physics experiments and training purpose. From the first start-up to the end of December 2002, it totaled about 24,700 hrs of operation and the total energy released was 490 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. This fuel reloading will ensure efficient exploitation of the reactor for about 3 years with 1200-1300 hrs per year at nominal power. The current status of operation and utilization and some activities related to the reactor core management of the DNRR are presented and discussed in this paper. (author)

Space Sciences Education and Outreach Project of Moscow State University

Science.gov (United States)

Krasotkin, S.

2006-11-01

sergekras@mail.ru The space sciences education and outreach project was initiated at Moscow State University in order to incorporate modern space research into the curriculum popularize the basics of space physics, and enhance public interest in space exploration. On 20 January 2005 the first Russian University Satellite “Universitetskiy-Tatyana” was launched into circular polar orbit (inclination 83 deg., altitude 940-980 km). The onboard scientific complex “Tatyana“, as well as the mission control and information receiving centre, was designed and developed at Moscow State University. The scientific programme of the mission includes measurements of space radiation in different energy channels and Earth UV luminosity and lightning. The current education programme consists of basic multimedia lectures “Life of the Earth in the Solar Atmosphere” and computerized practice exercises “Space Practice” (based on the quasi-real-time data obtained from “Universitetskiy-Tatyana” satellite and other Internet resources). A multimedia lectures LIFE OF EARTH IN THE SOLAR ATMOSPHERE containing the basic information and demonstrations of heliophysics (including Sun structure and solar activity, heliosphere and geophysics, solar-terrestrial connections and solar influence on the Earth’s life) was created for upper high-school and junior university students. For the upper-university students there a dozen special computerized hands-on exercises were created based on the experimental quasi-real-time data obtained from our satellites. Students specializing in space physics from a few Russian universities are involved in scientific work. Educational materials focus on upper high school, middle university and special level for space physics students. Moscow State University is now extending its space science education programme by creating multimedia lectures on remote sensing, space factors and materials study, satellite design and development, etc. The space

Forecasting the daily electricity consumption in the Moscow region using artificial neural networks

Science.gov (United States)

Ivanov, V. V.; Kryanev, A. V.; Osetrov, E. S.

2017-07-01

In [1] we demonstrated the possibility in principle for short-term forecasting of daily volumes of passenger traffic in the Moscow metro with the help of artificial neural networks. During training and predicting, a set of the factors that affect the daily passenger traffic in the subway is passed to the input of the neural network. One of these factors is the daily power consumption in the Moscow region. Therefore, to predict the volume of the passenger traffic in the subway, we must first to solve the problem of forecasting the daily energy consumption in the Moscow region.

The determination of fast neutron fluence in radiation stability tests of steel samples

International Nuclear Information System (INIS)

Hogel, J.; Vespalec, R.

1979-01-01

The activation method is described of determining fast neutron fluence. Samples of steel designed for WWER type reactor pressure vessels were irradiated in the CHOUCA-rigs in the core of the WWR-S reactor. The neutron spectrum was measured by the multiple activation foil method and the effective cross sections of fluence monitors were calculated. The fluences obtained from the reactions 54 Fe(n,p) 54 Mn and 63 Cu(n,α) 60 Co are presented and the method is discussed. (author)

Ground Source Heat Supply in Moscow Oblast: Temperature Potential and Sustainable Depth of Heat Wells

Science.gov (United States)

Vasil'ev, G. P.; Gornov, V. F.; Dmitriev, A. N.; Kolesova, M. V.; Yurchenko, V. A.

2018-01-01

The paper is devoted to a problem of increasing the efficiency of low-potential geothermal heat in heat pump systems of residential buildings the Moscow oblast of Russia, including Moscow. Estimates of a natural geothermal potential in the Moscow oblast (based on climatological data for the period from 1982 to 2011) are presented and a "Typical climatic year of natural soil temperature variations for the geoclimatic conditions of the Moscow oblast, including the city of Moscow" is proposed. Numerical simulation of the influence of geothermal energy potential and the depth of heat wells on the efficiency of ground source heat pump systems for the heat supply of residential buildings is carried out. Analysis of the numerical simulation showed that the operation of a heat pump system in a house heating mode under the geoclimatic conditions of the Moscow oblast leads to a temperature drop of the heat-exchange medium circulating through heat wells to 5-6°C by the end of the first 10 years of operation, and the process stabilizes by the 15th year of operation, and further changes in the heat-exchange medium temperature do not any longer significantly affect the temperature of the heat-exchange medium in the heat well. In this case, the exact dependence of the heat-exchange medium temperature drop on the depth is not revealed. Data on the economically expedient heat well depth for the conditions of the Moscow oblast ensuring a net present value for the whole residential building life cycle are presented. It is found that the heat well depth of 60 m can be considered as an endpoint for the Moscow oblast, and a further heat well deepening is economically impractical.

Current status and ageing management of the Dalat Nuclear Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Nguyen Nhi Dien [Nuclear Research Institute, Dalat (Viet Nam)

2000-10-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor loaded with the Soviet WWR-M2 fuel elements, moderated and cooled by light water. It was reconstructed and upgraded from the former 250 kW TRIGA Mark-II reactor built in 1963. The first criticality of the renovated reactor was in November 1983 and it has been put in regular operation at nominal power since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs every 4 weeks, for radioisotope production, neutron activation analyses and other research purposes. The remaining time is devoted to maintenance work and to short runs for reactor physics studies as well. From its first start-up to the end of 1998, it totaled about 20,000 hrs of operation at nominal power. After ten years of operation, reactor general inspection and refurbishment were implemented in the 1992-1996 period. In April 1994, refueling work was executed with adding of 11 fresh fuel elements to the reactor core. At present, the reactor has been working with 100-fuel element configuration. Corrosion study has been implemented by visual inspection of the reactor pool tank and some other inside components which remain unchanged from the previous TRIGA reactor. The inspections were carried out with the assistance of some experts from other countries. Some visual inspection results have been obtained and the nature of the electrochemical corrosion and related aspects were little by little identified. In this paper, the operation status of the Dalat reactor is presented, and some activities related to the ageing management of the reactor pool tank and its inside components are also discussed. (author)

Current status and ageing management of the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Nguyen Nhi Dien

2000-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor loaded with the Soviet WWR-M2 fuel elements, moderated and cooled by light water. It was reconstructed and upgraded from the former 250 kW TRIGA Mark-II reactor built in 1963. The first criticality of the renovated reactor was in November 1983 and it has been put in regular operation at nominal power since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs every 4 weeks, for radioisotope production, neutron activation analyses and other research purposes. The remaining time is devoted to maintenance work and to short runs for reactor physics studies as well. From its first start-up to the end of 1998, it totaled about 20,000 hrs of operation at nominal power. After ten years of operation, reactor general inspection and refurbishment were implemented in the 1992-1996 period. In April 1994, refueling work was executed with adding of 11 fresh fuel elements to the reactor core. At present, the reactor has been working with 100-fuel element configuration. Corrosion study has been implemented by visual inspection of the reactor pool tank and some other inside components which remain unchanged from the previous TRIGA reactor. The inspections were carried out with the assistance of some experts from other countries. Some visual inspection results have been obtained and the nature of the electrochemical corrosion and related aspects were little by little identified. In this paper, the operation status of the Dalat reactor is presented, and some activities related to the ageing management of the reactor pool tank and its inside components are also discussed. (author)

Submersion-Subcritical Safe Space (S4) reactor

International Nuclear Information System (INIS)

King, Jeffrey C.; El-Genk, Mohamed S.

2006-01-01

The Submersion-Subcritical Safe Space (S 4 ) reactor, developed for future space power applications and avoidance of single point failures, is presented. The S 4 reactor has a Mo-14% Re solid core, loaded with uranium nitride fuel, cooled by He-30% Xe and sized to provide 550 kWth for 7 years of equivalent full power operation. The beryllium oxide reflector of the S 4 reactor is designed to completely disassemble upon impact on water or soil. The potential of using Spectral Shift Absorber (SSA) materials in different forms to ensure that the reactor remains subcritical in the worst-case submersion accident is investigated. Nine potential SSAs are considered in terms of their effect on the thickness of the radial reflector and on the combined mass of the reactor and the radiation shadow shield. The SSA materials are incorporated as a thin (0.1 mm) coating on the outside surface of the reactor core and as core additions in three possible forms: 2.0 mm diameter pins in the interstices of the core block, 0.25 mm thick sleeves around the fuel stacks and/or additions to the uranium nitride fuel. Results show that with a boron carbide coating and 0.25 mm iridium sleeves around the fuel stacks the S 4 reactor has a reflector outer diameter of 43.5 cm with a combined reactor and shadow shield mass of 935.1 kg. The S 4 reactor with 12.5 at.% gadolinium-155 added to the fuel, 2.0 mm diameter gadolinium-155 sesquioxide interstitial pins, and a 0.1 mm thick gadolinium-155 sesquioxide coating has a slightly smaller reflector outer diameter of 43.0 cm, resulting in a smaller total reactor and shield mass of 901.7 kg. With 8.0 at.% europium-151 added to the fuel, along with europium-151 sesquioxide for the pins and coating, the reflector's outer diameter and the total reactor and shield mass are further reduced to 41.5 cm and 869.2 kg, respectively

Russian Specifics of Dacha Suburbanization Process: Case Study of the Moscow Region

Directory of Open Access Journals (Sweden)

Aleksandr Valer’evich Rusanov

2015-12-01

Full Text Available Topical issues related to the planning of urban agglomerations development include registration and analysis of changes in suburban areas in the process of socio-economic development. It is manifest, among other things, in urbanization, which in relation to larger cities is replaced by suburbanization. Suburbanization process has been developing to the greatest extent in North America and Western Europe. Scientific research confirms that the majority of large urban agglomerations are in the stage of suburbanization. The pace of suburbanization in the world is different – the authorities of individual countries, regions or cities often take measures to limit or simplify it: they reconstruct central cities, set limits to the construction in peripheral areas, etc. In Russia, the process of suburbanization started to develop rapidly only after the socio-economic transformation of the 1990s that led to the emergence of the free market of housing and land. The aim of the present work is to determine the specifics of suburbanization in Russia on the example of the Moscow Region. Suburbanization in Russia is mainly seasonal; therefore, the paper examines suburbanization specific for Russia and related to the distribution of population and its economic activities in the organized summer house settlements in suburban areas, i.e. in dachas. A kind of this activity popular in Russia is gardening and vegetable and fruit farming in the settlements located on specially designated lands. The paper examines the factors determining suburbanization in the Moscow Region, and demonstrates the influence of these factors taking two key areas as examples. Scientific novelty of the work consists in the fact that it clarifies the content of suburbanization factors as applied to the Moscow Region; in addition, it considers the development of dacha-related suburbanization, highlights its characteristics on the example of the Moscow Region, examines current distribution

The composition of pollutted air in Moscow based on surface observations

Science.gov (United States)

Pankratova, Natalia; Elansky, Nikolai; Skorokhod, Andrey

2013-04-01

Moscow is the one of the biggest world megacities. Population, industry, transport are strong sources of air pollution. This pollution influences on the air quality in the city and in the neighbor regions due to spreading by the wind. Here we present an analysis of variations of atmospheric compounds in Moscow since 2002 until the present in its dependence on different atmospheric characteristics, particularly cyclonic and anticyclonic conditions, heat waves and anthropogenic factors. The following variables are considered: NO2, NO, CO, CO2, O3, SO2, NMHC. The monitoring site is located at Moscow State University meteorological observatory on the South-West of Moscow. All observations are provided by A.M. Obukhov Institute of Atmospheric Physics RAS. Due to these continuous measurements, the typical (ore basic) level of pollution as well as the extreme cases have been studied. The temporal variability of the atmospheric compounds, and the chemical interaction of ozone and nitrogen oxides are investigated. High concentrations of nitrogen oxides are observed throughout the year. During some months the 90th NO2 percentile exceeds 60 ppb, NO - 80 ppb. Based on surface observations, we show that extremes of pollutant concentrations correspond with anticyclonic conditions and anthropogenic processes. These often increase the impact on the weather. These situations correspond with the anomalous cold winter in 2006 and heat wave in 2002. In these periods, concentrations of air pollutions exceed MAC, but the ozone concentration usually decreases due to interaction with NOx. Only two times, ozone concentration exceeded MAC - the heat waves 2002 and 2010. Also in the study we obtain the logarithmic dependence between ozone mix ratio and NO2/NO, which can be used for prediction of the surface ozone concentrations in Moscow: [O3] = 12.22Ln([NO2]/[NO]) + 15.3 However, this equation is not possible to use in smog conditions. From 29 July to 15 August Moscow was in a dense smoke

Research reactor`s role in Korea

Energy Technology Data Exchange (ETDEWEB)

Choi, C-O [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

1996-12-31

After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960`s in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs.

Removal of spent fuel from the TVR reactor for reprocessing and proposals for the RA reactor spent fuel handling

International Nuclear Information System (INIS)

Volkov, E.B.; Konev, V.N.; Shvedov, O.V.; Bulkin, S.Yu; Sokolov, A.V.

2002-01-01

The 2,5 MW heavy-water moderated and cooled research reactor TVR was located at the Moscow Institute for Theoretical and Experimental Physics site. In 1990 the final batch of spent nuclear fuel (SNF) from the TVR reactor was transported for reprocessing to Production Association (PA) 'Mayak'. This transportation of the SNF was a part of TVR reactor decommissioning. The special technology and equipment was developed in order to fulfill the preparation of TVR SNF for transportation. The design of the TVR reactor and the fuel elements used are similar to the design and fuel elements of the RA reactor. Two different ways of RA spent fuel elements for transportation to reprocessing plant are considered: in aluminum barrels, and in additional cans. The experience and equipment used for the preparing TVR fuel elements for transportation can help the staff of RA reactor to find the optimal way for these technical operations. (author)

NON-TRIVIALITY OF THE RESULTS OF MILGRAM FIELD EXPERIMENT IN MOSCOW AND NEW YORK SUBWAY

Directory of Open Access Journals (Sweden)

Olga V Mitina

2017-12-01

Full Text Available Non-triviality of the results of the field experiment conducted on Stanley Milgram’s methodology in the New York and Moscow subway have been studied. The statistical significance of the difference between empirical and predicted results has been taken as the non-triviality criterion. 208 respondents (psychologists and students studying psychology were asked to predict an experimental result in dependence on an experimenter’s and subject’s gender, a subject’s age, and a city where the experiment was carried out. The obtained results have confirmed our hypothesis on non-triviality of the experiments in subways: it has been showed that there is a statistically significant difference between real behavior of subway passengers (in New York and in Moscow and predictions made by Moscow and Tashkent respondents. Practically in most cases the predicted probability that a subject gives a seat after request of experimenter (young woman or young man is much less than in reality. The structural equation modeling (SEM has been used to analyze the data by constructing the model taking account of all factors mentioned above. The model fit the experimental data well (CFI = 0.919. It has been found that predicted results depend not only on gender, age, and residence of a respondent but also on the degree of familiarity with the research. The obtained data give an important material for a further study of the role of situational (an experiment design and individual (respondent characteristics factors in predicted results; they contribute to further understanding of the problem of creation and support of non-formal social norms in various cultures and show new aspects of research carried out on experimental methodology of Stanley Milgram.

The model of the Moscow world in M. Elizarov’s story “"Masha"” = El modelo del mundo de Moscú en la historia de M. Elizarov "Masha"

Directory of Open Access Journals (Sweden)

Oksana Sizykh

2017-01-01

Full Text Available Resumen: La literatura rusa de principios del siglo XXI demuestra la aspiración de los autores de evaluar diversos procesos sociales y culturales que tienen lugar en Moscú, el centro histórico y espiritual de Rusia. El estudio de un texto como fenómeno de cultura, en el que se refleja la mentalidad de una nación y se forman símbolos espaciales reales, contribuye a revelar la originalidad cultural de la nación, sus prioridades morales. La importancia de estudiar la semántica del espacio de Moscú en la prosa post-modernista de M. Y. Elizarov está especificada por un número de factores sociales y culturales, entre los cuales se encuentran el cambio del paradigma del valor de la vida, los imperativos morales y las tradiciones éticas que forman la nueva mitología de Moscú. En relación con los últimos acontecimientos en Ucrania, el nuevo estatuto de Crimea, la autodeterminación de Rusia en el espacio político y cultural mundial, este documento adquiere especial relevancia.Abstract: The Russian literature of the early XXI century demonstrates authors’ aspiration to assess various social and cultural processes taking place in Moscow – the historical and spiritual centre of Russia. The study of a text as a phenomenon of culture, in which a nation’s mentality is reflected and symbolic spatial realia are formed, contributes to revealing the cultural originality of the nation, its moral priorities. The importance of studying the semantics of the Moscow space in M. Y. Elizarov’s post-modernist prose is specified by a number social and cultural factors, among which are the change of the life value paradigm, moral imperatives and ethical traditions forming Moscow’s new mythology. In connection with the latest events in Ukraine, the new status of the Crimea, Russia’s self-determination in the global political and cultural space, this paper gains special relevance.

Comment on the in-core measurement in the WWER nuclear power plant

International Nuclear Information System (INIS)

Krett, V.; Dach, K.; Erben, O.

1985-01-01

The activity of the Nuclear Research Institute (NRI) Rez in the field of in-core measurement sensors is described in the paper. The results of comparison and calibration experiments realized on the WWR-S research reactor at the NRI are presented. Measurements with fission calorimeters and SPN detectors carried out in the framework of diagnostic fuel assembly program of WWER NPP reactors are described. Noise measurements with detectors of in-core instrumentation of diagnostic fuel assemblies are also mentioned. Comparison experiments on the WWER-440 NPP reactor are described and the method of function verification of neutron sensors of the in-core control system of these reactors is given. (author)

MANHATTAN PROJECT B REACTOR HANFORD WASHINGTON [HANFORD'S HISTORIC B REACTOR (12-PAGE BOOKLET)

Energy Technology Data Exchange (ETDEWEB)

GERBER MS

2009-04-28

The Hanford Site began as part of the United States Manhattan Project to research, test and build atomic weapons during World War II. The original 670-square mile Hanford Site, then known as the Hanford Engineer Works, was the last of three top-secret sites constructed in order to produce enriched uranium and plutonium for the world's first nuclear weapons. B Reactor, located about 45 miles northwest of Richland, Washington, is the world's first full-scale nuclear reactor. Not only was B Reactor a first-of-a-kind engineering structure, it was built and fully functional in just 11 months. Eventually, the shoreline of the Columbia River in southeastern Washington State held nine nuclear reactors at the height of Hanford's nuclear defense production during the Cold War era. The B Reactor was shut down in 1968. During the 1980's, the U.S. Department of Energy began removing B Reactor's support facilities. The reactor building, the river pumphouse and the reactor stack are the only facilities that remain. Today, the U.S. Department of Energy (DOE) Richland Operations Office offers escorted public access to B Reactor along a designated tour route. The National Park Service (NPS) is studying preservation and interpretation options for sites associated with the Manhattan Project. A draft is expected in summer 2009. A final report will recommend whether the B Reactor, along with other Manhattan Project facilities, should be preserved, and if so, what roles the DOE, the NPS and community partners will play in preservation and public education. In August 2008, the DOE announced plans to open B Reactor for additional public tours. Potential hazards still exist within the building. However, the approved tour route is safe for visitors and workers. DOE may open additional areas once it can assure public safety by mitigating hazards.

Live From Moscow: The Celebration Of Yuri Gagarin And Transnational Television In Europe

Directory of Open Access Journals (Sweden)

Lars Lundgren

2012-11-01

Full Text Available On April 14th, 1961, television viewers across Europe watched live images of Yuri Gagarin being celebrated on the Red Square in Moscow. The broadcast was made possible by the linking of the Intervision and Eurovision television networks, which was the result of cooperation between broadcasters on both sides of the Iron Curtain. By looking into how the co-operation between the OIRT and EBU was gradually developed between 1957 and 1961 this article engages with the interplay between cultural, legal and technological aspects of broadcasting and how the transnational broadcast of Gagarin’s return to Moscow was made possible. The article furthermore argues the need to understand early television in Europe as a dialectic between the national and the transnational and shows how the live transmission network binding the East and West together was the result of an interplay between structures provided by transnational organisations such as the OIRT and EBU, and initiatives by national broadcasting organisations.

Moscow – Third Rome as Source of Anti-Western Russian Geopolitic

Directory of Open Access Journals (Sweden)

Justyna Doroszczyk

2018-06-01

Full Text Available Moscow as the Third Rome is the basis of Russian thinking about the state and the Russian nation and also Russian geopolitics. It is a solid foundation of anti-Western tendency in Russian geopolitics. The belief about Russia’s providential mission is a tool of differentiation between the two types of civilizations and cultures – the “rotting” western world and the Russian world, which manifests as a cradle of traditional, conservative values that individualistic, materialistic Western civilisation has rejected.

Implementation of U.S. Department of Energy physical protection upgrades in Lithuania and Uzbekistan

International Nuclear Information System (INIS)

Haase, M.; Romesberg, L.; Showalter, R.; Soo Hoo, M.S.; Corey, J.; Engling, E.

1996-01-01

Since 1994, the U.S. Department of Energy (DOE) has provided cooperative assistance to the non-nuclear weapons states of the Former Soviet Union. This effort, within DOE's program of Material Protection, Control, and Accounting (MPC ampersand A), identified the Institute of Nuclear Physics (INP) in Uzbekistan and the Ignalina Nuclear Power Plant (INPP) in Lithuania as sites for cooperative MPC ampersand A projects. The INP, located just outside of Tashkent, is the site of a 10-megawatt WWR-SM research reactor. This reactor is expected to remain operational as a major nuclear research and isotope production reactor for Central Asia. The INPP, located 100 kilometers northeast of the capital city of Vilnius, consists of two Russian-made RBMK reactors with a combined power output of 3,000 megawatts (electric). This power plant has been the subject of international safety and security concerns, which prompted DOE's cooperative assistance effort. This paper describes U.S. progress in a multi-national effort directed at implementing physical protection upgrades in Lithuania and Uzbekistan. The upgrades agreed upon between DOE and the INP and between DOE and the INPP have been designed to interface with upgrades being implemented by other donor countries. DOE/INPP upgrade projects include providing training on U.S. approaches to physical protection, access control through the main vehicle portal, a hardened central alarm station, and improved guard force communications. DOE/INP upgrade projects in Uzbekistan include an access control system, a hardened fresh fuel storage vault, an interior intrusion detection and assessment system, and an integrated alarm display and assessment system

Pressurized water reactor simulator. Workshop material

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21 'WWER-1000 Reactor Simulator' (2002). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23 'Boiling Water Reactor Simulator' (2003). This report consists of course material for workshops using a pressurized water reactor simulator

Reactor neutron activation analysis on reference materials from intercomparison runs

International Nuclear Information System (INIS)

Pantelica, A.; Salagean, M.

2003-01-01

A review of using the Instrumental Neutron Activation Analysis (INAA) technique in our laboratory to determine major, minor and trace elements in mineral and biological samples from international intercomparison runs organised by IAEA Vienna, IAEA-MEL Monaco, 'pb-anal' Kosice, INCT Warszawa and IPNT Krakow is presented. Neutron irradiation was carried out at WWR-S reactor in Bucharest (short and long irradiation) during 1982-1997 and at TRIGA reactor in Pitesti (long irradiation) during the later period. The following type of materials were analysed: soils, marine sediments, uranium phosphate ore, water sludge, copper flue dust, whey powder, yeast, cereal flour (rye and wheat), marine animal tissue (mussel, garfish and tuna fish), as well as vegetal tissue (seaweed, cabbage, spinach, alfalfa, algae, tea leaves and herbs). The following elements could be, in general, determined: Ag, As, Au, Ba, Br, Ca, Ce, Co, Cr, Cs, Eu, Fe, Hf, Hg, K, La, Lu, Mo, Na, Nd, Ni, Rb, Sb, Sc, Se, Sm, Sr, Ta, Tb, Th, U, W, Yb and Zn of long-lived radionuclides, as well as Al, Ca, Cl, Cu, Mg, Mn, and Ti of short-lived radionuclides. Data obtained in our laboratory for various matrix samples presented and compared with the intercomparison certified values. The intercomparison exercises offer to the participating laboratories the opportunity to test the accuracy of their analytical methods as well as to acquire valuable Reference Materials/ standards for future analytical applications. (authors)

U.S. Nuclear Power Reactor Plant Status

Data.gov (United States)

Nuclear Regulatory Commission — Demographic data on U.S. commercial nuclear power reactors, including: plant name/unit number, docket number, location, licensee, reactor/containment type, nuclear...

“There is discrimination in the Russian army against religious minorities” - Interview with Abdurashid Saidov, surgeon, writer and Moscow correspondent for Dagestanskaia Pravda, Moscow, 7 October 2008

Directory of Open Access Journals (Sweden)

Elisabeth Sieca-Kozlowski

2009-12-01

Full Text Available PIPSS.ORG – What is it like for Dagestani conscripts? How do the officers relate to them? Are they able to fulfill all their religious duties? Do Dagestanis have the ability to rise to the officer ranks?Abdurashid Saidov: In Moscow, there are more than 10 million residents; in Dagestan, there are 2 million. In each conscription, however, Dagestan offers up many times more young men to the army than Moscow. Speaking of attitudes towards Muslims, it is possible to say with confidence that in th...

Russian Chronicles on the Moscow-Kazan Relations: An Experience of the Hermeneutic Research

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A.V. Aksanov

2017-03-01

Full Text Available Research objective: This paper analyzes the problem of interpretation of the chronicle reports about the Moscow-Kazan relations and identifies the semantics of these reports by using the hermeneutic analysis of texts. Research materials: The author cites the examples of the sources’ misunderstanding. Researchers treated literally reports about the Kazan khanate foundation, which in fact were based on the reminiscences from biblical books and needed an allegorical interpretation. Scholars made similar mistakes in their interpretation of some of the reports about the Kazan campaigns in 1467, 1487, 1506, and 1552. In turn, the use of hermeneutic methods allows us to significantly supplement and even revise the picture of the Moscow-Kazan relations presented in the historians’ works. This paper demonstrates some features of the evolution of Russian chronicle writing that affected the nature of the representation of interstate relations. Period of the last third of the 15th century is described both by official and independent (provincial chronicle vaults. In this, these sources describe the events in different ways. Official chronicles represented the Moscow-Kazan war of 1467–1469 as a religious confrontation ended with Russian victory, while independent sources described this war without religious connotations and pointed to the defeat of Moscow forces. The author also revealed significant differences in the description of the events in 1478 and 1487. Research results and novelty: In such a way, independent sources refute a number of official reports about the Moscow-Kazan relations in the last third of the 15th century. In turn, period of the first half of the 16th century is well documented only in the official chronicles since independent chronicles fell into decline during the strengthening of the united Russian State. Thus, the picture of the Moscow-Kazan relations of this period is unilateral since it is based on information of official

Boiling water reactor simulator. Workshop material

International Nuclear Information System (INIS)

2003-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and workshop material and sponsors workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 simulator from the Moscow Engineering and Physics Institute, Russian Federation is presented in the IAEA publication: Training Course Series No. 21 'WWER-1000 Reactor Simulator' (2002). Course material for workshops using a pressurized water reactor (PWR) simulator developed by Cassiopeia Technologies Incorporated, Canada, is presented in the IAEA publication: Training Course Series No. 22 'Pressurized Water Reactor Simulator' (2003). This report consists of course material for workshops using a boiling water reactor (BWR) simulator. Cassiopeia Technologies Incorporated, developed the simulator and prepared this report for the IAEA

[Mycobacterium tuberculosis strain transmission caused by migratory processes in the Russian Federation (in case of populational migration from the Caucasian Region to Moscow and the Moscow Region)].

Science.gov (United States)

Andreevskaia, S N; Chernousova, L N; Smirnova, T G; Larionova, E E; Kuz'min, A V

2006-01-01

The investigation was carried out on 134 M. tuberculosis isolated from 134 patients treated at the Central Research Institute of Tuberculosis, Russian Academy of Medical Sciences. The patients were divided into 2 groups: 1) those who were natives of Moscow and the Moscow Region (MR patients); 2) those who were migrants to the Moscow Region from Azerbaijan, Daghestan, Chechnya, Ingushetia, Karachai-Cherkessia, North Ossetia (the Caucasian Region) (CR patients) who had fallen in the place of birth. Genotyping by the polymorphism of lengths of the restriction fragments containing the insertion sequence IS6110 revealed a genetic diversity of M. tuberculosis strains. The examined M. tuberculosis strains belonged to 13 genotypic families. The W and AI families were prevalent. The family W M. tuberculosis strains isolated from the Caucasians were highly clustered, as confirmed by the overwhelming predominance of the strain variant W148 (19.7%). The spectrum of the strain variants of the W family, and those of the AI family in particular, greatly differed in MR and CR patients. Only one strain variant AI12 occurring both in MR and CR patients was detected. A study of the transmission activity coefficient (TAC) of the families W and AI indicated that the transmission activity of W strains was significantly higher than that of M. tuberculosis strains of the AI family. A comparative analysis of the TAC of M. tuberculosis strains of the AI family demonstrated that the transmission activity of the strains of this family was identical no matter where a patient had fallen ill (1.59 and 1.41% in the Moscow and Caucasian Regions, respectively). Unlike M. tuberculosis strains of the AI family, the TAC of W strains isolated from the patients infected in the Moscow Region (28.17 and 19.05%, respectively), which suggests the more intensive transmission of the pathogen M. tuberculosis of the W family in the Caucasian Region.

Estimations of pollution emissions by the Moscow megapolis basing on in-situ measurements and optical remote sensing

Science.gov (United States)

Elansky, N.; Postylyakov, O.; Verevkin, Y.; Volobuev, L.; Ponomarev, N.

2017-11-01

By the present a large amount of data has been accumulated on direct measurements of the pollution and thermodynamic state of the atmosphere in the Moscow region, which was obtained at stations of Roshydromet, Mosecomonitoring, A.M.Obukhov Institute of Atmospheric Physics (OIAP), M.V. Lomonosov Moscow State University, NPO Typhoon, what allows estimating pollution emissions based on measurements and correcting existing emission inventories, which are evaluated mainly on indirect data connected with population density, fuel consumption, etc. Within the framework of the project, the whole volume of data on the concentration of ground contaminants CO, NOx, SO2, CH4, obtained at regularly operated Moscow Ecological Monitoring stations and at OIAP stations from 2005 to 2014, was systematized. Observation data on pollution concentrations are supplemented by measurements of their integral content in the atmospheric boundary layer, obtained by differential spectroscopy methods (MAX DOAS, ZDOAS) at stationary stations and by passing Moscow with DOAS-equipped car. The paper present preliminary estimates of pollution emissions in the Moscow region, obtained on the basis of the collected array of experimental data. The estimations of pollutant emissions from Moscow were obtained experimentally in a few ways: (1) on the basis of network observations of surface concentrations, (2) on the basis of measurements in the atmospheric layer 0-348 m at Ostankino TV tower, (3) on the basis of the integral pollutant (NO2) content in ABL obtained by DOAS technique from stationary stations, and (4) using a car with DOAS equipment traveling over the closed route around Moscow (for NO2). All experimental approaches yielded close values of pollution emissions for Moscow. Trends in emissions of CO, NOx, and CH4 are negative, and the trend of SO2 emission is positive from 2005 to 2014.

The Last Case and Death of «Moscow Metropolitan» Boris (Rukin: to the Issue of His Suicide

Directory of Open Access Journals (Sweden)

A. MAZYRIN

2014-02-01

Full Text Available The author investigates circumstances of the last arrest and the death of bishop (in schism — «the Moscow metropolitan» Boris (Rukin in detention in 1931 on the basis of his Case from the documents of the Central archive of FSB of the Russian Federation. The author studies the arrest’s reason (the attempt to bribe a soviet clerk, assorts in details the course of investigation and analyzes its result — death of bishop Boris in the hospital of the Butyrsky insulator. In the article the basic attention was occupied with checking of the official version of church-historical literature about suicide of the bishop. The author considers the death of the prisoner, «the metropolitan Moscow», has followed soon after accusing him of a counterrevolutionary propaganda. It was his words to «churchmen» about the possibility to bribe the Soviet power. Materials of the investigatory case do not contain any data to support the version of suicide. At the same time, they allow to assume the interest of the OGPU bodies in the distribution of this version with the purpose to justify the refusal to give out the body of late «metropolitan» Boris for his church burial. The materials have also indirectly testified to the interest in elimination of «the Moscow metropolitan» of some «churchmen» connecting with him. First of all, it was «metropolitan» Bessarion (Zorin who headed the Gregorian split. He obtained a Boris’s apartment under the decision of VCIK. The article can be useful at drawing up of biographic directories, at writing of historical monographies about the Gregorian split, the Moscow diocese and the Russian Orthodox Church as a whole.

Influence of air temperature on electric consumption in Moscow

Science.gov (United States)

Lokoshchenko, Mikhail A.; Nikolayeva, Nataliya A.

2017-04-01

For the first time for mid latitudes and with the use of long-term data of Moscow State University Meteorological observatory a dependence of electric power consumption E on the air temperature T has been studied for each separate day for the period from 1990 to 2015 (totally - 9496 values). As a result, it is shown that the relation is in general decreasing in conditions of cold Moscow region: energy consumption as a rule reduces with a rise of the temperature. However, in time of severe frosts the energy consumption increasing goes to nothing due to special measures for energy savings whereas during heat wave episodes of extremely hot weather (especially in summer of 2010) an opposite tendency appears to the energy consumption increase with the increase of the air temperature due to additional consumption for the air conditioning. This relation between E and T is statistically significant with extremely high confidence probability (more than 0.999). The optimum temperature for the energy saving is 18 ˚C. The air temperature limit values in Moscow during last decades have been discussed. Daily-averaged T varied from -28.0 ˚C in January of 2006 to +31.4 ˚C in August of 2010 so a range of this parameter is almost 60 ˚C. Catastrophic heat wave in 2010 appeared as a secondary summer maximum of the electric consumption annual course. The relation between E and T for separate years demonstrates strong weekly periodicity at the dynamics of E daily values. As a result statistical distribution of E daily values for separate years is bimodal. One its mode is connected with working-days and another one - with non-work days (Saturday, Sunday and holidays) when consumption is much less. In recent time weekly cycle at the electric consumption became weaker due to total fall of industry in Moscow. In recent years the dependence of energy consumption on the air temperature generally became stronger - probably due to changes of its structure (growth of non-industrial users

Report on the visit of a U.S. Nuclear Safety Delegation to the Soviet Union, August 19-31, 1988

International Nuclear Information System (INIS)

1989-03-01

During August 1988 a US delegation of nuclear reactor safety specialists, led by US Nuclear Regulatory Commission Chairman Lando W. Zech, Jr., visited the Soviet Union to initiate cooperative activities in civilian nuclear reactor safety between the two countries under their April 1988 Memorandum of Cooperation. Areas of future cooperation and a schedule of working group meetings to explore these areas were defined in a protocol signed during this visit. The delegation met with Soviet representatives in Moscow as the Joint coordinating Committee on Civilian Nuclear Reactor Safety. Additionally, while in Moscow, Chairman Zech held discussions with leaders and other senior officials of Soviet organizations with responsibility for nuclear power safety. Nuclear facilities were also visited, including the Kurchatov Institute of Atomic Energy (Moscow), the Novovoronezh Atomic Power Station, the Novovoronezh Training and Commissioning Center, the Izhora Heavy Equipment Production Plant (Kolpino), the V. G. Khlopin Radium Institute (Gatchina), the Chernobyl Atomic Power Station, the All-Union Center for Radiation Medicine (Kiev), and the Rovno Atomic Power Station. 35 figs

New Admissions to the K.G. Paustovsky Moscow Literary Museum-Center

Directory of Open Access Journals (Sweden)

Angelica I. Dormidontova

2018-03-01

Full Text Available This is an overview of а new collection received by the K.G. Paustovsky Moscow Literary Museum-Center in 2017, the year of the 125th anniversary of his birth. The collection consists of 366 items. Among them are manuscripts, biographical documents, letters, books with autographs, photographs, posters, booklets, and drawings. These items are of considerable interest for the study of the writer’s methods, his biography as well as for understanding the circle of his contacts. The overview incorporates a number of authentic documents.

Topic 8 Ecological Risk Assessment and regulatory guidance, radioecological assessment and radioprotection of the territory of Moscow

Energy Technology Data Exchange (ETDEWEB)

Polski, O.G.; Shmonov, M.G.; Lakaev, V.S. [Scientific-and-Industrial Association Radon, Moscow (Russian Federation)

2004-07-01

Moscow is the historical centre of the atom project of the former USSR. The radiation situation in Moscow has been regularly monitored by 'Radon' Scientific-and-Industrial Association (Moscow) since 1987. In pursuance of conception and Program of the Environmental Radiation Monitoring in Moscow the environmental activity and monitoring of radiation exposure doses in Moscow area have been carried out. The environmental radiation monitoring includes radiation measuring, classification and summarisation of the data file, creation of the data bank, assessment of the general and local radiation situation and it's forecasting. The system for environmental radiation monitoring consists of mobile and stationary monitoring equipment. The mobile equipment includes the automobile, water and aircraft means for monitoring. The stationary equipment includes means for periodical monitoring (134 sites), a network for stationary monitoring of air (4 sites), water areas (64 sites) and a network for automated monitoring of radiation background (MRB) ( 19 sites). MRB are disposed at highways, railroads, large enterprises, at densely populated localities, taking into account the regularity of encompassing all administrative regions. MRB represents a totally automated component for monitoring at the region. It permanently monitors the radiation background in automatic mode, providing for monitoring the preset threshold background values and informing the data processing centre of exceeding the above preset values. The equipment monitors and reports the radiation values twenty four hours a day. The information is provided for the population at indication boards. More than 3000 environmental samples are monitored and studied; about 2500 km of automatic gamma-survey is carried out annually and 300 thermoluminescent dosimeters have been used to monitor the absorbed radiation dose. The major radionuclides monitored in the environmental samples have been the decay products of

Advances in U.S. reactor physics standards

International Nuclear Information System (INIS)

Cokinos, Dimitrios

2008-01-01

The standards for Reactor Design, widely used in the nuclear industry, provide guidance and criteria for performing and validating a wide range of nuclear reactor calculations and measurements. Advances, over the past decades in reactor technology, nuclear data and infrastructure in the data handling field, led to major improvements in the development and application of reactor physics standards. A wide variety of reactor physics methods and techniques are being used by reactor physicists for the design and analysis of modern reactors. ANSI (American National Standards Institute) reactor physics standards, covering such areas as nuclear data, reactor design, startup testing, decay heat and fast neutron fluence in the pressure vessel, are summarized and discussed. These standards are regularly undergoing review to respond to an evolving nuclear technology and are being successfully used in the U.S and abroad contributing to improvements in reactor design, safe operation and quality assurance. An overview of the overall program of reactor physics standards is presented. New standards currently under development are also discussed. (authors)

Neutron radiography

International Nuclear Information System (INIS)

Hrdlicka, Z.

1977-01-01

Neutron radiography is a radiographic method using a neutron beam of a defined geometry. The neutron source usually consists of a research reactor, a specialized neutron radiography reactor or the 252 Cf radioisotope source. There are two types of the neutron radiography display system, viz., a system producing neutron radiography images by a photographic process or a system allowing a visual display, eg., using a television monitor. The method can be used wherever X-ray radiography is used except applications in the radiography of humans. The neutron radiography unit at UJV uses the WWR-S reactor as the neutron source and both types of the above mentioned display system. (J.P.)

Evaluation of neutron flux in the WWR-SM reactor channel and in the irradiating zone of U-150 cyclotron

International Nuclear Information System (INIS)

Sadikov, I.I.; Zinov'ev, V.G.; Sadikova, Z.O.; Salimov, M.I.

2006-01-01

Full text: For effective work of a reactor, and correct planning of experiments related to the reactor irradiation of various materials it is required to control a neutron flux in the given irradiation point for a long irradiation period. For realization of research works on topazes ennobling under irradiation by reactor neutrons as well as by secondary neutrons produced in a cyclotron it is necessary to know the total neutron flux and spectra. To resolve the problem a technique for registration of neutrons with different energy and calculation of a neutrons spectrum in the given irradiation points in reactor channels and in cyclotron behind the nickel target has been developed. Neutron flux density and energy spectra were monitored by use of the following nuclear reactions: 59 Co(n,γ) 60 Co, 197 Au(n,γ) 198 Au, 58 Ni(n,p) 58 Co, 24 Mg(n,p) 24 Na, 48 Ti(n,p) 48 Sc, 46 Ti(n,p) 46 Sc, 54 Fe(n,p) 54 Mn, 89 Y(n,2n) 88 Y, 60 Ni(np) 60 Co. Gamma spectrometer composed of HPGe detector (Rel. Eff. - 15%) and Digital Spectra Analyzer DSA-1000 (Canberra Ind., USA) was used to measure gamma activity of irradiated samples. Acquired gamma spectra were processed by means of Genie 2000 standard software package. The σ(E) functions and neutron spectra were calculated by using the least squares method and approximating the tabular and experimental data with power polynomials. The developed technique was applied for the adjustment of the topazes irradiation regimes in the reactor core and under secondary neutrons flux from a nickel target in the cyclotron. The given technique allows to calculate a logarithmic spectrum of neutrons in a energy range from 0,025 eV up to 12 MeV with the uncertainty of about 10 %. (author)

Inauguration of the Moscow-based office of GRS/IPSN-RISKAUDIT by the Federal German Minister of the Environment, Mr. Klaus Toepfer, and the Minister of Industry, Mr. Dominique Strauss-Kahn

International Nuclear Information System (INIS)

1993-02-01

The German and the French Government as well as the EC are taking particular interest in cooperative activities with the Russian Federation in the field of reactor safety enhancement and protection of the environment. The existing cooperation is expected to be intensified by the establishment of a common office in Moscow. The organisation, tasks and financing scheme of the RISKAUDIT office are explained in the languages German, Russian and French. (HP) [de

Comparative Analysis of Tokyo and Moscow Experience in Addressing the Traffic Jams Problem: A View from Moscow and Tokyo

OpenAIRE

Kiichiro Hatoyama

2011-01-01

The problem of traffic jams in Moscow turns out to be chronic. The author employs a comparative analysis of the experiences of different countries, especially Russia and Japan, in decreasing traffic congestion, appropriate damage and in solving other transport problems. The article analyzes the objective and subjective reasons for the deterioration of the traffic situation, as well as effective strategies to address them. 

Comparative Analysis of Tokyo and Moscow Experience in Addressing the Traffic Jams Problem: A View from Moscow and Tokyo

Directory of Open Access Journals (Sweden)

Kiichiro Hatoyama

2011-01-01

Full Text Available The problem of traffic jams in Moscow turns out to be chronic. The author employs a comparative analysis of the experiences of different countries, especially Russia and Japan, in decreasing traffic congestion, appropriate damage and in solving other transport problems. The article analyzes the objective and subjective reasons for the deterioration of the traffic situation, as well as effective strategies to address them. 

Identification of Chemical Reactor Plant’s Mathematical Model

OpenAIRE

Pyakullya, Boris Ivanovich; Kladiev, Sergey Nikolaevich

2015-01-01

This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

Pressurized water reactor simulator. Workshop material. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development. And the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21, 2nd edition, 'WWER-1000 Reactor Simulator' (2005). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23, 2nd edition, 'Boiling Water Reactor Simulator' (2005). This report consists of course material for workshops using a pressurized water reactor simulator

Development prospects of keratoplasty in Moscow

Directory of Open Access Journals (Sweden)

E. M. Kildyushov

2013-01-01

Full Text Available A retrospective analysis of the statistical data for the years 2010‑2012 on mortality and the donor selection of the Bureau of Forensic Pathology of Moscow, Department of Forensic Pathology of Pirogov N. I. Russian National Research Medical University and ILab Eye Bank in order to determine the possible number of keratoplastic surgeries. The results of statistical data analysis testify to the fact that the number of available donor material is not sufficient to meet the needs for keratoplastic material and it is necessary to create eye banks, which would have provided this need. It is necessary to create eye banks, that possess a clear logistics chain of intake donor tissue, preliminary assessment of the donor tissue, laboratory diagnostics of the donor’s blood and delivery of tissue to the Bank. Theeye bank should not only produce preserved material for keratoplasty, but also carry out full morpho-functional assessment of material and its subsequent delivery to consumers in health facilities.

The foundation of computer based closed radionuclide sources turnover control system in Moscow city region

International Nuclear Information System (INIS)

Gusev, A.E.; Kozlov, A.A.; Lavrov, K.N.; Sobolev, I.A.

1998-01-01

This paper concerns the problem of Closed Radionuclide Sources (CRS) automated account and control in Moscow city and Moscow region. Information relations structure between authorities and enterprises is shown. Special computer oriented system of CRS turnover monitoring is used for this purposes. Its possibilities and numeric characteristics of database are mentioned. This system benefit and application aspects are discussed in detail. (author)

[Prevalence of dental diseases among Moscow students and need of dentistry].

Science.gov (United States)

Makeeva, I M; Doroshina, V Iu; Protsenko, A S

2009-01-01

A clinical epidemiologic study was made among 432 Moscow students and as a part of it was found the high prevalence rate of pathologies of dentition and variety of nosologic forms. The most common cases were: caries, periodontal disease, deformity and anomalies of tooth position. These findings were necessary to estimate the need of all types of dentistry for Moscow students. It was specified that 43% of students were in need of filling and dental restoration, 35% were in need of crowns of tooth, 22% were in need of dental restoration by means of orthopedic constructions. Endodontic dentistry was necessary for 31% of students, surgical removal - for 8%, periodontal dentistry - for 37%.

Identification of Chemical Reactor Plant’s Mathematical Model

Directory of Open Access Journals (Sweden)

Pyakillya Boris

2015-01-01

Full Text Available This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

Marketing plan for Pharmacare product line in the Moscow region Case Oriola-KD

OpenAIRE

Mashkilleyson, Peter

2012-01-01

The thesis was commissioned by Oriola-KD. It deals with a marketing plan for a product line called Pharmacare. The product line will be launched in 2012 in the Moscow region in the Russian Federation. The purpose of this thesis was to acquire useful information about the Moscow market for the target company and produce a marketing plan that they can implement. The research question was how to create an effective marketing plan and what it entails. The literary review consisted of the theo...

Comparison of long-term Moscow and Danish NLC observations: statistical results

Directory of Open Access Journals (Sweden)

P. Dalin

2006-11-01

Full Text Available Noctilucent clouds (NLC are the highest clouds in the Earth's atmosphere, observed close to the mesopause at 80–90 km altitudes. Systematic NLC observations conducted in Moscow for the period of 1962–2005 and in Denmark for 1983–2005 are compared and statistical results both for seasonally summarized NLC parameters and for individual NLC appearances are described. Careful attention is paid to the weather conditions during each season of observations. This turns out to be a very important factor both for the NLC case study and for long-term data set analysis. Time series of seasonal values show moderate similarity (taking into account the weather conditions but, at the same time, the comparison of individual cases of NLC occurrence reveals substantial differences. There are positive trends in the Moscow and Danish normalized NLC brightness as well as nearly zero trend in the Moscow normalized NLC occurrence frequency but these long-term changes are not statistically significant. The quasi-ten-year cycle in NLC parameters is about 1 year shorter than the solar cycle during the same period. The characteristic scale of NLC fields is estimated for the first time and it is found to be less than 800 km.

Neutron targets of Moscow meson facility status, problems, prospects

Energy Technology Data Exchange (ETDEWEB)

Sidorkin, S.; Koptelov, E.; Perekrestenko, A.; Stavissky, Y.; Trushkin, V.; Sobolevsky, N. [Institute for Nuclear Research RAS, 60-th October Anniversary Prospect, Moscow (Russian Federation)

2001-03-01

The status, problems and possible perspectives of target complexes of the Moscow meson factory is described in the report. The results of test proton beam session to neutron source are analysed. Some technical features of targets and expected modes in the nearest sessions are stated. (author)

Operating history of U.S. nuclear power reactors

International Nuclear Information System (INIS)

1974-01-01

The operating history of U. S. nuclear power plants through December 31, 1974 has been collected. Included are those nuclear reactor facilities which produce electricity, even if in token amounts, or which are part of a development program concerned with the generation of electricity through the use of a nuclear reactor as a heat source. The information is based on data furnished by facility operators. The charts are plotted in terms of cumulative thermal energy as a function of time. Since only those shutdowns of five days or more are shown, the charts do not give a detailed history of plant operation. They do, however, give an overview of the operating history of a variety of developmental and experimental nuclear power reactors. The data show the yearly gross generation of electricity for each U. S. nuclear plant and, for civilian power plants, information on reactor availability and plant capacity factor. (U.S.)

PECULIARITIES OF CONSTRUCTION OF INSTITUTIONS OF SECONDARY EDUCATION IN MOSCOW IN THE 1920IES AND 1930IES

Directory of Open Access Journals (Sweden)

Byzova Ol'ga Mikhaylovna

2012-10-01

Full Text Available Actions aimed at the generality of elementary education in the course of the period days of the industrialization and cultural revolution in the USSR is under discussion in the proposed paper. On the basis of the archived documents, organization of construction of school buildings in Moscow in the 20ies and 30ies of the 20th century is analyzed. It is noteworthy that industrialization in the periods of the first, second and third five-year plans reshaped the country and Moscow as its capital. Former suburbs turned into large industrial areas that had giant factories and housing built around them to accommodate workers. Thus, the population of Moscow grew in numbers. The need for competent staff facilitated construction of new schools. Peculiarities of school construction in Moscow within the first five-year plan are considered in article on the basis of a school building in Likhobory in 1932. The school building design, work progress, assembly and interior, deadlines and problems of construction are specified. It is noteworthy that, despite any difficulties, 19 new school buildings were completed in Moscow in the years of the first five-year plan. Classes were organized according to the principle of two shifts to implement the general education programme in 1932.

Research about reactor operator's personability characteristics and performance

Energy Technology Data Exchange (ETDEWEB)

Wei Li; He Xuhong; Zhao Bingquan [Tsinghua Univ., Institute of Nuclear Energy Technology, Beijing (China)

2003-03-01

To predict and evaluate the reactor operator's performance by personality characteristics is an important part of reactor operator safety assessment. Using related psychological theory combined with the Chinese operator's fact and considering the effect of environmental factors to personality analysis, paper does the research about the about the relationships between reactor operator's performance and personality characteristics, and offers the reference for operator's selection, using and performance in the future. (author)

Analysis of the structural changes in domestic consumption of FUEL and energetic resources of Moscow

Directory of Open Access Journals (Sweden)

L. G. Moiseykina

2017-01-01

identify existing trends in the development of the fuel and energy complex in the capital region Results. The analysis allowed to identify the current trends in consumption of the main types of fuel and energy resources in Moscow, to assess the structure and structural changes in consumption of fuel and energy resources in Moscow, in order to assess the energy efficiency of the fuel and energy complex of the capital. Conclusion. The main goal of Moscow’s energy policy is to create an economically efficient, dynamically developing and financially sustainable fuel and energy complex equipped with advanced technologies and highly qualified personnel and meeting the requirements of the time and status of Moscow. Increasing the efficiency of the use of fuel and energy resources, for Moscow as one of the coldest capitals of the world, is becoming one of the priority tasks. Consequently, another task of developing the fuel and energy complex of the city is to expand the scale of the introduction of secondary energy resources and bring the indicator of their use to 50%. That is why, a comprehensive analysis of the dynamics and structure of consumption of fuel and energy resources will allow not only to assess the existing patterns of distribution and trends, but also as a consequence to form a highly effective energy strategy for the megacity. 

EMERIS: an advanced information system for a materials testing reactor

International Nuclear Information System (INIS)

Adorjan, F.; Buerger, L.; Lux, I.; Mesko, L.; Szabo, K.; Vegh, J.; Ivanov, V.V.; Mozhaev, A.A.; Yakovlev, V.V.

1990-06-01

The basic features of the Materials Testing Reactor of IAE, Moscow (MR) Information System (EMERIS) are outlined. The purpose of the system is to support reactor and experimental test loop operators by a flexible, fully computerized and user-friendly tool for the aquisition, analysis, archivation and presentation of data obtained during operation of the experimental facility. High availability of EMERIS services is ensured by redundant hardware and software components, and by automatic configuration procedure. A novel software feature of the system is the automatic Disturbance Analysis package, which is aimed to discover primary causes of irregularities occurred in the technology. (author) 2 refs.; 2 figs

Sex differences in health and mortality in Moscow and Denmark

DEFF Research Database (Denmark)

Oksuzyan, A; Shkolnikova, M; Vaupel, J W

2014-01-01

and a male advantage in self-rated health, physical functioning, and depression symptomatology. Only on cognitive tests males performed similarly to or worse than women. Nevertheless, Muscovite males had more than twice higher mortality at ages 55-69 years compared to Muscovite women, almost double the ratio......In high income countries females outlive men, although they generally report worse health, the so-called male-female health-survival paradox. Russia has one of the world's largest sex difference in life expectancy with a male disadvantage of more than 10 years. We compare components of the paradox...... between Denmark and Moscow by examining sex differences in mortality and several health measures. The Human Mortality Database and the Russian Fertility and Mortality Database were used to examine sex differences in all-cause death rates in Denmark, Russia, and Moscow in 2007-2008. Self-reported health...

3. International conference on catalysis in membrane reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

The 3. International Conference on Catalysis in Membrane Reactors, Copenhagen, Denmark, is a continuation of the previous conferences held in Villeurbanne 1994 and Moscow 1996 and will deal with the rapid developments taking place within membranes with emphasis on membrane catalysis. The approx. 80 contributions in form of plenary lectures and posters discuss hydrogen production, methane reforming into syngas, selectivity and specificity of various membranes etc. The conference is organised by the Danish Catalytic Society under the Danish Society for Chemical Engineering. (EG)

"Have a Good One": For a U of I Transplant from New Delhi, Moscow, Idaho, Was as Confusing as Moscow, Russia

Science.gov (United States)

Dasgupta, Sayantani

2012-01-01

In 2006, the author had moved to Moscow, Idaho, from New Delhi, after having worked for nearly four years in publishing houses. She had become exhausted by stets, specs, and style sheets. Whiny authors with paper-thin egos bored her, and she was frustrated with lazy designers who tried to pass off every odd cover as avant-garde. She wanted to…

Weekly variability of surface CO concentrations in Moscow

Science.gov (United States)

Sitnov, S. A.; Adiks, T. G.

2014-03-01

Based on observations of carbon monoxide (CO) concentrations at three Mosekomonitoring stations, we have analyzed the weekly cycle of CO in the surface air of Moscow in 2004-2007. At all stations the minimum long-term mean daily CO values are observed on Sunday. The weekly cycle of CO more clearly manifests itself at the center of Moscow and becomes less clear closer to the outskirts. We have analyzed the reproducibility of the weekly cycle of CO from one year to another, the seasonal dependence, its specific features at different times of day, and the changes in the diurnal cycle of CO during the week. The factors responsible for specific features of the evolution of surface CO concentrations at different observation stations have been analyzed. The empirical probability density functions of CO concentrations on weekdays and at week- end are presented. The regularity of the occurrence of the weekend effect in CO has been investigated and the possible reasons for breaks in weekly cycles have been analyzed. The Kruskal-Wallis test was used to study the statistical significance of intraweek differences in surface CO contents.

Report on results of the Experts from the Boris Kidric Institute to the Institute for theoretical and experimental physics in Moscow - Operational Report; Radni izvestaj - Izvestaj o rezultatima posete strucnjaka iz IBK Institutu za teorijsku i eksperimentalnu fiziku u Moskvi

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Petrovic, M; Cupac, S [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1976-12-15

Three experts from the Boris Kidric Institute of Nuclear sciences have visited the the Institute of theoretical and experimental physics in Moscow from 17-23 October 1976. The objective of this visit was to: a) obtain information about operational characteristics of the TVRS reactor with 80% enriched fuel, and experiences about utilization of this fuel in the TVRS in Moscow; b) getting acquainted with the elements of safety analysis related to conversion of TVRS reactor core to new fuel into and its utilization; and c) exchange of opinion about the program for introducing the new 80% enriched fuel into the RA reactor core. This report contains the results achieved during the visit. The most important conclusions drawn are as follows. a) The visit was successful although answers to some important questions were not obtained. b) After analyzing the obtained information and after obtaining the first experiences related to application of the new fuel in the RA reactor core and final decision about the operation equilibrium cycle with the new fuel, another visit to Moscow would be very useful. c.) New dispersion highly enriched fuel is much more reliable during operation than the 2% enriched metal uranium fuel (presently used in the Ra reactor). d) There have been no objection concerning our program for conversion of RA reactor to operation with the new fuel (transition regime). e) additional information will be demanded concerning maximum permissible burnup level of the 80% enriched dispersion fuel. Optimum equilibrium burnup cycle will be revised according to the maximum burnup conditioned by RA reactor parameters. f) Methods for thermal analysis of the fuel elements which is applied at the RA reactor was found to be equivalent with the method applied for calculations at the TVRS in Moscow. [Serbo-Croat] Grupa od tri saradnika IBK boravila je u Institutu za teorijsku i eksperimentalnu fiziku u Moskvi u vremenu od 17.10. do 23.10.1976. godine. Cilj posete je bio: a

History of fast reactor development in U.S.A.-I

International Nuclear Information System (INIS)

Ninokata, Hisashi; Sasao, Nobuyki

2007-01-01

History and present state of fast reactor was reviewed in series. As a history of fast reactor development in U.S.A. - I, this third lecture presented the dawn of the fast reactor development in the USA. The first fast reactor was the Clementine reactor with plutonium fuels and mercury coolant. The LAMPRE-1 reactor was the first sodium cooled and molten plutonium reactor. Experimental breeder reactor (EBR-1) was the first reactor to produce electricity and four kinds of fuels were loaded. Zero-power reactors were constructed to conduct reactor physics experiments on fast reactors. Today there are renewed interests in fast reactors due to their ability to fission actinides and reduce radioactive wastes. (T. Tanaka)

Moscow DMZ: The story of the international effort to convert Russian weapons science to peaceful purposes

International Nuclear Information System (INIS)

Schweitzer, G.E.

1996-01-01

ISTC created a program to re-employ former Soviet scientists in civilian projects dealing with environmental pollution, nuclear safety, and economic underdevelopment: in short, the legacy of the Soviet system. Glenn E. Schweitzer was the first Executive Director of ISTC, based in Moscow, and his book is additionally a vivid personal account of his impressions of life and work in Moscow as he set about establishing ISTC

Forecasting of passenger traffic in Moscow metro applying artificial neural networks

International Nuclear Information System (INIS)

Ivanov, V.V.; Natsional'nyj Issledovatel'skij Yadernyj Univ. MIFI, Moscow; FKU Rostransmodernizatsiya, Moscow

2016-01-01

Methods for the forecasting of passenger traffic in Moscow metro have been developed using artificial neural networks. To this end, the factors primarily determining passenger traffic in the subway have been analyzed and selected [ru

THE ANALYSIS OF CANCER INCIDENCE AND MORTALITY AMONG THE POPULATION OF THE MOSCOW REGION IN 2014

Directory of Open Access Journals (Sweden)

A. N. Gurov

2015-01-01

Full Text Available Rationale: Analysis of the cancer incidence and mortality in the population is of major importance for planning of measures aimed at improvement of organization of medical care to cancer patients, ensuring high quality and availability of this type of medical care.Aim: To evaluate cancer-related incidence and mortality rates and structure among the population of the Moscow Region depending on patient gender and tumor localization.Materials and methods: The estimation and analysis of incidence and mortality rates was performed based on the Reporting Form of the Federal Statistic Surveillance #7 “Information on disorders related to malignant tumors” in the Moscow Region in 2014. For mortality analysis, including that among pediatric patients, we used data from the State Statistics Service of the Moscow Region.Results: In 2014, there were 25 600 new cases of malignancies diagnosed in the Moscow Region, that corresponded to the incidence rate of 363.2 per 100,000 of the population. The leading types of newly diagnosed tumors in men were prostate cancer, as well as tracheal, bronchial and lung cancers (54.2 and 47.0 per 100,000 of male population, respectively. In women, the highest incidence rates were found for breast and skin cancers (86.0 and 58.9 per 100,000 of female population, respectively. According to the data from Rosstat, in 2014, the overall cancer mortality rate in the Moscow Region was 228.1 per 100,000 of the population. Among the causes of cancer mortality in men, the leading one was tracheal, bronchial and lung cancer (22.2%, followed by stomach cancer (13.3% and prostate cancer (8.1%. In women, the leading cause of cancer mortality was breast cancer (16.6%, followed by ovarian, uterine and cervical cancers (14.1% and stomach cancer (11.4%.Conclusion: Based on the results of medical and statistical analysis of cancer incidence and mortality rates, the main direction of improvement of medical care to cancer patients and the ways

[Clinico-statistical analysis of arterial hypertension complicated with hypertensive crisis in Moscow in 2005-2009].

Science.gov (United States)

Gaponova, N I; Plavunov, N F; Tereshchenko, S N; Baratashvili, V L; Abdurakhmanov, V R; Komissarenko, I A; Filippov, D V; Podkopaev, D V

2011-01-01

Clinicostatistical analysis of arterial hypertension complicated with hypertensive crisis using data of Moscow A.S.Puchkov Station of Urgent and Emergent Medical Aid revealed 14% rise in number of hypertensive crises during the period from 2005 to 2009. Number of hypertensive crises increased among persons of young age (18-35 years). Frequency of cerebrovascular complications of hypertensive crises was age dependent with maximal values among men aged 36-74 years and women older than 75 years.

The U.S. Geological Survey's TRIGA® reactor

Science.gov (United States)

DeBey, Timothy M.; Roy, Brycen R.; Brady, Sally R.

2012-01-01

The U.S. Geological Survey (USGS) operates a low-enriched uranium-fueled, pool-type reactor located at the Federal Center in Denver, Colorado. The mission of the Geological Survey TRIGA® Reactor (GSTR) is to support USGS science by providing information on geologic, plant, and animal specimens to advance methods and techniques unique to nuclear reactors. The reactor facility is supported by programs across the USGS and is organizationally under the Associate Director for Energy and Minerals, and Environmental Health. The GSTR is the only facility in the United States capable of performing automated delayed neutron analyses for detecting fissile and fissionable isotopes. Samples from around the world are submitted to the USGS for analysis using the reactor facility. Qualitative and quantitative elemental analyses, spatial elemental analyses, and geochronology are performed. Few research reactor facilities in the United States are equipped to handle the large number of samples processed at the GSTR. Historically, more than 450,000 sample irradiations have been performed at the USGS facility. Providing impartial scientific information to resource managers, planners, and other interested parties throughout the world is an integral part of the research effort of the USGS.

Socio-Structural Barriers, Protective Factors, and HIV Risk Among Central-Asian Female Migrants in Moscow

Directory of Open Access Journals (Sweden)

Christopher Zabrocki

2013-07-01

Full Text Available Objective: This study aimed to build formative knowledge on socio-structural barriers, protective factors, and HIV sexual risk amongst Central-Asian female migrants in Moscow. Methods: Data collection included ethnographic interviews in Moscow with a purposive sample of 30 unmarried female migrants, 15 from Kyrgyzstan and 15 from Tajikistan. Results: Study participants reported difficulties with acquiring documents for legal status, financial insecurity, discrimination, sexual harassment, and lack of support. Based on analysis of the cases, one pathway linked lack of legal documentation and instrumental support with elevated sexual risk. Another pathways linked traditional cultural attitudes with both no and moderate sexual risk. Conclusion: Future HIV prevention efforts with Central Asian female migrants in Moscow should be multilevel and include: increasing HIV and prevention knowledge and skills, promoting condom use with regular partners, identifying and supporting cultural attitudes that protect against HIV sexual risk behaviors, facilitating legal status, building community support, and increasing economic options.

WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

Prospects of closed-circuit television in detecting surface defects

International Nuclear Information System (INIS)

Kaisler, L. et al.

The use is discussed of closed-circuit television for optical in-service testing of surface defects of nuclear reactors. Experience gained by UJV Rez with in-service testing of the WWR-S reactor is briefly reported. Main attention is devoted to recognizability of defects and to determining the fundamental conditions of the applicability and limitations of the closed-circuit television method. In experiments, resolution of the method was tested and the role of the human factor was assessed in evaluating the results. The need was stressed of thorough training of operators. Based on the experiments conducted, considerations are presented regarding modifications of the individual elements of the tv chain aimed at improved quality of information and a limited role of the observer. (B.S.)

Hope dies last: two aspects of hope in contemporary Moscow

NARCIS (Netherlands)

Zigon, J.

2009-01-01

The concept of hope has, for the most part, been neglected by anthropologists. Recently, however, hope has been analyzed by two prominent anthropologists who view it either as a passive attitude or a future-oriented stance toward a good. My research in Moscow, Russia, suggests that hope is not so

Quantum electronics and Moscow State University's Khokhlov-Akhmanov school of coherent and nonlinear optics

International Nuclear Information System (INIS)

Makarov, V.A.

2004-01-01

The aim of the report is to describe the history of the Moscow University Coherent and Nonlinear Optics School headed by R.V. Khokhlov and S.A. Akhmanov being a part of the history of the Russian efforts to investigate into quantum electronics. The reports describes briefly the most significant results of the mentioned School activity, in particular, thermonuclear reactions initiated by laser pulses in plasma; the procedure to accelerate electrons up to 1 GeV using the present-day lasers; the nonlinear-optical analogues of the Faraday and the Kerr effects [ru

[Current status and trends in the health of the Moscow population].

Science.gov (United States)

Tishuk, E A; Plavunov, N F; Soboleva, N P

1997-01-01

Based on vast comprehensive medical statistical database, the authors analyze the health status of the population and the efficacy of public health service in Moscow. The pre-crisis tendencies and the modern status of public health under modern socioeconomic conditions are noted.

The Conference in the Moscow Kremlin State Museums “Historical Weapons in Museums and Private Collections”

OpenAIRE

Sergey P. Orlenko

2017-01-01

In November 2016 in the Moscow Kremlin State Historical and Cultural Museum and Heritage Site in the framework of events dedicated to the 210th anniversary of the Armoury Chamber museum, an international conference “Historical weapons in museums and private collections”. This scientific forum continued the tradition of conferences held in the Moscow Kremlin Museums in 1999-2007. The participants of this forum discussed a number of priority topics for the studies of the weapon collection h...

Ethnization of the collective consciousness of Russians in the Moscow region: An expert assessment of the process

Directory of Open Access Journals (Sweden)

A A Onosov

2016-12-01

Full Text Available Based on the existing scientific approaches, the article continues considering the ethnicization of the mass consciousness of Russian citizens, which takes place under the internal and international labor migration. The article presents the results of the situational analysis and humanitarian expertise of the Russian population’s ethnic identity formation in Moscow and the Moscow Region as Russia’s main attractors of international labor migrants. Based on the statistical data, public opinion survey data and expert assessments, the authors present an empirical model of ethnic identity with theoretical validation and interpretation provided. The study of ethnic identity is accompanied by an insight into the causes and factors of the Russians’ collective consciousness ethnicization, explication of the real content of this process with regard to specific conditions of its manifestation contributing to intensification or weakening of ethnicization. Then the ethnicization of consciousness is considered in the broad context of global ethnic-social dynamics: as a part and reflection of the overall civilizational process determining that the rise of ethnic self-awareness in various social groups and regional communities, not only in Russia, but also far abroad, is a forced response to the globalization as it is practiced in the contemporary world.

Ways of prevention of accidents at atomic reactor

International Nuclear Information System (INIS)

Takibaev, Zh. S.

2000-01-01

The methods proposed to prevent such a move are discussed as well as the scheme of their realization. To improve reactor operation characteristics the safeguard system of quick response is used. Nowadays direct-acting safeguard system (DAS) is to be worked out. It reacts on the main cause of the accident the rapid growth of neutron flux. The time delay of combined gas-liquid DAS unit and fluctuation of nuclear power are calculated. The DAS grid disposed in active zone is developed. Fissile materials are employed because their heating almost immediately follows the growth of neutron flux. There are several systems proposed: uranium bimetal dispersed absorber, uranium hexafluoride liquid absorber (gadolinium solution).Neutronic calculation is done for WWR-1000. The model suggested acts over 0.12 sec. after reactivity swing of 0.003, becomes a 'safety rod' over time delay of 1.49 sec. and cleans itself over 3.0 sec. after.The study presents its improved version. Absorber is injected dose by dose and thus negative reactivity is introduced discretely. Accordingly the same system can act by extracting some parts of fuel from the core. Bimetal safeguard systems are studied. The methods suggested above seem proved in the sense of strengthening nuclear energy development in the future. The problem of DAS and other safeguard systems to prevent reactivity accidents for various reactor types including computer simulation is set to be studied further

WEB GIS SUPPORT OF ENVIRONMENTAL-GEOGRAPHICAL ASSESSMENT OF LAND RESOURCES IN THE NEW MOSCOW TERRITORY

Directory of Open Access Journals (Sweden)

I. K. Lurie

2016-01-01

Full Text Available In 2011, the area of Moscow, one of the largest urbanized megacomplexes, increased by more than 1440 km2 due to the accession of the Troitsky and Novomoskovsky аutonomous districts. That called for conducting detailed comprehensive environmental-geographical research, integrated assessment of the lands state of the annexed territories and the corresponding cartographic support to maintain further socio-economic development of the area. In the same 2011, at Lomonosov Moscow State University, MSU Geoportal started working as a new instrument of collective access and processing of spatial data to provide innovative research and educational activities with relevant materials of remote sensing data of the Earth and analytical tools for conducting geographic data analysis in the Geoportal environment. Cartographic support of the «New Moscow» project has been realized by means of collection, processing and systematization of geo-spatial data, formation of a geo-data bank and a series of thematic maps, created on its basis. It has been decided to develop Web GIS software by creating a geo-resource on the existed MSU Geoportal, which main purpose is forming the information and cartographic support for the New Moscow territories, based on the profound study of different components of the environment and affecting factors. The realization of this project has required the creation of a few dozens of maps for the comprehensive ecological and geographical assessment of the lands of the new annexed territories because of their status, economic and socio-geographical state changes.

ASSORTMENT AND PRICE POLICY OF STATE PHARMACIES OF MOSCOW

Directory of Open Access Journals (Sweden)

I. V. Voronovich

2015-01-01

Full Text Available The most important index which determines the level and quality of pharmaceutical support is the correspondence of assortment to consumers needs. Assortment policy is determined by the functions implemented, and the problems of organization of pharmaceutical support of medicinal organizations within the frameworks of substantiated and reasonable expenditure of budget funds, and affordable pharmaceutical support of the population. The purpose of this research was the study of assortment and price policy of state pharmacies of Moscow. The objects were pharmacy subdivisions of state pharmacy network of Moscow. We have used sociological methods (questionnaire, interviewing, method of marketing, and statistic analysis. We have studied the assortment structure, assortment groups’ distribution on price segments. We have established that the drugs, more than 60% of which are foreign-made occupied more than a half of the assortment. Medicinal drugs in 50 rubles price spectrum occupy the biggest share of pharmacy assortment. Distribution within every assortment group revealed that more than a half of drugs are in average price spectrum from 50 to 500 rubles. Average charge for VED amounts to 21.87%, and for drugs which were not included in VED list – 34.07%. The charge for the goods, the price of which is not regulated, trade charge is more. 

Les couleurs de Moscou et de Saint-Pétersbourg The colours of Moscow and Saint Petersburg

Directory of Open Access Journals (Sweden)

Andréi Éfimov

2008-05-01

Full Text Available Moscou et Saint-Pétersbourg ont connu une évolution chromatique similaire mais les différences en matière de plan, d’urbanisme et d’influences culturelles, et leurs rôles alternés de capitale ont déterminé leurs particularités chromatiques propres. Le Moscou en bois du xiiie siècle s’est enrichi d’un ensemble de cathédrales blanches aux coupoles dorées entourées par la muraille en brique rouge du Kremlin. Le style baroque a introduit dans l’architecture de Moscou et de Saint-Pétersbourg les couleurs bleu foncé, orange et verte. À l’époque du classicisme, on utilisait la palette officielle de teintes pastel à dominante ocre. L’achromatisme devient ensuite un trait distinctif de l’éclectisme en Russie. Au début du XXe siècle, l’Art nouveau ranime les villes grâce aux couleurs verte, orange et violette. Dans les années 1920 et 1930, les constructivistes utilisent les tons gris mais tentent d’élaborer un code chromatique homogène. L’architecture soviétique, quant à elle, reprend l’esthétique du classicisme « ocre ». La construction de masse des années 1960 aux années 1980 méconnaît la couleur, mais à la charnière des XXe et XXIe siècles apparaissent des approches professionnelles qui visent à créer un milieu chromatique similaire pour les deux villes.Moscow and Saint Petersburg experienced similar evolutions in colour, but the differences in their plans, urbanity and cultural influences, and their alternating roles as capitals, determined the particularities of their palettes. The wooden Moscow of the thirteenth century was enriched by a group of white cathedrals with golden domes, surrounded by the red brick wall of the Kremlin. Baroque, as an architectural style, introduced Moscow and Saint Petersburg to the colours dark blue, orange, and green. The official palette of classicism was pastel, predominantly ochre, while the period of eclecticism in Russia was achromatic. At the

Training activities at FSUE 'RADON' and Lomonosov's Moscow state university under practical arrangements with IAEA

International Nuclear Information System (INIS)

Batyukhnova, O.G.; Karlina, O.K.; Neveykin, P.P.; Kalmykov, S.N.; Ojovan, M.I.

2013-01-01

The International Education Training Centre (IETC) at Moscow Federal State Unitary Enterprise (FSUE) 'Radon', in co-operation with the International Atomic Energy Agency (IAEA), has developed expertise and provided training to waste management personnel for the last 15 years. Since 1997, the educational system of the enterprise with the support of the IAEA has acquired an international character: more than 470 experts from 35 countries - IAEA Member States completed the professional development. Training is conducted at various thematic courses or fellowships for individual programs and seminars on IAEA technical projects. In June 2008 a direct agreement (Practical Arrangements) has been signed between FSUE 'Radon' and the IAEA on cooperation in the field of development of new technologies, expert's advice to IAEA Member States, and, in particular, the training of personnel in the field of radioactive waste management (RWM), which opens up new perspectives for fruitful cooperation of industry professionals. A similar agreement - Practical Arrangements - has been signed between Lomonosov's MSU and the IAEA in 2012. In October 2012 a new IAEA two-weeks training course started at Lomonosov's MSU and FSUE 'Radon' in the framework of the Practical Agreements signed. Pre-disposal management of waste was the main topic of the courses. The paper summarizes the current experience of the FSUE 'Radon' in the organization and implementation of the IAEA sponsored training and others events and outlines some of strategic educational elements, which IETC will continue to pursue in the coming years. (authors)

Characteristics of pathogenic Neisseria meningitidis in Moscow: prevalence of 'non-European' strains

NARCIS (Netherlands)

Koroleva, Irina S.; Platonov, Alexander E.; van der Ende, Arie; Kuijper, Ed; Dankert, Jacob

1998-01-01

OBJECTIVE: To investigate the distribution of serogroups, serotypes and subtypes, and susceptibility to antibiotics, of 75 strains isolated from patients with systemic meningococcal disease in Moscow in 1993--95. RESULTS: In contrast to the situation in most European countries, 21% of group A

Soil technological and other ecological aspects of state of trees in Moscow

NARCIS (Netherlands)

Makarova, O.V.

2003-01-01

Moscow is one of the world's largest cities. Its height levels are such that the urban vegetation generally cannot benefit from groundwater. The natural soil is strongly modified by anthropogenic influences. Examples are the construction activities for the underground railways (metro) which reached

What's new in magnetism (Scientific session of the Physical Sciences Division of the Russian Academy of Sciences, 27 May 2015)

International Nuclear Information System (INIS)

2015-01-01

A scientific session of the Physical Sciences Division of the Russian Academy of Sciences (RAS), 'What's new in magnetism?', was held in the conference hall of the Lebedev Physical Institute, RAS, on 27 May 2015. The papers collected in this issue were written based on talks given at the session: (1) Kalashnikova A M, Pisarev R V (Ioffe Physical-Technical Institute, RAS, St. Petersburg), Kimel A V (Radboud University Nijmegen, Institute for Molecules and Materials, The Netherlands; Moscow State Technical University of Radio Engineering, Electronics and Automation, Moscow) 'Ultrafast optomagnetism'; (2) Pyatakov A P, Sergeev A S, Nikolaeva E P, Kosykh T B, Nikolaev A V (Lomonosov Moscow State University, Moscow), Zvezdin K A (Prokhorov General Physics Institute, RAS, Moscow; Kintech Laboratory Ltd, Moscow), Zvezdin A K (Prokhorov General Physics Institute, RAS, Moscow; Lebedev Physical Institute, RAS, Moscow) 'Micromagnetism and topological defects in magnetoelectric media'; (3) Mukhin A A, Kuzmenko A M, Ivanov V Yu (Prokhorov General Physics Institute, RAS, Moscow), Pimenov A V, Shuvaev A M, Dziom V E (Institute of Solid State Physics, Vienna University of Technology, Vienna, Austria) 'Dynamic magnetoelectric phenomena within electromagnons in rare-earth borate multiferroics'; (4) Nikitov S A (Kotel'nikov Institute of Radio Engineering and Electronics, RAS, Moscow; Moscow Institute of Physics and Technology (State University), Dolgoprudnyi, Moscow region; Chernyshevskii Saratov State University, Saratov), Kalyabin D V, Osokin S A (Kotel'nikov Institute of Radio Engineering and Electronics, RAS, Moscow; Moscow Institute of Physics and Technology (State University), Dolgoprudnyi, Moscow region), Lisenkov I V (Kotel'nikov Institute of Radio Engineering and Electronics, RAS, Moscow; Moscow Institute of Physics and Technology (State University), Dolgoprudnyi, Moscow region; Oakland University, Rochester, USA

Characteristics of Winter Surface Air Temperature Anomalies in Moscow in 1970-2016 under Conditions of Reduced Sea Ice Area in the Barents Sea

Science.gov (United States)

Shukurov, K. A.; Semenov, V. A.

2018-01-01

On the basis of observational data on daily mean surface air temperature (SAT) and sea ice concentration (SIC) in the Barents Sea (BS), the characteristics of strong positive and negative winter SAT anomalies in Moscow have been studied in comparison with BS SIC data obtained in 1949-2016. An analysis of surface backward trajectories of air-particle motions has revealed the most probable paths of both cold and warm air invasions into Moscow and located regions that mostly affect strong winter SAT anomalies in Moscow. Atmospheric circulation anomalies that cause strong winter SAT anomalies in Moscow have been revealed. Changes in the ways of both cold and warm air invasions have been found, as well as an increase in the frequency of blocking anticyclones in 2005-2016 when compared to 1970-1999. The results suggest that a winter SIC decrease in the BS in 2005-2016 affects strong winter SAT anomalies in Moscow due to an increase in the frequency of occurrence of blocking anticyclones to the south of and over the BS.

The socio-demographic aspects of building social infrastructure in the city of Moscow

Directory of Open Access Journals (Sweden)

Strashnova Yuliya gennad’evna

2018-03-01

trends in change of the main socio-demographic measure groups affecting the social infrastructure in Moscow were determined. Conclusions: a detailed study of the existing demographic peculiarities of the city, including sociological survey; demographic forecasting makes it possible to determine the promising trends in the population’s consumption of services. The design of social infrastructure throughout the city should be based on research findings which would provide the sustainable development of social infrastructure, the optimal balanced load of social facilities.

Russian RBMK reactor design information

International Nuclear Information System (INIS)

1993-11-01

This document concerns the systems, design, and operations of the graphite-moderated, boiling, water-cooled, channel-type (RBMK) reactors located in the former Soviet Union (FSU). The Russian Academy of Sciences Nuclear Safety Institute (NSI) in Moscow, Russia, researched specific technical questions that were formulated by the Pacific Northwest Laboratory (PNL) and provided detailed technical answers to those questions. The Russian response was prepared in English by NSI in a question-and-answer format. This report presents the results of that technical exchange in the context they were received from the NSI organization. Pacific Northwest Laboratory is generating this document to support the US Department of Energy (DOE) community in responding to requests from FSU states, which are seeking Western technological and financial assistance to improve the safety systems of the Russian-designed reactors. This report expands upon information that was previously available to the United States through bilateral information exchanges, international nuclear society meetings, International Atomic Energy Agency (IAEA) reactor safety programs, and Research and Development Institute of Power Engineering (RDIPE) reports. The response to the PNL questions have not been edited or reviewed for technical consistency or accuracy by PNL staff or other US organizations, but are provided for use by the DOE community in the form they were received

Text of the joint USSR-USA statement following the summit meeting in Moscow, 29 May - 2 June 1988

International Nuclear Information System (INIS)

1988-06-01

The document reproduces the text of the joint USSR-USA statement following the summit meeting between the President of the United States, Ronald W. Reagan and the General Secretary of the Central Committee of the Communist Party of the Soviet Union, Mikhail S. Gorbachev, held in Moscow between May 29 - June 2, 1988. It refers to the arms control (including nuclear weapons), human rights and humanitarian concerns, regional issues, bilateral affairs and further meetings

Requirements of Employers for Young Specialists and Issues of Their Training at the Educational Institutions: Regional Specificity of Moscow

Directory of Open Access Journals (Sweden)

Vyacheslav Nikolaevich Bobkov

2016-12-01

Full Text Available The subject-matter of the article is the study of the peculiarities of the youth labour market in such a specific region of Russia as the city of Moscow. The topic of the work is connected to the adaptation of young specialists training system to the regional requirements of the employers of Moscow. The main hypothesis of the research assumes that Moscow is the atypical region of Russia and it is inexpedient to apply criteria and methodological approaches, which are standard for our country, to its labour market. As a method of the research, a selective survey of key employers of Moscow and respondents aged from 14 till 30 years has been used. The data of the sociological survey conducted by the authors have allowed to establish the following features of the researched region: a respectively low level of youth unemployment compared with the whole Russia; focusing of employers on such features of personnel as a good communicative skills learning ability, professional knowledge and competences. Moscow employers don’t pay significant attention to such characteristics of young specialists as language and computer skills, computer knowledge and the diploma of a prestigious educational institution. The main difficulties in finding employment for young specialists in the city of Moscow are: overestimated salary expectations; the weak professional training level and unwillingness, in fact, to work. As a result of the survey, the practical offers have been formulated. There are two directions of their application: the offers focused on the behaviour of the youth at a stage of their training and those offers focused on the increase of a practical component of the activity of professional educational institutions. The authors came to conclusions about the need of a deep orientation of educational institutions to the applied training for specialists, of practical workers for teaching special disciplines, the development by future specialists their

The Professional Education of Handicapped People in Moscow: Opportunities and Obstacles

Science.gov (United States)

Chadova, T. A.

2014-01-01

In Moscow, one priority area of urban social policy has focused on the formation of equal opportunities for handicapped people and those with impaired health in the process of their integration into all spheres of life and activity, including professional education. The year 2009 was declared to be the Year of Equal Opportunities. The…

The Conference in the Moscow Kremlin State Museums “Historical Weapons in Museums and Private Collections”

Directory of Open Access Journals (Sweden)

Sergey P. Orlenko

2017-03-01

Full Text Available In November 2016 in the Moscow Kremlin State Historical and Cultural Museum and Heritage Site in the framework of events dedicated to the 210th anniversary of the Armoury Chamber museum, an international conference “Historical weapons in museums and private collections”. This scientific forum continued the tradition of conferences held in the Moscow Kremlin Museums in 1999-2007. The participants of this forum discussed a number of priority topics for the studies of the weapon collection history in the Kremlin. These topics were relevant to the national and world studies of weaponology as a whole. In addition to general issues of the history of arms and armour, a number of reports were devoted to the functioning of the historical centers of arms production, weapons collections in Russia and abroad, particular items, as well as the activities of gunsmiths, designers of weapons. The conference was attended by representatives of more than 20 Russian and foreign museums, 14 academic and university research centers and institutions, private collectors and lovers of ancient weapons. During the three days of the conference 36 reports were presented and discussed. Organizers of the conference highlighted a number of reports including new attributions of the items from the Kremlin collections. The conference program is available on the official website of the Moscow Kremlin State Museums. The conference results were published as a collection of proceedings. The weaponology forum in the Kremlin will be held annually. The Moscow Kremlin Museums invite researchers of historical weapons, museum employees and collectors to the active cooperation.

An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Rosenthal, Murray Wilford [ORNL

2009-08-01

The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

Russian Chronicles and Diplomatic Documents on the Moscow-Crimean-Kazan Relations at the end of the 15th – the first half of the 16th centuries

Directory of Open Access Journals (Sweden)

A.V. Aksanov

2016-12-01

Full Text Available Research objective: The article analyzes chronicles’ and diplomatic information about joining of the Kazan Khanate to the Moscow-Crimean alliance in 1487, about the joint actions of these three states against the Great Horde in 1491–1492 and about the Moscow-Crimean-Kazan peace negotiations of 1537–1542. Research materials: Special attention is given to inconsistencies in the sources that often has not been considered in the historiography. In official chronicles the campaign of 1487 marks the submission of Kazan. Whereas diplomatic documents represent the expedition of the Moscow troops of 1487 as the military aid of Ivan III to the khan Mahomed-Amin in his struggle for the Kazan throne. According to official chronicles, in 1491 the Kazan khan warred against the Horde on the side of the Crimea by the order of the Moscow sovereign. In turn, in the Novgorod chronicle the campaign of 1491 is represented as the act of the help of Ivan III to the sultan Satylgan and khan Mahomed-Amin in their fight against the Great Horde. The data of diplomatic documents are consistent with the estimate of the Novgorod chronicle. Research results and novelty: Therefore, it can be assumed that Mahomed-Amin participated in the war against the Great Horde as he was in allied relations with Moscow and the Crimea. Diplomatic documents confirm the point of view of official chroniclers of rather intermediary role of the Crimean khan in the Moscow-Kazan negotiations of 1537–1542. Thus, they display a completely different character of the relations between Moscow, the Crimea and Kazan. The Moscow boyars demanded from the Kazan khan to recognize the supremacy of the Moscow sovereign. In turn, the governors of the Crimea and Kazan called for equal relations. Possibly, this contradiction was the main reason for a failure of the peace negotiations.

Suburbanization and sustainability in metropolitan Moscow.

Science.gov (United States)

Mason, Robert J; Nigmatullina, Liliya

2011-01-01

Although Soviet-era urban-growth controls produced relatively sustainable metropolitan development patterns, low-density suburban sprawl has accelerated markedly in modern Russia. Distinctive features of Moscow's development history are its greenbelt, which dates from 1935 and is becoming increasingly fragmented, proliferation of satellite cities at the urban fringe, conversion of seasonal dachas into full-time residences, the very exclusive Rublevo Uspenskoe Highway development, and today's crippling traffic congestion. The recent economic crisis has slowed development and actually increased the supply of “economy-class” single-family homes, for which there is much pent-up desire but insufficient credit availability to meet the demand. A renewed commitment to sustainability's triple bottom line—environmental quality, equity, and economic prosperity—will require greater government transparency and fairness, stronger planning controls, and an expanded public transportation system.

Ocular oxyspirurosis of primates in zoos: intermediate host, worm morphology, and probable origin of the infection in the Moscow zoo

Directory of Open Access Journals (Sweden)

Ivanova E.

2007-12-01

Full Text Available Over the last century, only two cases of ocular oxyspirurosis were recorded in primates, both in zoos, and two species were described: in Berlin, Germany, Oxyspirura (O. conjunctivalis from the lemurid Microcebus murinus, later also found in the lorisid Loris gracilis; in Jacksonville, Florida, O. (O. youngi from the cercopithecid monkey Erythrocebus patas. In the present case from the Moscow zoo, oxyspirurosis was recorded in several species of Old World lemuriforms and lorisiforms, and some South American monkeys. i The intermediate host was discovered to be a cockroach, as for O. (O. mansoni, a parasite of poultry. The complete sequence identity between ITS-1 rDNA from adult nematodes of the primate and that of the larval worms from the vector, Nauphoete cinerea, confirmed their conspecificity. ii Parasites from Moscow zoo recovered from Nycticebus c. coucang were compared morphologically to those from other zoos. The length and shape of the gubernaculum, used previously as a distinct character, were found to be variable. However, the vulvar bosses arrangement, the distal extremity of left spicule and the position of papillae of the first postcloacal pair showed that the worms in the different samples were not exactly identical and that each set seemed characteristic of a particular zoo. iii The presence of longitudinal cuticular crests in the infective stage as well as in adult worms was recorded. Together with several other morphological and biological characters (long tail and oesophagus, cockroach vector, this confirmed that Oxyspirura is not closely related to Thelazia, another ocular parasite genus. iv The disease in the Moscow zoo is thought to have started with Nycticebus pygmaeus imported fromVietnam, thus the suggestion was that Asiatic lorisids were at the origin of the Moscow set of cases. The natural host(s for the Berlin and Jacksonville cases remain unknown but they are unlikely to be the species found infected in zoos

IDENTIFICATION OF PATIENTS WITH FAMILIAL HYPERCHOLESTEROLEMIA IN THE RUSSIAN POPULATION USING THE EXAMPLE OF MOSCOW CITY AND MOSCOW REGION

Directory of Open Access Journals (Sweden)

I. V. Sergienko

2018-01-01

Full Text Available Aim. To estimate the prevalence of familial hypercholesterolemia (FH in a sample of Moscow city and Moscow region patients with hypercholesterolemia (HCh based on lipid spectrum and instrumental methods.Material and methods. The study included two samples of patients (age >18 years, with total cholesterol (TCh level ≥7.5 mmol/l and/or low-density lipoprotein (LDL cholesterol level ≥4.9 mmol/l. First sample (n=60 was included to determine secondary hyperlipidemia frequency in newly diagnosed HCh, with measurement of thyroid hormone, glucose and glycated hemoglobin (HbA1c levels. Patients of the second sample (n=432 from Russian registry of FH (RuFH were studied by drug therapy assessment, lipid profile measurements, calculation of FH probability according to Dutch and British criteria, carotids duplex scanning (CDS, cardiac perfusion single-photon emission computed tomography (SPECT/CT using rest/stress protocol.Results. The incidence of secondary dyslipidemia due to diabetes or hypothyroidism in patients with severe HCh was 18.3%. Monotherapy with atorvastatin (34.2% or rosuvastatin (31.8%, combined therapy with statins and other lipid-lowering drugs (24.4% prevails in the structure of lipidlowering therapy in patients with severe HCh. The frequency of "definite" FH according to Dutch criteria in HCh patients was 15.3%, "probable" – 18.1%. Patients with definite FH diagnosis showed higher level of TCh (p<0.001, LDL cholesterol (p<0.001, proprotein convertase subtilisin/kexin type 9 (p<0.001, lower high-density lipoprotein (HDL; p=0.02, and triglycerides (p<0.001. At that HDL cholesterol levels differed only in patients treated with lipid-lowering drugs. Patients with lipid-lowering therapy had significantly higher values of total stenosis percent, the number of plaques, intima-media complex thickness (p<0.001. Patients with lipid-lowering therapy with a definite and probable FH diagnosis had significantly worse values of CDS parameters

Social and structural risks for HIV among migrant and immigrant men who have sex with men in Moscow, Russia: implications for prevention.

Science.gov (United States)

Wirtz, A L; Zelaya, C E; Peryshkina, A; Latkin, C; Mogilnyi, V; Galai, N; Dyakonov, K; Beyrer, C

2014-01-01

Moscow has a large population of immigrants and migrants from across the Former Soviet Union. Little is studied about men who have sex with men (MSM) within these groups. Qualitative research methods were used to explore identities, practices, and factors affecting HIV prevention and risks among immigrant/migrant MSM in Moscow. Nine interviews and three focus group discussions were conducted between April-June 2010 with immigrant/migrant MSM, analyzed as a subset of a larger population of MSM who participated in qualitative research (n=121). Participants were purposively selected men who reported same sex practices (last 12 months). Migrants were men residing in Moscow but from other Russian regions and immigrants from countries outside of Russia. A socioecological framework was used to describe distal to proximal factors that influenced risks for HIV acquisition. MSM ranged from heterosexual to gay-identified. Stigma and violence related to homophobia in homelands and concerns about xenophobia and distrust of migrants in Moscow were emerged as key themes. Participants reported greater sexual freedom in Moscow but feared relatives in homelands would learn of behaviors in Moscow, often avoiding members of their own ethnicity in Moscow. Internalized homophobia was prevalent and linked to traditional sexual views. Sexual risks included sex work, high numbers of partners, and inconsistent condom use. Avoidance of HIV testing or purchasing false results was related to reporting requirements in Russia, which may bar entry or expel those testing positive. HIV prevention for MSM should consider immigrant/migrant populations, the range of sexual identities, and risk factors among these men. The willingness of some men to socialize with immigrants/migrants of other countries may provide opportunities for peer-based prevention approaches. Immigrants/migrants comprised important proportions of the MSM population, yet are rarely acknowledged in research. Understanding their

Preliminary results with the CLAMSUD pion spectrometer at the Moscow Meson Factory

International Nuclear Information System (INIS)

Badala, A.; Barbera, R.; Librizzi, F.; Longhitano, A.; Nicotra, D.; Palmeri, A.; Pappalardo, G.S.; Riggi, F.; Santoro, A.; Turrisi, R.; Aseev, V.; Feschenko, A.; Gavrilov, Yu.; Guber, F.; Golubeva, M.; Karavicheva, T.; Kurepin, A.; Ostroumov, P.; Potapov, V.; Tiflov, V.; Zhuravlev, A.

1995-01-01

A magnetic spectrometer has been recently installed at the new proton beam facility of the Moscow Meson Factory, to study charged pion production from proton-nucleus interactions at 200-400 MeV bombarding energy. Preliminary reults obtained during the first runs are reported. The planned physics program is also discussed. (orig.)

Assessment methodology applicable to safe decommissioning of Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Baniu, O.; Vladescu, G.; Vidican, D.; Penescu, M.

2002-01-01

The paper contains the results of research activity performed by CITON specialists regarding the assessment methodology intended to be applied to safe decommissioning of the research reactors, developed taking into account specific conditions of the Romanian VVR-S Research Reactor. The Romanian VVR-S Research Reactor is an old reactor (1957) and its Decommissioning Plan is under study. The main topics of paper are as follows: Safety approach of nuclear facilities decommissioning. Applicable safety principles; Main steps of the proposed assessment methodology; Generic content of Decommissioning Plan. Main decommissioning activities. Discussion about the proposed Decommissioning Plan for Romanian Research Reactor; Safety risks which may occur during decommissioning activities. Normal decommissioning operations. Fault conditions. Internal and external hazards; Typical development of a scenario. Features, Events and Processes List. Exposure pathways. Calculation methodology. (author)

Radiation research of materials using irradiation capsules

International Nuclear Information System (INIS)

Chamrad, B.

1976-01-01

The methods are briefly characterized of radiation experiments on the WWR-S research reactor. The irradiation capsule installed in the reactor including the electronic instrumentation is described. Irradiated samples temperature is stabilized by an auxiliary heat source placed in the irradiation space. The electronic control equipment of the system is automated. In irradiation experiments, experimental and operating conditions are recorded by a digital measuring centre with electric typewriter and paper tape data recording and by an analog compensating recorder. The irradiation experiment control system controls irradiated sample temperature, the supply current size and the heating element temperature of the auxiliary stabilizing source, inert and technological pressures of the capsule atmosphere and the thermostat temperature of the thermocouple junctions. (O.K.)

Inelastic scattering of 275 keV neutrons by silver

International Nuclear Information System (INIS)

Litvinsky, L.L.; Zhigalov, Ya.A.; Krivenko, V.G.; Purtov, O.A.; Sabbagh, S.

1997-01-01

Neutron total, elastic and inelastic scattering cross-scattering of Ag at the E n = 275 KeV neutron energy were measured by using the filtered neutron beam of the WWR-M reactor in Kiev. The d-neutron strength function S n2 of Ag was determined from the analysis of all available data in the E n ≤ keV energy region on neutron inelastic scattering cross-sections with excitation of the first isomeric levels I π m = 7/2 + , E m ∼ 90 keV of 107,109 Ag: S n2 = (1.03 ± 0.19) · 10 -4 . (author). 10 refs, 3 figs

From Moscow to Copenhagen. Russian views on climate change; Van Moskou naar Kopenhagen. Russische vergezichten op klimaatverandering

Energy Technology Data Exchange (ETDEWEB)

Van Agt, C.

2009-11-15

To fuel economic recovery and growth Russia will increase oil and gas supplies to the industrialized market economies of the Euro Atlantic in the West and the Asian Pacific growth economies in the East. Despite the post-Soviet economic collapse, Russia is still among the largest emitters of greenhouse gases, after the United States, China and the European Union. Moscow's foreign economic policies are spearheaded by natural gas, a clean burning fossil fuel pivotal to world economic transition to a less carbon intensive 'green' model. Despite the adoption of a new climate-change strategy and Russia's acknowledgement that it must play a responsible role in the run up to the Climate Change Summit in Copenhagen, Moscow's policy position is still aloof, due to geopolitical undercurrents and Russia's particular position in debates on the nature and cost of mitigation measures between industrialized countries and the emerging economies of the developing world. [Dutch] Door het economisch herstel en de economische groei zal Rusland leveringen van olie en gas aan de geindustrialiseerde markt economieen verhogen. Ondanks de economische achteruitgang van de voormalige Sovjet Unie is Rusland, na de Verenigde Staten, China en de Europese Unie, nog steeds een van de grootste uitstoters van broeikasgassen. Het buitenlandse economische beleid van Moskou wordt sterk bepaald door aardgas, dat een belangrijke rol speelt in de mondiale economische overgang naar een minder koolstofintensief 'groen' model. Ondanks de goedkeuring van een nieuw klimaat-verandering-strategie en de Russische erkenning dat het een verantwoordelijke rol moet spelen in de aanloop naar de klimaatveranderingtop in Kopenhagen, is het Russische beleid nog steeds afstandelijk, als gevolg van geopolitieke onderstromen en de bijzondere positie die Rusland inneemt in de debatten over de aard en de kosten van mitigerende maatregelen tussen de geindustrialiseerde landen en de

Enhancement the physical protection system of the WWR-SM reactor at Institute of Nuclear Physics of Academy of Science of the Republic of Uzbekistan

International Nuclear Information System (INIS)

Karabaev, Kh.Kh.; Rakhimbaev, A.T.; Rakhmanov, A.B.; Salikhbaev, U.S.; Yuldashev, B.S.

2004-01-01

Full text: Joining of the Republic of Uzbekistan to Non-Proliferation Treaty required the revision of nuclear fuel protection system and radioactive sources from illegal access in all stages of work with nuclear materials. One of the primary technical actions of ensuring non-proliferation of nuclear materials is physical protection. The project was worked out on upgrading and enhancement of the physical protection of the reactor building. In cooperation with Sandia National Laboratory and support of the Department of Energy (DOE) USA The first stage of the physical protection upgrading provided for fresh fuel protection: - the new fresh fuel storage room was built and equipped with the modern control and detection system, - the reactor building was equipped with detection devices and access control, - the central alarm station (CAS) has been built and equipped with computer control and observing system, - code access system has been implemented. The first stage of upgrading of physical protection system was accomplished for 4 months, and put into operation in 1996. The second stage of physical protection system modernization included the construction of the second barrier of the physical protection, equipping it with observation and control devices and also extension of the CAS. The perimeter around the reactor building was cleaned from trees, bushed and in a short time a two-fence barrier was erected. The access control point provided the secured intensified control of the access to the reactor territory. The physical protection system was supplied with equipment for safeguard and TV observation of perimeter, access control to the territory of the reactor: - the CAS was extended and computer observation control system was upgraded, - the badge station has been constructed, equipped and set up, - all doors, windows, reactor hall gate have been replaced by strengthened metal ones, - uninterruptible power supply (UPS) and diesel-generator have been installed, - the

Final report. U.S. Department of Energy University Reactor Sharing Program

Energy Technology Data Exchange (ETDEWEB)

Bernard, John A

2003-01-21

Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

Review the Moscow wholesale market meat delicacies and sausages

OpenAIRE

Sidorchuk, Roman

2010-01-01

The main goal of our marketing research is to review the status of the Moscow wholesale market deli meats in 2005. The study is based on the method of the expert survey, a method that includes: selection of experts survey form, the definition of the structure and strength of the expert group, the development of the methodology of the study, survey, a list of problems. As experts in the survey attended by leaders and experts who know the state of the market of meat products. Also in the study ...

Handgrip strength and its prognostic value for mortality in Moscow, Denmark, and England

DEFF Research Database (Denmark)

Oksuzyan, Anna; Demakakos, Panayotes; Shkolnikova, Maria

2017-01-01

BACKGROUND: This study compares handgrip strength and its association with mortality across studies conducted in Moscow, Denmark, and England. MATERIALS: The data collected by the Study of Stress, Aging, and Health in Russia, the Study of Middle-Aged Danish Twins and the Longitudinal Study of Aging...... Danish Twins, and the English Longitudinal Study of Ageing was utilized. RESULTS: Among the male participants, the age-standardized grip strength was 2 kg and 1 kg lower in Russia than in Denmark and in England, respectively. The age-standardized grip strength among the female participants was 1.9 kg...... and 1.6 kg lower in Russia than in Denmark and in England, respectively. In Moscow, a one-kilogram increase in grip strength was associated with a 4% (hazard ratio [HR] = 0.96, 95% confidence interval [CI]: 0.94, 0.99) reduction in mortality among men and a 10% (HR = 0.90, 95%CI: 0.86, 0.94) among women...

Qualitative and quantitative analysis of arsenic and mercury in human remains of the XVI-XVII centuries from the Moscow Kremlin necropolises by neutron activation analysis at the IREN facility and the IBR-2 reactor of FLNP, JINR

International Nuclear Information System (INIS)

Panova, T.D.; Dmitriev, A.Yu.; Borzakov, S.B.; Khramko, K.

2017-01-01

The neutron activation analysis (NAA) of three samples of human remains of the XVI-XVII centuries from the necropolises of the Moscow Kremlin has been carried out at FLNP JINR. The samples were irradiated at two facilities: at the IREN source of resonance neutrons and at the IBR-2 reactor. Spectra of induced activity of the irradiated samples were measured by using the automatic measurement system developed at FLNP JINR. This system consists of a high-purity germanium detector with spectrometric electronics, a sample changer, and a control software. Mass fractions of arsenic, mercury and other elements were calculated by relative and absolute NAA methods. The obtained values confirmed the fact of an acute mercury poisoning of the first wife of Tsar Ivan Vasilievich the Terrible - Tsarina Anastasia Romanovna. Increased mercury content was detected in the bone remains of the son of Tsar Ivan the Terrible, Tsarevich Ivan Ivanovich, and Prince M. V. Skopin-Shuisky. The obtained results allow us to introduce into scientific circulation the exact values of mass fraction of mercury, arsenic and some other elements in the samples from the graves of Russian historical figures of the second half of XVI - early XVII centuries. [ru

Development of Euler's ideas at the Moscow State Regional University

Science.gov (United States)

Vysikaylo, P. I.; Belyaev, V. V.

2018-03-01

In honor of the 250th anniversary of Euler's discovery of three libration points in Russia in 1767 in the area of two rotating gravitational attractors in 2017 an International Interdisciplinary Conference “Euler Readings MRSU 2017” was held in Moscow Region State University (MRSU). The Conference demonstrated that the Euler's ideas continue to remain relevant at the present time. This paper summarizes the main achievements on the basis of Leonard Euler's ideas presented at the Conference.

Creation of new electronic services of Moscow government, interested for students, and their impact on the economy of the region (on the example of the real estate services

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Ponomarev V.G.

2016-11-01

Full Text Available options for implementation in the framework of the Internet portal of the Government of Moscow of new electronic services associated primarily with the effective visualization and informing of new real estate in the city of Moscow, as well as the ability to influence the proposed services on the development of the regional economy are considered in the article. Offers of the author based on the results of research carried out in the course of the joint work of the Department of territorial bodies of the executive power of the city of Moscow and the Moscow State University of Technology and Management named after K.G. Razumovsky.

Calibration of a special neutron dosemeter based on solid-state track detectors and fission radiators in various neutron fields

International Nuclear Information System (INIS)

Doerschel, B.; Krusche, M.; Schuricht, V.

1980-01-01

The calibration of a personnel neutron dosemeter in different neutron fields is described. The badge-like dosemeter contains 5 detectors: polycarbonate foil (10 μm, Makrofol KG), 232 Th, natural uranium, natural uranium with boron, and natural uranium with cadmium. Detector sensitivity and calibration factors have been calculated and measured in radiation fields of 252 Cf fission neutrons, WWR-S reactor neutrons with and without Cd and Fe shielding, 3-MeV (d,t) generator neutrons, and 238 PuBe neutrons. Measurement range and achievable accuracy are discussed from the point of view of applying the dosemeter in routine and emergency uses

The First Sprite Observation from Moscow in the Direction of Tver Region Associated with Repetitive Lightning Discharge

International Nuclear Information System (INIS)

Sorokin, L.V.

2017-01-01

The summer thunderstorms 2016 in the central part of Russia produced heavy precipitations and were accompanied by huge amount of lightning. During these events we provide the Sprite observation from Moscow. On the 18 August we caught two Sprites on the distance from 260 km to 290 km in the Tver region. It is important to underline that both Sprites occurred after the rare repetitive lightning discharge and the multiple lightning discharge. These types of lightning are rare in the Moscow region and more habitual for the tropical thunderstorms in Equator area. Due to the Climate Change and Global Warming the Sprites are common for the Russian Federation now. (author)

U.S. uranium supply to the research and test reactor community

International Nuclear Information System (INIS)

Parker, Elaine M.

2002-01-01

From the 1950s through the early 1990s, the U.S. Department of Energy (DOE) was the primary supplier of low enriched uranium (LEU) and highly enriched uranium (HEU) to research and test reactors worldwide. The formerly called Y-12 Plant in Oak Ridge, Tennessee, was put into operational stand down in 1994 due to inadequate safety documentation. This paper will discuss the re-start of the Y-12 Plant and its current capabilities. Additionally, the paper will address recent changes within the DOE, with the creation of the National Nuclear Security Administration (NNSA). It will show how the change to NNSA and an organizational re-alignment has improved efficiencies. NNSA is committed to operate its sales program so that it is complementary to, and in support of, the Reduced Enrichment for Research and Test Reactors (RERTR) and Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Return Programs. The NNSA is committed to provide an assurance of competitively-priced, high-quality uranium supply to the research and test reactor community under long-term contracts. This paper will discuss some of NNSA's recent successes in long-term contracting and meeting deliveries. (author)

RADON AND CARCINOGENIC RISK IN MOSCOW

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S. M. Golovanev

2015-01-01

Full Text Available Objective: comparative evaluation of carcinogenic risk inMoscowfrom radon in indoor and atmospheric pollutants.Materials and methods: the lung cancer incidence in Moscow; radiation-hygienic passport of the territory; .U.S. EPA estimated average age at all and radon induced deaths, years of life lost; Report of UNSCEAR 2006 and WHO handbook on indoor radon, 2009. Trend analysis of incidence; evaluation of the excess relative risk; assessment of ratio radon-induced population risk and published values оf total population carcinogenic risk from chemical carcinogens.Results: it is shown that the 304 cases of lung cancer per year (1. 85 10-3 on average from 2006 to 2011 (21280diseases for 70 years in addition to background level induced by radon; the differences in average trends of all lungcancer incidence in the districts can exceed 25%.Conclusion. The potential of risk reduction by measures of mitigation radon concentration exceeds 5 times the cost efficiency to reduce emissions from vehicles and can reduce cancer incidence, on average 236 cases per year; population risk 16520 cases over 70 years or save not less than 2832 person-years of life per year. The annual effect of reducing losses from not-survival of 12 years as a result of radon-induced lung cancer deaths exceeds 14160000 dollars. The evaluating of the carcinogenic risk from radon in accordance with the definition of population risk increases the predictive evaluation of the effectiveness of preventive measures more than twice.

[MONITORING OF THE CONTENT OF HEAVY METALS AND ELEMENTS IN THE SNOW COVER IN AGRICULTURAL SOILS AT THE TERRITORY OF THE MOSCOW REGION].

Science.gov (United States)

Ermakov, A A; Karpova, E A; Malysheva, A G; Mikhaylova, R I; Ryzhova, I N

2015-01-01

The monitoring of snow cover pollution by heavy metals and elements (zinc, copper, lead, cadmium, arsenic, nickel, chromium, strontium, manganese, fluorine, lithium) was performed in 20 districts of the Moscow region in 2009, 2012 and 2013. The assessment of the levels of contamination by heavy metals and elements was given by means of comparison of them with the average values in the snow cover near Moscow in the end of the last century and in some areas of the world, that no exposed to technological environmental impact. 7 districts of Moscow region were characterized by a high content of lead and cadmium in the snow water. It requires the control of water, soil and agricultural products pollution.

Safe decommissioning of the Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Garlea, C.; Garlea, I.; Kelerman, C.; Rodna, A.

2002-01-01

The VVR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotopical production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency Technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was stage 1. In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH04.1/1994 was dedicated to the 'Study of Soviet Design Research Reactors', had consolidated the development of the project emphasizing technical options of safe management for radioactive wastes and VVR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to the establishment of strategy for safe management of decommissioning. Technical analysis of the VVR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita-Bihor) proved the possibility of the classical method utilization for dismantling of the facility and treatment-conditioning-disposal of the arrised wastes in safe conditions. The decommissioning plan at stage 2 has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by the R and D programme including neutron calculations and experiments, radiological characterizing (for facility and its influence area), seismic analysis and environmental balance during the operation and after shut down of the reactor. A special chapter is dedicated to regulatory issues concerning the development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, the Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for the

Development of the IAEA’s Knowledge Preservation Portals for Fast Reactors and Gas-Cooled Reactors Knowledge Preservation

International Nuclear Information System (INIS)

Batra, C.; Menahem, D. Beraha; Kriventsev, V.; Monti, S.; Reitsma, F.; Grosbois, J. de; Khoroshev, M.; Gladyshev, M.

2016-01-01

Full text: The IAEA has been carrying out a dedicated initiative on fast reactor knowledge preservation since 2003. The main objectives of the Fast Reactor Knowledge Portal (FRKP) initiative are to, a) halt the on-going loss of information related to fast reactors (FR), and b) collect, retrieve, preserve and make accessible existing data and information on FR. This portal will help in knowledge sharing, development, search and discovery, collaboration and communication of fast reactor related information. On similar lines a Gas Cooled Fast Reactor Knowledge Preservation portal project also started in 2013. Knowledge portals are capable to control and manage both publicly available as well as controlled information. The portals will not only incorporate existing set of knowledge and information, but will also provide a systemic platform for further preservation of new developments. It will include fast reactor and gas cooled reactor document repositories, project workspaces for the IAEA’s Coordinated Research Projects (CRPs), Technical Meetings (TMs), forums for discussion, etc. The portal will also integrate a taxonomy based search tool, which will help using new semantic search capabilities for improved conceptual retrieve of documents. The taxonomy complies with international web standards as defined by the W3C (World Wide Web Consortium). (author

TREATMENT COMPLIANCE AMONG PATIENTS WITH CHRONIC PANCREATITIS IN THE MOSCOW REGION

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S. V. Beljakova

2014-01-01

Full Text Available Background: In the past decade, incidence of chronic pancreatitis among different age groups has been growing globally and in Russia. Chronic pancreatitis is a progressive disease characterized by development of complications and decrease of exocrine function of pancreas. Treatment should be initiated early, before the complications occur; therapy should account for international experience and established Russian guidelines. Continuous usage of high-dose enzyme preparations preferably in modern dosage forms (microgranules, minimicrospheres or microtablets is one of the key principles in the management of chronic pancreatitis. Patient’s cooperative behavior and good compliance is crucial for achieving treatment targets. Aim: To assess treatment compliance among patients with chronic pancreatitis in the Moscow Region and to identify sources of information on the disease used by the patients. Materials and methods: One hundred patients with chronic pancreatitis in Moscow Region were questionnaired anonymously on their adherence to the medical recommendations for diet, alcohol consumption and medications, particularly enzyme preparations. Patients’ sources of information on the disease were also determined. Results: Poor compliance results were shown: only 28% of patients were fully adherent to medical recommendations; other patients took their medications irregularly, changed drug doses or preparations choosing less expensive and effective drugs. The majority of patients (89% were aware of the main treatment principles, though, 53% didn’t adhere to them. Patients used varied sources of information on the disease including special literature and the web; nevertheless, the information could be incorrectly understood. Only some patients received disease-related information from their physician, and many of the patients described physician-derived information as insufficient. As a result, treatment was often inadequate. Conclusion:  Improved

New experience in atmospheric monitoring in Moscow city on the base of WSN technology

Science.gov (United States)

Asavin, Alex; Litvinov, Artur; Baskakov, Sergey; Chesalova, Elena

2016-04-01

The aim of this report is to present the gas emission of H2 in the general composition of atmospheric pollution of Moscow city. We start the project at the beginning of 2015 year in two Moscow academicals organization -Vernadsky Institute of Geochemistry and Analytical Chemistry and Moscow Geological State Museum. One place is in the center of Moscow, near the Kremlin and other one is in the most clear zone of Moscow - Moscow State University place, Vorobyevy Mountains (high point of Moscow). We plan to compare these regions by the concentration of H2 and other gases (CH4, SO2) for green gas pollution. Application network of monitoring is composed of gas sensors (H2, CH4), complex autonomous equipment for measurement temperature, pressure, humidity and network of telecommunications (used ZigBee protocol). Our project offer the technical solutions for monitoring network on the base of WSN (wireless sensor network) technology and the high-sensitive sensors of hydrogen and methane, software and electronic equipment with a transmitter network. This work is the first project in Russia. Gas sensors for monitoring system were developed on the base of MIS-structures (metal-insulator-semiconductor). MIS-sensors are suitable for measuring the concentrations of the following gases: hydrogen, hydrogen sulphide, nitrogen dioxide, ethylmercaptan, chlorine and ammonia. The basis of the sensor is MIS - structure Pd-Ta2O5-SiO2-Si,), which capacitance changes when reaction with gases occurs. The sensor fabrication technology is based on the microelectronics device fabrication technologies and the thin film laser deposition technique. Sensor can be used for measuring the concentration of any gas among noted before, in ambient temperature range -30..+40°C and RH 30-90% (30°C).Three gas sensors with analog interface were made for our experimental monitoring system. Original calibration was made using calibration by special standard mixture of H2 and atmosphere. There are 10-15 points

The Moscow economic conference of April 1952: a tactical manoeuvre or a new strategy of USSR?

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Михаил Аркадьевич Липкин

2010-06-01

Full Text Available In the article analyzes the prehistory, history and the meaning of a large soviet international action - the Moscow economic conference in April 1952. With a use of new evidences from the Russian state archive of social and political history the author argues that the Conference was not just a reaction to the Marshall Plan and Shuman Plan in Western Europe. It was the first attempt to open the iron curtain and change the logic of international relations towards peaceful coexistence. The Conference turned into quite unusual for the period of late Stalin's rule nursery for fresh ideas used in full by USSR later in 1950-1970s.

I. A. ILYIN ON KINDNESS: TOWARDS A STUDY OF THE MOSCOW PERIOD OF THE ACTIVITY OF THE PHILOSOPHER

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Vladimir Rozhnov

2013-06-01

Full Text Available This article examines the Moscow period of the activity of I.A. Il’in and especially his philosophical study entitled On Kindness. The distinguishing particularity of this study is the fact that Il’in used the methods of the descriptive psychology of Wilhelm Dilthey and of the sociology of Georg Simmel. The author investigates the type of infl uence and to what degree the works of Dilthey and Simmel influenced the method of Il’in. He concludes that Il’in, following the methods proposed by these two thinkers, was able to compose a brilliant analysis of the phenomenon of kindness. The author also examines the personal reasons why Il’in might have chosen to try this psychological-sociological experiment. He concludes that Il’in was motivated to attempt this study after refl ecting on his own personality and character. It is known that Il’in himself was known for his self-assuredness and his hot temper, both of which influenced the way he interacted with colleagues and the cultural elite of his own time. This article reconstructs the activity of Il’in in both its theoretical and personal aspects through one of the main works of his Moscow period. It also examines Il’in’s own method of scientifi c research

Landscape approach to the formation of the ecological frame of Moscow

Science.gov (United States)

Nizovtsev, Vyacheslav; Natalia, Erman

2015-04-01

The territory of Moscow, in particular in its former borders, is distinct for its strong transformation of the natural properties of virtually all types of landscape complexes. The modern landscape structure is characterized by fragmentation of natural land cover. Natural and quasinatural (natural and anthropogenic) landscape complexes with preserved natural structure are represented by isolated areas and occupy small areas. During recent years landscape diversity in general and biodiversity in particular have been rapidly declining, and many of the natural landscape complexes are under ever-increasing degradation. Ecological balance is broken, and preserved natural landscapes are not able to maintain it. Effective territorial organization of Moscow and the rational use of its territory are impossible without taking into account the natural component of the city as well as the properties and potential of the landscape complexes that integrate all natural features in specific areas. The formation of the ecological framework of the city is particularly important. It should be a single system of interrelated and complementary components that make up a single environmental space: habitat-forming cores (junctions), ecological corridors and elements of environmental infrastructure. Systemic unity of the environmental framework can support the territorial ecological compensation where a break of the ecological functions of one part of the system is compensated by maintaining or restoring them in another part and contribute to the polarization of incompatible types of land use. Habitat-forming cores should include as mandatory parts all the specifically protected natural areas (SPNAs), particularly valuable landscape complexes, as well as preserved adjacent forest areas. Their most important function should be to maintain resources and area reproducing abilities of landscapes, landscape diversity and biodiversity. Ecological corridors which perform environmental and

75 FR 53012 - Culturally Significant Objects Imported for Exhibition Determinations: “Treasures of Moscow...

Science.gov (United States)

2010-08-30

... Rublev Museum,'' imported from abroad for temporary exhibition within the United States, are of cultural... Determinations: ``Treasures of Moscow: Icons From the Andrey Rublev Museum'' SUMMARY: Notice is hereby given of... determine that the exhibition or display of the exhibit objects at the Museum of Russian Icons, Clinton, MA...

Steam water cycle chemistry of liquid metal cooled innovative nuclear power reactors

International Nuclear Information System (INIS)

Yurmanov, Victor; Lemekhov, Vadim; Smykov, Vladimir

2012-09-01

The Federal Target Program (FTP) of Russian Federation 'Nuclear Energy Technologies of the New Generation for 2010-2015 and for Perspective up to 2020' is aimed at development of advanced nuclear energy technologies on the basis of closed fuel cycle with fast reactors. There are advanced fast reactor technologies of the 4. generation with liquid metal cooled reactors. Development stages of maturity of fast sodium cooled reactor technology in Russia includes experimental reactors BR-5/10 (1958-2002) and BOR-60 (since 1969), nuclear power plants (NPPs) with BN-350 (1972-1999), BN-600 (since 1980), BN-800 (under construction), BN-1200 (under development). Further stage of development of fast sodium cooled reactor technology in Russia is commercialization. Lead-bismuth eutectic fast reactor technology has been proven at industrial scale for nuclear submarines in former Soviet Union. Lead based technology is currently under development and need for experimental justification. Current status and prospects of State Corporation 'Rosatom' participation in GIF activities was clarified at the 31. Meeting of Policy Group of the International Forum 'Generation-IV', Moscow, May 12-13, 2011. In June, 2010, 'Rosatom' joined the Sodium Fast Reactor Arrangement as an authorized representative of the Russian Government. It was also announced the intention of 'Rosatom' to sign the Memorandum on Lead Fast Reactor based on Russia's experience with lead-bismuth and lead cooled fast reactors. In accordance with the above FTP some innovative liquid metal cooled reactors of different design are under development in Russia. Gidropress, well known as WER designer, develops innovative lead-bismuth eutectic cooled reactor SVBR-100. NIKIET develops innovative lead cooled reactor BRESTOD-300. Some other nuclear scientific centres are also involved in this activity, e.g. Research and Development Institute for Power Engineering (RDIPE). Optimum

CHOICE OF THE INITIAL TREATMENT FOR MILD TO MODERATE ARTERIAL HYPERTENSION IN MOSCOW PRIMARY PRACTICE

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S. V. Gatsura

2015-09-01

Full Text Available Aim. To assess the choice of initial pharmacotherapy of uncomplicated mild to moderate arterial hypertension (HT in Moscow primary care as well as to clear up the influence of regulatory measures on this choice.Material and methods. Results of two similar surveys conducted in 2011-2012 (452 respondents and 2013-2014 (273 respondents were compared to estimate preferences of Moscow primary care physicians regarding initial antihypertensive agents for therapy of uncomplicated mild to moderate HT taking into consideration an influence of regulatory requirement to prescribe medicinal products by international nonproprietary name (INN since July 2012. All participants were proposed to write down their preferred antihypertensive agents for initial mono- or combined therapy of mild to moderate HT with moderate cardiovascular risk and absence of compelling indications.Results. Angiotensin converting enzyme inhibitors (ACEI remained the leading class of antihypertensive agents, though their popularity slightly but significantly declined from 44.4% in 2011-12 to 37.2% in 2013-14 (р<0.05. Angiotensin receptor blockers partially displaced the leaders and increased their popularity from 11.3% in 2011-12 to 18.0% in 2013-14 (р<0.01. ACEI/diuretic combination remained on the 3rd position (16.4% and 15.3% respectively. Beta-blockers and diuretics as monotherapy shared 4th and 5th places in this rating. Calcium channel blockers popularity among Moscow prescribers remained unchanged and poor – 2.1%. The most popular medicine by trade name was Noliprel, perindopril/indapamide fixed combination, – 14.0% and 13.7% of respondents in 2011-12 and 2013-14, respectively. The share of medicine products recommended by INN went up from 11.9% to 22.8% among top-10 popular medications (р<0.01.Conclusion. Blockers of renin-angiotensin-aldosterone system remain the leading drugs for the initial treatment of uncomplicated mild to moderate HT without compelling indications

Dynamics of species diversity of epiphytic lichenized fungi in the southern district of Moscow city

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Biazrov Lev

2013-03-01

2006-2007 on the same territory the representatives of 54 epiphytic lichen species were found. The basic reason of the changes in the compositionof lichen biota revealed on the studied urban territory is eutrophication mainly nitrophication of lichen habitats in Moscow city."

High field FT-ICR mass spectrometry for molecular characterization of snow board from Moscow regions.

Science.gov (United States)

Mazur, Dmitry M; Harir, Mourad; Schmitt-Kopplin, Philippe; Polyakova, Olga V; Lebedev, Albert T

2016-07-01

High field Fourier transform ion cyclotron resonance (FT-ICR) mass spectrometry analysis of eight snow samples from Moscow city allowed us to identify more than 2000 various elemental compositions corresponding to regional air pollutants. The hierarchical cluster analysis (HCA) of the data showed good concordance of three main groups of samples with the main wind directions. The North-West group (A1) is represented by several homologous CHOS series of aliphatic organic aerosols. They may form as a result of enhanced photochemical reactions including oxidation of hydrocarbons with sulfonations due to higher amount of SO2 emissions in the atmosphere in this region. Group A2, corresponding to the South-East part of Moscow, contains large amount of oxidized hydrocarbons of different sources that may form during oxidation in atmosphere. These hydrocarbons appear correlated to emissions from traffic, neighboring oil refinery, and power plants. Another family of compounds specific for this region involves CHNO substances formed during oxidation processes including NOx and NO3 radical since emissions of NOx are higher in this part of the city. Group A3 is rich in CHO type of compounds with high H/C and low O/C ratios, which is characteristic of oxidized hydrocarbon-like organic aerosol. CHNO types of compounds in A3 group are probably nitro derivatives of condensed hydrocarbons such as PAH. This non-targeted profiling revealed site specific distribution of pollutants and gives a chance to develop new strategies in air quality control and further studies of Moscow environment. Copyright © 2016 Elsevier B.V. All rights reserved.

Long-term variability and impact on human health of biologically active UV radiation in Moscow

Science.gov (United States)

Zhdanova, Ekaterina; Chubarova, Natalia

2014-05-01

the developed classification for Moscow. Booth, C.R. and S. Madronich, 1994: Radiation amplification factors: improved formulation accounts for large increases in ultraviolet radiation associated with Antarctic ozone depletion. In: Ultraviolet Radiation in Antarctica: Measurements and Biological Research [Weiler, C.S. and P.A. Penhale (eds.)]. AGU Antarctic Research Series, 62, Washington, DC, USA, 39-42. Chubarova N.Y., 2008: UV variability in Moscow according to long-term UV measurements and reconstruction model. Atmos.Chem.Phys., 8, 3025-3031 Oriowo, M. et al., 2001:, Action spectrum for in vitro UV-induced cataract using whole lenses. Invest.Ophthalmol.&Vis.Sci, 42, 2596-2602. CIE, 1993: Reference Action Spectra for Ultraviolet Induced Erythema and Pigmentation of Different Human skin Types. CIE Research Note, CIE Technical Collection., N.3 CIE, 2006: Action spectrum for the production of previtamin D3 in human skin, Technical report 174, International commission on illumination

U. S. Utility Leadership in Requirements For Passive Reactors

International Nuclear Information System (INIS)

Kim, Jcng H.; Layman, William H.

1991-01-01

Utility leadership from both U.S. utilities and international utilities, is a key element in the U. S. Advanced Light Water Reactor Program. International utilities have played a very import Design reviews by the utilities participating in the ALRR Program will ensure that all of the utility requirements are met while design work is being carried out. Our mission is to achieve NRC certification of designs that reflect the needs of the utilities and we believe that this will play an important role in the resurgence of nuclear plant construction in the United States. As stated in the Nuclear Power Oversight Committee's Strategic Plan For Building New Nuclear Power Plants : 'The extensive operating experience with today's light water reactors (LWRs), and the promise shown in recent technical developments, leads the industry to the conclusion that the next nuclear plants ordered in the United States will be advanced light water reactors (A LWRs). Two types are under development : units of large output (1300 MW) called 'evolutionary' A LWRs and units of mid-size output (600 MW) called 'Passive' A LWRs. The term 'passive' refers to the safety features which depend more on natural processes such as gravity and buoyancy than on powered equipment such as pumps

Zadonshchina, Ryazan, and the Moscow Princely Family

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Alexander V. Lavrentyev

2015-12-01

Full Text Available This paper is devoted to the history and controversies surrounding the outstanding representative of Russian medieval literature from the late 14th century, the famous Zadonshchina. This work glorifies the military victory of the united forces of the Russian troops, led by Grand Prince Dmitry Donskoy, over the Tatar army on 8 September 1380, at Kulikovo Field near the Don River. This article presents arguments in favor of a Ryazan origin of the Zadonshchina text; furthermore, the article offers an explanation of the presence in the text of two “protagonists,” Grand Prince Dmitry Ivanovich and his cousin, Vladimir Andreyevich the Bold, Prince of Serpukhov. The joint rule of the “brothers” was a result of deaths caused by the plague in the Moscow ruling house, which took the dynasty to the brink of extinction. This feature of the political situation is reflected in the Zadonshchina text.

Current status of operation and utilization of the Dalat Research Reactor

International Nuclear Information System (INIS)

Dien, Nguyen Nhi

2006-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool-type reactor using the HEU (36% enrichment) WWR-M2 fuel assemblies. It was renovated and upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in the 1st November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analysis, scientific research and training. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for reactor physics and thermal hydraulics experiments. From the first start-up to the end of December 2004, it totaled about 27,253 hrs of operation and the total energy released was about 543 MWd. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 fuel assemblies (FA). The 11 new FAs were added in the core periphery, at previous beryllium element locations. After reloading the working configuration of reactor core consisted of 100 FAs. The second fuel reloading was executed in March 2002. The 4 new FAs were added in the core periphery, at previous beryllium element locations. The working configuration of 104 FAs ensured efficient exploitation of the DNRR at nominal power for about 3000 hrs since March 2002. In order to provide excess reactivity for the reactor operation without the need to discharge high burned FAs, in June 2004, the fuel shuffling of the reactor core was done. 16 FAs with low burn-up from the core periphery were moved toward the core center and 16 FAs with high-burn-up from the core center were moved toward the core periphery. This operation provided additional reactivity of about 0.85 β eff that the current reactor configuration using re-shuffled HEU fuel is expected to allow normal operation until June 2006. In 1999, the request of returning to Russia HEU fuels from foreign

Full instantaneous traversal rupture of the primary loop pipeline

International Nuclear Information System (INIS)

Baytelesov, S.A.; Kungurov, F.R.

2010-01-01

Accident, reflecting full immediate cross rupture of primary loop pipe of WWR-SM research reactor of INP AS RUz is observed in this paper. Calculations for accident situation and analysis for different reactor cores, formed from fully IRT-3M type high enriched fuel (36% enrichment on 235 U), first mixed core, compiled from 16 IRT-3M fuel assemblies and 4 IRT-4M type fuel assemblies with low enriched fuel (19,7% enrichment on 235 U) and the core fully formed from low enriched fuel are carried out

A Small Modular Reactor Design for Multiple Energy Applications: HTR50S

Energy Technology Data Exchange (ETDEWEB)

Yan, X.; Tachibana, Y.; Ohashi, H.; Sato, H.; Tazawa, Y.; Kunitomi, K. [Japan Atomic Energy Agency, Ibaraki (Japan)

2013-06-15

HTR50S is a small modular reactor system based on HTGR. It is designed for a triad of applications to be implemented in successive stages. In the first stage, a base plant for heat and power is constructed of the fuel proven in JAEA's 950 .deg. C, 30MWt test reactor HTTR and a conventional steam turbine to minimize development risk. While the outlet temperature is lowered to 750 .deg. C for the steam turbine, thermal power is raised to 50MWt by enabling 40% greater power density in 20% taller core than the HTTR. However the fuel temperature limit and reactor pressure vessel diameter are kept. In second stage, a new fuel that is currently under development at JAEA will allow the core outlet temperature to be raised to 900 .deg. C for the purpose of demonstrating more efficient gas turbine power generation and high temperature heat supply. The third stage adds a demonstration of nuclear-heated hydrogen production by a thermochemical process. A licensing approach to coupling high temperature industrial process to nuclear reactor will be developed. The low initial risk and the high longer-term potential for performance expansion attract development of the HTR50S as a multipurpose industrial or distributed energy source.

Weekly cycle of minor air gases in Moscow

Science.gov (United States)

Lokoshchenko, Mikhail A.; Elansky, Nikolay F.; Trifanova, Alexandra V.

2017-04-01

The weekly cycle of the surface concentrations of five trace atmospheric gases in Moscow has been analyzed based on continuous automatic once-a-minute measurements. The data of joint ecological station of the Institute of Atmospheric Physics and Moscow State University for nine years (2002-2010) were used. This station operated in conditions of comparatively clear park zone of the University on the South-Western periphery of the city at a distance of 8 km from the city centre. Fortunately, none of the great sources of the air pollution - neither point sources, nor linear ones - are present in the vicinity of the station so that the measurements there are quite representative. Results of spectral analysis demonstrate statistically significant maximum of spectral density close to 7 days. Any clear periodicity of around seven days may be a consequence of either natural synoptic period or weekly cycle. The fact that the influence of human activity on urban air composition changes with a weekly periodicity is confirmed by statistically significant difference between concentrations of trace gases on working days and on Sunday (when emissions from both the traffic and the industrial sources are minimal). On average, both primary pollutants (nitrogen oxide and carbon oxide) and the secondary ones (NO2) show the lowest concentrations of the week on Sunday whereas ozone, by contrast, peaks on this day. Besides, usual diurnal cycle of air pollutants is transformed on Sunday - e.g., secondary nocturnal maximum of ozone in the city is absent on Sunday like at rural area. On Saturday concentrations of trace gases are in between working days and Sunday; this 'Saturday effect' is a result of a gradual clearing of the urban air. An additional effect is that in the first half of Monday (before noon) surface concentrations of NO and NO2 are generally less, whereas the concentration of O3 is, on the contrary, a bit higher than at the same time on the rest of working days. The 'Monday

Computer control system synthesis for nuclear power plants through simplification and partitioning of the complex system model into a set of simple subsystems

International Nuclear Information System (INIS)

Zobor, E.

1978-12-01

The approach chosen is based on the hierarchical control systems theory, however, the fundamentals of other approaches such as the systems simplification and systems partitioning are briefly summarized for introducing the problems associated with the control of large scale systems. The concept of a hierarchical control system acting in broad variety of operating conditions is developed and some practical extensions to the hierarchical control system approach e.g. subsystems measured and controlled with different rates, control of the partial state vector, coordination for autoregressive models etc. are given. Throughout the work the WWR-SM research reactor of the Institute has been taken as a guiding example and simple methods for the identification of the model parameters from a reactor start-up are discussed. Using the PROHYS digital simulation program elaborated in the course of the present research, detailed simulation studies were carried out for investigating the performance of a control system based on the concept and algorithms developed. In order to give a real application evidence, a short description is finally given about the closed-loop computer control system installed - in the framework of a project supported by the Hungarian State Office for Technical Development - at the WWR-SM research reactor where the results obtained in the present IAEA Research Contract were successfully applied and furnished the expected high performance

Nuclear reactor safety program in U.S. Department of Energy and future perspectives

International Nuclear Information System (INIS)

Song, Y.T.

1987-01-01

The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)

Analysis of arsenic and mercury content in human remains of the 16th and 17th centuries from Moscow Kremlin necropolises by neutron activation analysis at the IREN facility and the IBR-2 reactor FLNP JINR

Science.gov (United States)

Panova, T. D.; Dmitriev, A. Yu.; Borzakov, S. B.; Hramco, C.

2018-01-01

A neutron activation analysis (NAA) of three samples of human remains of the 16th and 17th centuries from the necropolises of the Moscow Kremlin has been carried out at FLNP JINR. The samples were irradiated at two facilities: the IREN source of resonance neutrons and the IBR-2 reactor. Spectra of the induced activity of the irradiated samples were measured by using the automatic measurement system developed at the Frank Laboratory of Neutron Physics (FLNP) of the Joint Institute for Nuclear Research (JINR). This system consists of a high-purity germanium detector with spectrometric electronics, a sample changer, and control software. Mass fraction of arsenic, mercury, and some other elements were calculated using two NAA methods—relative and absolute. The obtained values confirm the fact of acute mercury poisoning of Anastasia Romanovna, the first wife of Tsar Ivan Vasil'evich the Terrible, the first Russian Tsarina (died in 1560). High levels of mercury were detected in the bone remains of Tsarevich Ivan Ivanovich (died in 1581), the son of Tsar Ivan the Terrible, and Prince Mikhail Vasil'evich Skopin-Shuiskii (died in 1610). The results provide an opportunity to introduce into scientific circulation the exact values of mass fraction of mercury, arsenic, and other elements in the samples taken from the burials of the Russian historical figures of the second half of 16th-early 17th century.

Final report on the IAEA research contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB

International Nuclear Information System (INIS)

Zobor, E.; Janosy, J.S.; Szentgali, A.

1980-09-01

The final report summarizes the research activities made in the framework of the IAEA Research Contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB. A multilevel hierarchical control system is treated which uses weakly-coupled low dimensional subsystems under the supervision of a dynamic coordinator program. This self-organizing adaptive control system was checked by a 5 MW research reactor. As an example the paper describes the experimental computer control system of the 5 MW WWR-SM research reactor, where the reactor power and outlet temperature have been controlled on the basis of the treated control concept since 1978. (author)

Preliminary Design of S-CO2 Brayton Cycle for KAIST Micro Modular Reactor

International Nuclear Information System (INIS)

Kim, Seong Gu; Kim, Min Gil; Bae, Seong Jun; Lee, Jeong Ik

2013-01-01

This paper suggests a complete modular reactor with an innovative concept of reactor cooling by using a supercritical carbon dioxide directly. Authors propose the supercritical CO 2 Brayton cycle (S-CO 2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the core and PCU in one vessel for the full modularization. This study suggests a conceptual design of small modular reactor including PCU which is named as KAIST Micro Modular Reactor (MMR). As a part of ongoing research of conceptual design of KAIST MMR, preliminary design of power generation cycle was performed in this study. Since the targets of MMR are full modularization of a reactor system with S-CO 2 coolant, authors selected a simple recuperated S-CO 2 Brayton cycle as a power conversion system for KAIST MMR. The size of components of the S-CO 2 cycle is much smaller than existing helium Brayton cycle and steam Rankine cycle, and whole power conversion system can be contained with core and safety system in one containment vessel. From the investigation of the power conversion cycle, recompressing recuperated cycle showed higher efficiency than the simple recuperated cycle. However the volume of heat exchanger for recompressing cycle is too large so more space will be occupied by heat exchanger in the recompressing cycle than the simple recuperated cycle. Thus, authors consider that the simple recuperated cycle is more suitable for MMR. More research for the KAIST MMR will be followed in the future and detailed information of reactor core and safety system will be developed down the road. More refined cycle layout and design of turbomachinery and heat exchanger will be performed in the future study

[The specificity of children and adolescent eating habits (data for schoolchildren in Moscow and Murmansk)].

Science.gov (United States)

Aleksandrov, A A; Poriadina, G I; Kotova, M B; Ivanova, E I

2014-01-01

Objective of the study is to evaluate the specificity of schoolchildren's eating behavior in the cities of Moscow and Murmansk. Dietary habits of 785 children 10-17 years old residing in two cities--Moscow (222 boys and 221 girls, 14.1 ± 1.9 years old) and Murmansk (183 and 159 correspondingly, 14.1 ± 1.8 years old)--were analyzed. The questionnaire included data on the meals ratio per day, frequency of vegetables and fruit intake, fast-food intake, hot meals, soft drinks, meat, fish and milk intake, usage of school cafeteria, regularity of breakfasts. Parents responded to questions concerning the materialsupport of family and education. It was found that more than half of schoolchildren (64.4%) had meals irregularly (3 times per day or less), only 50.9% received hot meals several times a day. Every third child (31.6%) has insufficient intake of vegetables and fruit, 11.8%--insufficient intake of meat dishes. Only 51.4% of schoolchildren consumed dairy products daily (one or several times a day). At the same time 19.5% of children used fast-food products several times a week or more often, 42.2%--carbonated drinks, and 22.7%--smoked food. Only 45.7% of schoolchildren regularly ate at school caf- eteria; 21.9% did it irregularly and 32.5%--did not attend school canteen at all. There were no significant differences between Moscow and Murmansk children as well as gender differences in the usage of school cafeteria. At the same time only 23.4% of children [26.3% in Moscow and 19.3% in Murmansk (significantly less, p = 0.032)] liked cafeteria food, 38.7% did not like and 37.9% had no certain answer. Less obese children (54.0%) have breakfast everyday than children with normal weight (75.4%, p = 0.019). Children of mothers with high and incomplete high education (89.4%) have more regular meat intake (3-4 times per week or more often) than the children of mothers with secondary, incomplete secondary and secondary special education (81.9%, p = 0.034). Schoolchildren

Church, freedom and bolshevisation of Moscow University

Science.gov (United States)

Gaina, Alex

2008-05-01

A short description of events, occured in Russia after 1917 with emphasysis on main phyilosophycal curents such as marxism and believing, first of atheistic content and second of christian moralty content is given. It is argued, that bolshevicks contributed to progress of Russia, but this was reached by mean of purges and terror, during which many peoples were killed, especially representatives of the Russian Ortodox church. A list of scientists, which contributed more than other to the bolshevisation of the Russia and Moscow University, particularly, is given. The controverse between Hegel and Einstein from one part and Marx and bolshevicks from other part is examined also. The bolshevicks destroyed the Russian ortodox church, instead of its modernisation, is argued. The Calendar in the Russian Ortodox church is discussed, which is Julian, and it is argued, that a peaceful dialogue between the representatives of the Church and scientists is needed in order to make a transition to the Gregorian one.

Pharmacoeconomic analysis of conservative strategy for the treatment of patients with diabetic foot syndrome in Moscow

Directory of Open Access Journals (Sweden)

Marina Fedorovna Kalashnikova

2011-09-01

Full Text Available Aim. To perform cost-effectiveness analysis of prescription of pharmaceutical products and dressing materials and their consumption volume for inandout-patient treatment of diabetic foot syndrome (DFS. To analyse efficacy of the treatment in terms of modern therapeutic standards. Materials and methods. This retrospective study is based on the medical documentation of 139 DM1 and DM2 patients with DFS from differentmedical facilities of Moscow (2007. 72 patients were given general out-patient care by surgeons of city polyclinics, 50 ones received specialized aidin the regional Diabetic Foot Cabinet. 67 patients were hospitalized: 20 for general care in the department of purulent surgery of a military hospital,27 for specialized care in the department of purulent surgery of a city hospital, 20 for high-technology care in the endocrinological clinic of the FirstMoscow State Medical University. Results. Therapeutic strategy for DFS patients used in the regional Diabetic Foot Cabinet met the current therapeutic standards. General out-patientcare by surgeons of city polyclinics was at variance with the algorithms adopted in this country. Pharmacoeconomic analysis of the spectrum of pharmaceuticalproducts used for in- and out-patient treatment of DFS patients revealed frequent and ungrounded application of drugs whose woundhealing effect remains to be confirmed (pentoxifylline, thioctoic and alpha-lipoic acids. Conclusion. Additional training courses for surgeons of Moscow polyclinics are needed to improve the quality of medical aid to DFS patients. Suchpatients must be referred to regional Diabetic Foot Cabinets. Pentoxifylline, thioctoic and alpha-lipoic acids need to be substituted by pharmaceuticalswith validated therapeutic efficacy.

Female migrant sex workers in Moscow: gender and power factors and HIV risk.

Science.gov (United States)

Weine, Stevan; Golobof, Alexandra; Bahromov, Mahbat; Kashuba, Adrianna; Kalandarov, Tohir; Jonbekov, Jonbek; Loue, Sana

2013-01-01

This study aimed to build formative knowledge regarding HIV risks in female migrant sex workers in Moscow, focusing on gender and power. This was a collaborative ethnographic study, informed by the theory of gender and power, in which researchers conducted minimally structured interviews with 24 female sex workers who were migrants to Moscow and who provided sexual services to male migrant laborers. Overall, the female migrant sex workers engaged in HIV risk behaviors and practiced inadequate HIV protection with their clients. These behaviors were shaped by gender and power factors in the realms of labor, behavior, and cathexis. In the labor realm, because some female migrants were unable to earn enough money to support their families, they were pushed or pulled into sex work providing service to male migrants. In the behavior realm, many female migrant sex workers were intimidated by their male clients, feared violence, and lacked access to women's health care and prevention. In the cathexis realm, many had a sense of shame, social isolation, emotional distress, and lacked basic HIV knowledge and prevention skills. To prevent HIV transmission requires addressing the gender and power factors that shape HIV/AIDS risks among female migrant sex workers through multilevel intervention strategies.

Radiological protection of the staff during the decommissioning operations of the Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Ene, D.C.

2002-01-01

Dose rate estimates for periods of 100 days and 6, 10, 25, 100 years after the shut down of the Romanian VVR-S reactor are presented in this paper for some foreseen decommissioning activities which include: i) cutting the water pipe in the pump room and the reactor sealing operations; ii) extracting reactor components; and iii) handling and dismantling the internal structures taken of from the reactor. For the reactor components extracted from the reactor, the considered calculation points were placed in the central plan of the items, on the surface and at distances from the surface which correspond to +0.2m, +1m, +2m, +8m, and +10m. Time dependence of the resulted dose rates are presented and discussed. Qualitative comparison with the measured values from other VVR-S reactors is done. The obtained results assist to develop working procedures that must be observed during the decommissioning activities. (author)

[Vitamin status of citizens from Moscow Region].

Science.gov (United States)

Beketova, N A; Pogozheva, A V; Kodentsova, V M; Vrzhesinskaya, O A; Kosheleva, O V; Pereverzeva, O G; Aristarhova, T V; Levin, L G; Danisova, N N; Baturin, A K

2016-01-01

Evaluation of vitamin status in healthy individuals (68 men and 70 women) aged from 18 to 60 years (median - 37 years), residents of Moscow and the Moscow region has been performed by means of determination of vitamin C, A, E, B2, B12 and folic acid level in blood serum. The nutrition was investigated by questionnaire method on frequency of food consumption. Both diet of men and women had excessive fat content (41.7 and 42.7% of total calories), saturated fatty acids (14.1 and 13.6%), added sugars (11.1 and 11.0%), sodium, and had lack of dietary fiber (2.5-fold reduced level comparing with RDA). Daily intake of vitamin B1 was 1.37±0.04 mg for men and 1.06±0.07 mg for women, vitamin B2 - respectively 1.72±0.06 and 1.62±0.07 mg, niacin - 18.5±0.72 and 14.8±0.88 mg and did not reach the optimal level. All persons were sufficiently supplied with vitamins A, C, E and B12: mean and median of blood serum level of retinol, tocopherols, ascorbic acid and cobalamins were in the range of optimum values. The lack of vitamins A and B12 has not been found in any person. The frequency of vitamin C and E insufficiency was insignificant and amounted to 2 and 8% respectively. The lack of vitamin B2, and β-carotene was most pronounced and took place in about a half of individuals. Only 34% of healthy people of working age were sufficiently supplied with all vitamins. A combined lack of two vitamins was detected in 26%, of three vitamins - in 8%. Women were better supplied with riboflavin and β-carotene. The blood serum level of β-carotene and vitamin E was significantly higher in individuals older than 30 years compared with persons of younger age. Individuals with overweight or obesity were worse supplied with β-carotene and folate. A negative correlation was detected between the levels of serum folate and homocysteine concentration (r=-0.262, p<0.05). A positive correlation has been revealed between the concentration of folic acid and the level of HDL-C (r=0.356, p<0

MOSCOW PRINTERS-FOREIGNERS IN THE LAST THIRD OF THE 19TH - EARLY 20TH CENTURY

Directory of Open Access Journals (Sweden)

Г В Аксенова

2017-12-01

Full Text Available The article considers the role of foreigners in the publishing business of Moscow in the last third of the 19th - early 20th century on the example of Moscow printers E.-C. A. Lissner and A.A. Levenson, whose ancestors came to Russia from Austria and Germany. The historio-graphical review showed that the history of Moscow publishing houses and foreign printers who arrived in Russia remains beyond the scope of the current scientifi c interest. There are analyzed the stages of the development of the publishing business, it features, printing fi ndings, the specifi cs of the book market.E.-C. A. Lissner and A.A. Levenson are the brightest fi gures in Russia in the fi eld of publishing. Starting from scratch, they were able to create unique typography, in which it was possible to produce multicolour hard products, phototype table, to improve engraving, chromolithography and colour photozincography. To perform these works, they attracted specialists who were able to develop and implement new ways of printing. E.-C. A. Lissner and A.A. Levenson collaborated with the best artists of Russia helping to implement the ideas of publishing quality printed products that contributed to the aesthetic education of readers. The article reveals the importance of the activities of the two publishers of German origin E.-C. A. Lissner and A. Levenson in the development of the Russian culture (literature and art and the popularization of scientifi c knowledge. They laid new principles of publishing and printing of illustrations, created a new trend in book production. Their activities contributed to the opening of new names in literature and art, promotion of Russian printing technology and book production to both domestic and foreign markets, development of book art and improve-ment of printing.

U.S. Non-proliferation policy and programs regarding use of high-enriched uranium in research reactors

International Nuclear Information System (INIS)

Lewis, R.A.

1993-01-01

Uranium enriched to 90-93%, supplied by the U.S., is now used in 141 research and test reactors in 35 countries around the world with a cumulative power of 1714 mw. Since of the order of 3 kg of 235 U is involved annually in fuel fabrication, fresh fuel transport and storage, reactor operation, and spent fuel cooling and return per megawatt of research reactor power, it is estimated that more than 5000 kg of very high-enriched uranium is handled each year to operate these reactors. Recent U.S. assessments have led to the tentative conclusion that in only approximately 11 of these reactors, generally those of highest power or power density, is the use of 90-93% enriched uranium currently a technical necessity. Universal use of the best state-of-the-art fuel technology would permit an estimated 90 of these reactors to use 20% enriched fuel, and estimated 40 others to use 45% enriched fuel, without significant performance degradation. If advanced research reactor fuel development programs currently under way in the U.S. and elsewhere are successful, it may, in fact, be possible to operate virtually all of these reactors on less than 20% enriched uranium in the longer term. The physical and economic practicality of these developmental fuels must, of course, await future assessments

THE EFFECT OF THE WINDOW-TO-WALL RATIO ON COOLING ENERGY USAGE AND COMFORT TEMPERATURE

Directory of Open Access Journals (Sweden)

Aris Budhiyanto

2017-12-01

Full Text Available This study presents an investigation of the effect of building envelope, especially glass facade buildings on cooling energy usage and thermal comfort. An office building was modeled with various window-to-wall ratio (WWR using panasap glass with SC=0.58 in order to analyze the effect of the WWR addition on cooling energy usage and comfort temperature. The result suggested that the average increase of the cooling energy usage is about 5.67% per 10% WWR addition, and of the operative temperature ranges from 0.350C to 0.560C per 10% WWR addition. Moreover, the building with above 20% WWR doesn’t provide comfort temperature.

Dutch business opportunities in the Russian agrifood sector; Animal protein sector and Moscow Metropolitan fresh food chain

NARCIS (Netherlands)

Wijnands, J.H.M.; Valeeva, N.I.; Berkum, van S.

2012-01-01

This report studies the Russian animal protein sector and the Moscow Metropolitan Food Security. It aims at identifying the opportunities for Dutch business to do businesses through exports or via local investments. Public available government policies, papers and interviews with stakeholders are

Experience in incorporation control of operation personnel of the Reinsberg nuclear power plant (1967 - 1973)

International Nuclear Information System (INIS)

Pul'khajm, K.F.; Klyuke, Kh.

1976-01-01

A theoretic estimate of fission products and corrosion nuclides in a WWR type reactor is given. The results of radiation monitoring of the personnel irradiation at the Reinsberg (DDR) nuclear power plant are presented. It is supposed that the intake of fission and corrosion products has been realized through inhalation. The equivalent doses of internal irradiation are calculated. The estimate of the results of radiation monitoring are presented [ru

In-Pile Assemblies for Investigation of Tritium Release from Li2TiO3 Lithium Ceramic

International Nuclear Information System (INIS)

Shestakov, V.; Tazhibayeva, I.; Kawamura, H.; Kenzhin, Y.; Kulsartov, T.; Chikhray, Y.; Kolbaenkov, A.; Arinkin, F.; Gizatulin, Sh.; Chakrov, P.

2005-01-01

The description of algorithm to design in-pipe experimental ampoule devices (IPAD) is presented here, including description of IPAD design for irradiation tests of highly enriched lithium ceramics at WWR-K reactor. The description of the system for registration of tritium release from ceramics during irradiation is presented as well. Typical curve of tritium release from the IPAD during irradiation under various temperatures of the samples is shown here

Advanced liquid metal reactor development at Argonne National Laboratory during the 1980s

International Nuclear Information System (INIS)

Wade, D.C.

1990-01-01

Argonne National Laboratory's (ANL'S) effort to pursue the exploitation of liquid metal cooled reactor (LMR) characteristics has given rise to the Integral Fast Reactor (IFR) concept, and has produced substantial technical advancement in concept implementation which includes demonstration of high burnup capability of metallic fuel, demonstration of injection casting fabrication, integral demonstration of passive safety response, and technical feasibility of pyroprocessing. The first half decade of the 90's will host demonstration of the IFR closed fuel cycle technology at the prototype scale. The EBR-II reactor will be fueled with ternary alloy fuel in HT-9 cladding and ducts, and pyroprocessing and injection casting refabrication of EBR-II fuel will be conducted using near-commercial sized equipment at the Fuel cycle Facility (FCF) which is co-located adjacent to EBR-II. Demonstration will start in 1992. The demonstration of passive safety response achievable with the IFR design concept, (already done in EBR-II in 1986) will be repeated in the mid 90's using the IFR prototype recycle fuel from the FCF. The demonstration of scrubbing of the reprocessing fission product waste stream, with recycle of the transuranics to the reactor for consumption, will also occur in the mid 90's. 30 refs

Experimental validation of TASS/SMR-S critical flow model for the integral reactor SMART

Energy Technology Data Exchange (ETDEWEB)

Seo, Si Won; Ra, In Sik; Kim, Kun Yeup [ACT Co., Daejeon (Korea, Republic of); Chung, Young Jong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

An advanced integral PWR, SMART (System- Integrated Modular Advanced ReacTor) is being developed in KAERI. It has a compact size and a relatively small power rating (330MWt) compared to a conventional reactor. Because new concepts are applied to SMART, an experimental and analytical validation is necessary for the safety evaluation of SMART. The analytical safety validation is being accomplished by a safety analysis code for an integral reactor, TASS/SMR-S developed by KAERI. TASS/SMR-S uses a lumped parameter one dimensional node and path modeling for the thermal hydraulic calculation and it uses point kinetics for the reactor power calculation. It has models for a general usage such as a core heat transfer model, a wall heat structure model, a critical flow model, component models, and it also has many SMART specific models such as an once through helical coiled steam generator model, and a condensate heat transfer model. To ensure that the TASS/SMR-S code has the calculation capability for the safety evaluation of SMART, the code should be validated for the specific models with the separate effect test experimental results. In this study, TASS/SMR-S critical flow model is evaluated as compared with SMD (Super Moby Dick) experiment

Transit space: The corridor Berlin–Moscow and German-Polish border to Poznan

Directory of Open Access Journals (Sweden)

Wilfried Hackenbroich

2004-01-01

Full Text Available Transit space is about the infrastructure investigations concerning the spatial order of the “corridor” Berlin–Moscow and the most dynamic part of the “corridor” from the German-Polish Border to Poznan. It is based on the research conducted during the Bauhaus Kolleg V, “Transit Spaces: Transitional Cities in Eastern Europe” 2003/04 in the Bauhaus Dessau Foundation. The corridor between Berlin and Moscow is one example for a new spatial order within the postsocialism of Eastern Europe, and the flow of capital and goods, migrant streams, the EU expansion, communication networks and the development of the infrastructure holding it together. Transit economies and multilayered new allocation policies result from the shifting of the EU to the East, and cause new spatial structures and differentiations. Beyond the national borders, new invisible but effective spatial barriers and frontiers have emerged. The case studies, along the two lane transit road from the German Polish border to Poznan reveal an intense sequence of service stations, 24 hour bars, night clubs, restaurants and hotels. Complex service stations were built and placed – like pearls on a chain – along new goods traffic axes at so far undeveloped territories. They are nodes in the network of a global flow of goods, information and products of daily use. This article investigates the conditions and prospects of this new area within the European development.

Immunogenetic markers of Crohn's disease in adults population of the Moscow region

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Stavtsev D.S.

2014-12-01

Full Text Available Aim: to study immunogenetic markers of predisposition to the development and protection for Crohn's disease in adults population of the Moscow region. Material and methods. The study included 53 samples of peripheral blood of patients with Crohn's disease in the Moscow region. The control group was represented by 1,700 samples of umbilical cord blood is healthy newborns. Revealing HLA antigens at low level performed by SSO method on DynalRELI 48 processor. The results received with ambiguous interpretation was using PCR-SSP method (Ivitrogen. Results. Were found the positive and negative associations of groups of HLA alleles with clinical form, the course of Crohn's disease and response to steroid treatment, in particular revealed that, predisposition to the development for Crohn's disease in women and with sensitivity to steroid treatment in this disease associated allele group C*12, to the characteristic restricting markers such as Crohn's disease include the В 38 and A*11 markers nonrestricting, nonpenetrating noninflammatory type groups are alleles B*56 and C*14 and C*14 is also associated with the risk of Crohn's disease in men, characteristic markers of protection to the development of the disease crown with chronic relapsing and severe clinical course are DQB1*02 and DQB1*03, respectively. Conclusion. These results demonstrate the need for studies of gene polymorphism HLA-system, not only in relation to the disease in general, but in selected patients with clinical groups.

Historical flora of Moscow’s Railway Junction (until 2012

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Vinogradova Yulia Konstantinovna

2017-12-01

Full Text Available The article touches upon the biodiversity at the railways. The list of species found within the Moscow Railways (≈300 km from 1851 until today has been compiled based on herbarium data [MHA, MW, LE] and personal observations conducted in 1980-2016. The list of “railways’ flora” includes 1087 taxa from 447 genera of 94 families – this is significantly higher than what is known for the railroads of other regions. A brief comparative analysis with the “railways’ flora” in other regions of the world in respect of the species number, taxonomy and life form spectrum has been performed. The therophytes absolutely prevail in the life-form spectrum (46 percent. The role of the railways as a pathway for alien species has been confirmed. Around 54 percent of all alien plants recorded for the Moscow Region (Moscow and Moscow Region grow along the railways. Several species new for the former USSR territory was found there, as well as many species new for the Moscow Region. The Railways are not only “donors/sources” of alien species, they also act as a refugee area for “the escapees”: over 30 years, Asclepias syriaca has been growing within the section of the Kursk-Moscow railway located near the All-Russian Research Institute of Medical and Aromatic Plants. Galega officinalis, a specie that forms a 200 m2 area of tangled vegetation, was found there, too. A trend when plants fall out of cultivation was established, this is how Sedum hispanicum and S. album emerged. The article also marks the role of the rail slopes as a refugium of rare and endangered plants of the natural flora: some 35 species included in the Red Book of Moscow were found within the area.

Moscow University race-track microtron control system: ideas and development

International Nuclear Information System (INIS)

Chepurnov, A.S.; Gribov, I.V.; Morozov, S.Yu.; Shumakov, A.V.; Zinoviev, S.V.

1992-01-01

Moscow University race-track microtron (RTM) control system is a star-shape network of LSI-11 compatible microcomputers. Each of them is connected with RTM systems via CAMAC; optical fiber coupling is also used. Control system software is designed on Pascal-1, supplemented with real time modules and Macro. A unified real time technique and reenterable data acquisition drivers allow to simplify development of control drivers and algorithms. Among the latter three main types are used: DDC methods, those, based on optimization technique and algorithms, applying models of microtron's systems. Man-machine interface is based on concept of the 'world of accelerator'. It supports means to design, within hardware possibilities, various computer images of the RTM. (author)

Quality control of baby food products on the basis of results obtained using the instrumental neutron-activation analysis technique

International Nuclear Information System (INIS)

Mukhammedov, S.; Khaydarov, A.; Pardaev, O.

2013-01-01

The purpose of this study was to use the instrumental neutron-activation analysis (INAA) to determine the elemental composition of some kind of imported baby food products (BFP) and to compare the results with the permissible contents. The nuclear reactor WWR-SM of INP has been used to develop INAA to study the mineral composition of some children's food products. The concentration of 26 trace elements, including Mg, Ca, Fe, Zn, etc. was found. The comparison of the results with regulation contents and the daily data on food needs have shown that the investigated group of BFP does not meet the requirements for all trace and macro elements composition. (authors)

Geochemical characteristics of black shales from the ore-bearing complex of strata of the Male Karpaty Mts. IV. Evaluation of data on the element contents obtained by neutron activation analysis

Energy Technology Data Exchange (ETDEWEB)

Cambel, B. (Slovenska Akademia Vied, Bratislava (Czechoslovakia). Geologicky Ustav); Khun, M. (Komenskeho Univ., Bratislava (Czechoslovakia). Prirodovedecka Fakulta)

1983-06-01

The application is described of instrumental neutron activation analysis in determining the levels of the individual elements in rocks. Samples were irradiated in the WWR-S reactor at Rez near Prague, and evaluated by the Radiometric Department of the Central Laboratories of the Czechoslovak Uranium Industry. The results are described in detail of measuring the levels of W, Ta, Sc, Hf, Ga, Rb, Cs, U, Th, Au, Sb, As, Zn and Ag in Male Karpaty rocks. The levels of the elements in different samples and in different localities are tabulated. A comparison is made with the Keno Hill, Yukon (USA) area where the polymetallic mineralization is evolutionally analogous to that of the Male Karpaty region.

Geochemical characteristics of black shales from the ore-bearing complex of strata of the Male Karpaty Mts

International Nuclear Information System (INIS)

Cambel, B.; Khun, M.

1983-01-01

The application is described of instrumental neutron activation analysis in determining the levels of the individual elements in rocks. Samples were irradiated in the WWR-S reactor at Rez near Prague, and evaluated by the Radiometric Department of the Central Laboratories of the Czechoslovak Uranium Industry. The results are described in detail of measuring the levels of W, Ta, Sc, Hf, Ga, Rb, Cs, U, Th, Au, Sb, As, Zn and Ag in Male Karpaty rocks. The levels of the elements in different samples and in different localities are tabulated. A comparison is made with the Keno Hill, Yukon (USA) area where the polymetallic mineralization is evolutionally analogous to that of the Male Karpaty region. (M.D.)

Nuclear prehistory influence on transfer velocity of 54Mn impurity 'hot' atoms in irradiated metallic iron

International Nuclear Information System (INIS)

Alekseev, I.E.

2007-01-01

Influence of nuclear prehistory on transfer velocity of 54 Mn impurity 'hot'-atoms - got by different nuclear channels: 56 Fe(d, α), 54 Fe(n,p) in irradiated metallic iron - is studied. Irradiation of targets were carried out in U-120 accelerator (energy range 7.3/5.3 MeV, deuteron beam current makes up 5 μA). Mean density of thermal neutron (WWR-M reactor) makes up 8.6·10 13 neutron·cm -2 ·s -1 . It is shown, that transfer velocity of 54 Mn 'hot' atoms is defining by rate of radiation damage of targets in the irradiation process at that a key importance has a bombarding particles type applied for radioactive label getting

Eugene P. Wigner’s Visionary Contributions to Generations-I through IV Fission Reactors

Directory of Open Access Journals (Sweden)

Carré Frank

2014-01-01

Full Text Available Among Europe’s greatest scientists who fled to Britain and America in the 1930s, Eugene P. Wigner made instrumental advances in reactor physics, reactor design and technology, and spent nuclear fuel processing for both purposes of developing atomic weapons during world-war II and nuclear power afterwards. Wigner who had training in chemical engineering and self-education in physics first gained recognition for his remarkable articles and books on applications of Group theory to Quantum mechanics, Solid state physics and other topics that opened new branches of Physics.

Nuclear science. U.S. electricity needs and DOE's civilian reactor development program

International Nuclear Information System (INIS)

England-Joseph, Judy; Allen, Robert E. Jr.; Fitzgerald, Duane; Young, Edward E. Jr.; Leavens, William P.; Bell, Jacqueline

1990-05-01

Electricity projections developed by the North American Electric Reliability Council (NERC) appear to be the best available estimates of future U.S. electricity needs. NERC, which represents all segments of the utility industry, forecasts that before 1998 certain regions of the country, particularly in the more heavily populated eastern half of the United States, may experience shortfalls during summer peak demand periods. These forecasts considered the utility companies' plans, as of 1989, to meet electricity needs during the period; these plans include such measures as constructing additional generators and conducting demand management programs. Working closely with the nuclear industry, DOE is supporting the development of several reactor technologies to ensure that nuclear power remains a viable electricity supply option. In fiscal year 1990, DOE's Civilian Reactor Development Program was funded at $253 million. DOE is using these funds to support industry-led efforts to develop light water reactors (LWR), advanced liquid-metal reactors (LMR), and modular high-temperature gas-cooled reactors (MHTGR) that are safe, environmentally acceptable, and economically competitive. The utility company officials we spoke with, all of whom were in the Southeast, generally supported DOE's efforts in developing these technologies. However, most of the officials do not plan to purchase nuclear reactors until after 2000 because of the high costs of constructing nuclear reactors and current public opposition to nuclear power

Development and verification of a three-dimensional core model for WWR type reactors and its coupling with the accident code ATHLET. Final report

International Nuclear Information System (INIS)

Grundmann, U.; Lucas, D.; Mittag, S.; Rohde, U.

1995-04-01

The main goal of the project was the coupling of the 3D core model DYN3D for Russian VVER-type reactors, which has been developed in the RCR, with the thermohydraulic code ATHLET. The coupling has been realized on two basically different ways: - The implementation of only the neutron kinetics model of DYN3D into ATHLET (internal coupling), - the connection of the complete DYN3D core model including neutron kinetics, thermohydraulics and fuel rod model via data interfaces at the core top and bottom (external coupling). For the test of the coupling, comparative calculations between internal and external coupling versions have been carried out for a LOCA and a reactivity transient. Complementary goals of the project were: - The development of a DYN3D version for burn-up calculations, - the verification of DYN3D on benchmark tasks and experimental data on fuel rod behaviour, - a study on the extension of the neutron-physical data base. The project contributed to the development of advanced tools for the safety analysis of VVER-type reactors. Future work is aimed to the verification of the coupled code complex DYN3D-ATHLET. (orig.) [de

Mathematical model use for evaluation of radioactivity spreading in nuclear power plant

International Nuclear Information System (INIS)

Kubik, I.; Gladki, Eh.; Yanchik, O.

1976-01-01

On the basis of knowledges of radioactive products behaviour and their spreading in nuclear power plant under normal and accident conditions a KOMPLEX program is developed in the FORTRAN 4 language, permitting to calculate the activity in separate parts of the nuclear power plant with WWR type reactor. The COMPLEX program includes the following subprograms: AZ - PRIM - for estimating active products in fuel, coolant, on the surfaces of fuel element cans and the primary circuit. The subprogram permits to estimate the coolant activity at the expense of fission fragments for 4 different leakage mechanisms: due to diffusion, considerable fuel element damage, contamination of fuel element can surface and fuel washout by coolant; KOR - the program for estimating active corrosion products; ACT - the program for estimating the activity of activation products; CONT - the program for estimating the activity in the nuclear power plant premises (protection envelop) and ventilating pipe. The desciption of the above subprograms is given. For testing of the mathematical model applicability and the possibilities of the corresponding programs the checking calculations for operating parameters of nuclear power plant with WWR type reactor were carried out. The calculation results obtained have shown the applicability of the model suggested and the corresponding programes for nuclear power plant under normal operation and accident conditions [ru

Predicted radionuclide release from marine reactors dumped in the Kara Sea. Report of the source term working group of the international arctic seas assessment project (IASAP)

International Nuclear Information System (INIS)

1997-04-01

The present report summarizes the work carried out by the Source Term Working Group of IASAP during 1994-1996. The report is based on the studies concerning the initial and current radionuclide inventories, operational history and construction of the reactors carried out by Y. Sivintsev of the Russian Research Center ''Kurchatov Institute'', Moscow and E. Yefimov of the Institute of Physics and Power Engineering, Obninsk, Russian Federation. The working group convened five times and evaluated the results of the studies and developed models for prediction of potential releases to the environment. The calculations were carried out at the Royal Naval College, Greenwich, UK, by N. Lynn, J. Warden and S. Timms and at the Lawrence Livermore National Laboratory, California, USA, by M. Mount. 31 refs, 36 figs, 18 tabs

Actions for continued safe wet storage of spent nuclear fuel at VVR-S reactor in Bucharest-Magurele

International Nuclear Information System (INIS)

Isbasescu, M.; Zorliu, A.; Silviu-laurentiu, B.; Stefan, V. . E-mail address of corresponding author: mirifa@ifin.nipne.ro; Isbasescu, M.)

2005-01-01

The Romanian VVR-S research reactor is located 8 kilometers from Bucharest in the town of Magurele and was operated by the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH). The reactor first reached criticality in July 1957 and operated until December 1997 when it was permanently shutdown. The VVR - S reactor of IFIN has two repositories for spent fuel elements: (1) Cooling pool located in the reactor room; (2) Long-term repositories located outside the reactor building - SNFW (spent nuclear fuel warehouse). The major factors believed to influence the pitting of aluminium alloys are conductivity, pH, and bicarbonate, chloride, sulphate and oxygen content. Some of these parameters have been analyzed at SNFW-IFIN-HH. (author)

76 FR 44964 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

Science.gov (United States)

2011-07-27

... Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on August 18, 2011, Room T-2B3, 11545 Rockville Pike... the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of...

Condom use and intimacy among Tajik male migrants and their regular female partners in Moscow.

Science.gov (United States)

Zabrocki, Christopher; Polutnik, Chloe; Jonbekov, Jonbek; Shoakova, Farzona; Bahromov, Mahbat; Weine, Stevan

2015-01-01

This study examined condom use and intimacy among Tajik male migrants and their regular female partners in Moscow, Russia. This study included a survey of 400 Tajik male labour migrants and longitudinal ethnographic interviews with 30 of the surveyed male migrants and 30 of their regular female partners. of the surveyed male migrants, 351 (88%) reported having a regular female partner in Moscow. Findings demonstrated that the migrants' and regular partners' intentions to use condoms diminished with increased intimacy, yet each party perceived intimacy differently. Migrants' intimacy with regular partners was determined by their familiarity and the perceived sexual cleanliness of their partner. Migrants believed that Muslim women were cleaner than Orthodox Christian women and reported using condoms more frequently with Orthodox Christian regular partners. Regular partners reported determining intimacy based on the perceived commitment of the male migrant. When perceived commitment faced a crisis, intimacy declined and regular partners renegotiated condom use. The association between intimacy and condom use suggests that HIV-prevention programmes should aim to help male migrants and female regular partners to dissociate their approaches to condom use from their perceptions of intimacy.

Division of Household Labor as a Source of Contention for Married and Cohabiting Couples in Metropolitan Moscow

Science.gov (United States)

Cubbins, Lisa A.; Vannoy, Dana

2004-01-01

Using data on Moscow couples, this study investigates the division of household labor and its effects on marital conflict and thought of divorce. The hypotheses predict how spouses' economic resources, gender beliefs, and time constraints influence marital contention both directly and indirectly through wife's perceived division of household labor…

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2002-04-01

SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

ASN’s actions in GEN IV reactors and Sodium Fast Reactors (SFR)

International Nuclear Information System (INIS)

Belot, Clotilde

2013-01-01

The ASN is involved in 3 actions concerning GEN IV: • Overview of nuclear reactor GEN IV systems; • Specific analysis about transmutation; • Prototype reactor ASTRID (SFR). Furthermore theses actions are in the beginning (no conclusions or results available)

77 FR 74697 - Meeting of the ACRS, Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting

Science.gov (United States)

2012-12-17

..., Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on January 17, 2013, Room T-2B1, 11545 Rockville Pike... be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty...

Multifactorial biogeochemical monitoring of linden alley in Moscow

Science.gov (United States)

Ermakov, Vadim; Khushvakhtova, Sabsbakhor; Tyutikov, Sergey; Danilova, Valentina; Roca, Núria; Bech, Jaume

2015-04-01

The ecological and biogeochemical assessment of the linden alley within the Kosygin Street was conducted by means of an integrated comparative study of soils, their chemical composition and morphological parameters of leaf linden. For this purpose 5 points were tested within the linden alley and 5 other points outside the highway. In soils, water extract of soil, leaf linden the content of Cu, Pb, Mn, Fe, Cd, Zn, As, Ni, Co Mo, Cr and Se were determined by AAS and spectrofluorimetric method [1]. Macrocomponents (Ca, Mg, K, Na, P, sulphates, chlorides), pH and total mineralization of water soil extract were measured by generally accepted methods. Thio-containing compounds in the leaves were determined by HPLC-NAM spectrofluorometry [2]. On level content of trace elements the soils of "contaminated" points different from background more high concentrations of lead, manganese, iron, selenium, strontium and low level of zinc. Leaf of linden from contaminated sites characterized by an increase of lead, copper, iron, zinc, arsenic, chromium, and a sharp decrease in the level of manganese and strontium. Analysis of the aqueous extracts of the soil showed a slight decrease in the pH value in the "control" points and lower content of calcium, magnesium, potassium, sodium and total mineralization of the water soil extract. The phytochelatins test in the leaves of linden was weakly effective and the degree of asymmetry of leaf lamina too. The most differences between the variants were marked by the degree of pathology leaves (chlorosis and necrosis) and the content of pigments (chlorophyll and carotene). The data obtained reflect the impact of the application of de-icing salts and automobile emissions. References 1. Ermakov V.V., Danilova V.N., Khyshvakhtova S.D. Application of HPLC-NAM spectrofluorimtry to determination of sulfur-containing compounds in the environmental objects// Science of the biosphere: Innovation. Moscow State University by M.V. Lomonosov, 2014. P. 10

HEALTH OF URBAN POPULATION IN MOSCOW AND BEIJING AGGLOMERETIONS

Directory of Open Access Journals (Sweden)

Svetlana M. Malkhazova

2014-01-01

Full Text Available The paper presents the results obtained under the joint Russian-Chinese RFBR project № 12-05-91175-ГФЕН_а aimed at assessment of the state of the environment and health of the population in urban areas in Russia and China. The paper presents the authors’ approach to a comprehensive evaluation of the impact of the environment on the populationhealth of urban agglomerations and a method of regional medico-geographical analysis. A series of analytical and synthetic maps was compiled and used for a comparative geographical analysis of medical and environmental situation in Moscow and Beijing – major metropolitan areas with different natural and socio-economic conditions. The paper discusses the influence of the environment on the state of public health and identifies the leading risk factors, both general and specific to each region.

The main problems of Cycling excursions on the Moscow market

Directory of Open Access Journals (Sweden)

Sergeev A.A.

2016-12-01

Full Text Available the article discusses the reasons of rejection of Bicycle transport. It is noted that the main causes are the heavy ecological situation in Moscow and a large number of vehicles. The authors note that according to the Department of natural resources 90% of pollution is caused by the road transport. To solve this problem, the authors offer to use bicycles and to develop a network of cycle routes and excursions, improve the quality of bike paths to connect them together, to approve the rules of the road (SDA for cyclists, which will reduce the number of accidents with their participation. The article presents strong arguments in favor of the development and use of bicycles and bicycle tours.

Local bifurcation analysis in nuclear reactor dynamics by Sotomayor’s theorem

International Nuclear Information System (INIS)

Pirayesh, Behnam; Pazirandeh, Ali; Akbari, Monireh

2016-01-01

Highlights: • When the feedback reactivity is considered as a nonlinear function some complex behaviors may emerge in the system such as local bifurcation phenomenon. • The qualitative behaviors of a typical nuclear reactor near its equilibrium points have been studied analytically. • Comprehensive analytical bifurcation analyses presented in this paper are transcritical bifurcation, saddle- node bifurcation and pitchfork bifurcation. - Abstract: In this paper, a qualitative approach has been used to explore nuclear reactor behaviors with nonlinear feedback. First, a system of four dimensional ordinary differential equations governing the dynamics of a typical nuclear reactor is introduced. These four state variables are the relative power of the reactor, the relative concentration of delayed neutron precursors, the fuel temperature and the coolant temperature. Then, the qualitative behaviors of the dynamical system near its equilibria have been studied analytically by using local bifurcation theory and Sotomayor’s theorem. The results indicated that despite the uncertainty of the reactivity, we can analyze the qualitative behavior changes of the reactor from the bifurcation point of view. Notably, local bifurcations that were considered in this paper include transcritical bifurcation, saddle-node bifurcation and pitchfork bifurcation. The theoretical analysis showed that these three types of local bifurcations may occur in the four dimensional dynamical system. In addition, to confirm the analytical results the numerical simulations are given.

Structural-Functional Organization of the Eukaryotic Cell Nucleus and Transcription Regulation: Introduction to This Special Issue of Biochemistry (Moscow).

Science.gov (United States)

Razin, S V

2018-04-01

This issue of Biochemistry (Moscow) is devoted to the cell nucleus and mechanisms of transcription regulation. Over the years, biochemical processes in the cell nucleus have been studied in isolation, outside the context of their spatial organization. Now it is clear that segregation of functional processes within a compartmentalized cell nucleus is very important for the implementation of basic genetic processes. The functional compartmentalization of the cell nucleus is closely related to the spatial organization of the genome, which in turn plays a key role in the operation of epigenetic mechanisms. In this issue of Biochemistry (Moscow), we present a selection of review articles covering the functional architecture of the eukaryotic cell nucleus, the mechanisms of genome folding, the role of stochastic processes in establishing 3D architecture of the genome, and the impact of genome spatial organization on transcription regulation.

Floating nuclear heat. And power station 'Pevec' with KLT-40S type reactor plant for remote regions of Russia

International Nuclear Information System (INIS)

Veshnyakov, K.B.; Kiryushin, A.I.; Panov, Yu.K.; Polunichev, V.I.

2000-01-01

Floating small nuclear power plants power for local energy systems of littoral regions of Russia, located far from central energy system, open a new line in nuclear power development. Designing a floating power unit of a lead nuclear heat and power generating station for port Pevec at the Chuckchee national district is currently nearing completion. Most labor-intensive components are being manufactured. The co-generation NPP Pevec is to be created on the basis of a floating power unit with KLT-40S type reactor plant. KLT-40S reactor plant is based on similar propulsion plants, verified at operation of Russia's nuclear-powered civil ships, evolutionary improved by elimination of 'weak points' revealed during its prototypes operation or on the basis of safety analysis. KLT-40S reactor plant uses the most wide-spread and developed in the world practice PWR-type reactor. KLT-40S meets contemporary national and international requirements imposed to future reactor plants. The NHPS description, its main technical-economic data, environmental safety indices, basic characteristics of KLT-40S reactor plant are presented. Prospects of small NPPs utilization outside Russia, particularly as an energy source for sea water desalination, are considered. (author)

Moscow wholesale market meat delicacies and sausages in late 1999 and early 2000.

OpenAIRE

Sidorchuk, Roman

2010-01-01

The main goal of our marketing research is to obtain an overview of the status of the Moscow wholesale market meat delicacies and sausages at the end of 2000. The study was laid expert method, which includes: choice of the form the survey of experts, the definition of the structure and strength of the expert group, the development of survey methodology, survey, list of problems. By the expert survey involved managers and specialists, who know how deeply the problem of organization as a whole,...

The ≪Ukrainian question≫ in the relations between Constantinople and Moscow at the beginning of the 21st century

Directory of Open Access Journals (Sweden)

Anastasia Chibisova

2014-10-01

Full Text Available The article is devoted to an important problem in the relations between the Patriarchates of Moscow and Constantinople at the beginning of the 21st century. The author provides a complex analysis of the infl uence exercised by the ecclesiastical crisis in the Ukraine on the relations between Moscow, Phanar and Kiev. Special attention is paid to the activities of non-recognized Ukrainian ecclesiastical structures and their attempts to join the Orthodox world by way of obtaining recognition on the part of the Church of Constantinople. Their frequent joint meetings held at Phanar proved fruitless; however, they were quite illustrative as to the double standards of the Ecumenical Patriarchate in its policies towards the ecclesiastical schisms in the Ukraine. An important role here,according to the author, was played by the Ukrainian civil authorities, although the relations between Church and state as well as the events of the internal ecclesiastical life in the Ukraine (such as the attempted dialogue between the Ukrainian Autonomous Orthodox Church and the Ukrainian Orthodox Church of the Patriarchate of Kiev are left outside the framework of the present research; facts concerning these areas are cited only when they contribute to the understanding of the processes under analysis. Proceeding from the data of Russian and Ukrainian ecclesiastical periodicals, the author maintains that the problem of the religious life in the Ukraine has long ago overstepped the boundaries of a “local confl ict” and that the “Ukrainian question” plays the part of a powerful catalyst in the inter-Orthodox relations. The Patriarchate of Moscow aims at preserving its status in the Orthodox world. As for the Patriarchate of Constantinople, it keeps voicing certain claims at strengthening its position as primus inter pares among the Orthodox Patriarchates, dreams about convening a new “Ecumenical Council” and puts the Ukraine at stake in its relations with

A small research reactor for the 1980's

International Nuclear Information System (INIS)

Baglin, C.; Collis-Smith, J.A.; Mitchell, B.; Roskilly, T.

1978-01-01

In 1960, GEC together with Imperial College, designed and built the Consort reactor which is still in daily use at the London University Reactor Centre, Silwood Park. In 1977, GEC-REL chose the Consort reactor as a prototype for the development of a modern swimming pool research reactor, designed to meet the needs of countries or organisations starting in the field of Nuclear Technology. This paper outlines some of the topics which arose in the course of this project. (author)

U.S. Department of Energy operational experience with shipments of foreign research reactor spent nuclear fuel

International Nuclear Information System (INIS)

Messick, Charles E.; Massey, Charles D.; Mustin, Tracy P.

1998-01-01

On May 13, 1996, the U.S. Department of Energy issued a Record of Decision on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. The goal of the long-term policy is to recover enriched uranium exported from the United States, while giving foreign research reactor operators sufficient time to develop their own long-term solutions for storage and disposal of spent fuel. The spent fuel accepted by the U.S. DOE under the policy must be out of the research reactors by May 12, 2006 and returned to the United States by May 12, 2009. (author)

The Future of Russia and the Russian Navy. Report of Discussions in Moscow November 2-6, 2003

Science.gov (United States)

2004-01-01

grave existence of their workers. It is also reported that for oil especially, the companies are simply 4. IKEA has found that the average Russian...shopper spends as much as the average Swedish shopper— IKEA is only in Moscow now, but is planning to expand around the country. 5. Erin A. Arvedlund

In-situ stripping of H{sub 2}S in gasoil hydrodesulphurization - reactor design considerations

Energy Technology Data Exchange (ETDEWEB)

Nava, J.A.O.; Krishna, R. [Amsterdam Univ., Dept. of Chemical Engineering, Amsterdam (Netherlands)

2004-02-01

In order to meet future diesel specifications the sulphur content of diesel would need to be reduced to below 50 ppm. This requirement would require improved reactor configurations. In this study we examine the benefits of counter-current contacting of gas oil with H{sub 2}, over conventional co-current contacting in a trickle bed hydrodesulphurization (HDS) reactor. In counter-current contacting, we achieve in-situ stripping of H{sub 2}S from the liquid phase; this is beneficial to the HDS kinetics. A comparison simulation study shows that counter-current contacting would require about 20% lower catalyst load than co-current contacting. However, counter-current contacting of gas and liquid phases in conventionally used HDS catalysts, of 1.5 mm sizes, is not possible due to flooding limitations. The catalysts need to be housed in special wire gauze envelopes as in the catalytic bales or KATAPAK-S configurations. A preliminary hardware design of a counter-current HDS reactor using catalytic bales was carried out in order to determine the technical feasibility. Using a realistic sulphur containing feedstock, the target of 50 ppm S content of desulphurized oil could be met in a reactor of reasonable dimensions. The study also underlines the need for accurate modelling of thermal effects during desulphurization. Our study also shows that interphase mass transfer is unlikely to be a limiting factor and there is a need to develop improved reactor configurations allowing for increased catalyst loading, at the expense of gas-liquid interfacial area. (Author)

The U.S. DOE new production reactor/heavy water reactor facility pollution prevention/waste minimization program

International Nuclear Information System (INIS)

Kaczmarsky, Myron M.; Tsang, Irving; Stepien, Walter P.

1992-01-01

A Pollution Prevention/Waste Minimization Program was established during the early design phase of the U.S. DOE's New Production Reactor/Heavy Water Reactor Facility (NPR/HWRF) to encompass design, construction, operation and decommissioning. The primary emphasis of the program was given to waste elimination, source reduction and/or recycling to minimize the quantity and toxicity of material before it enters the waste stream for treatment or disposal. The paper discusses the regulatory and programmatic background as it applies to the NPR/HWRF and the waste assessment program developed as a phased approach to pollution prevention/waste minimization for the NPR/HWRF. Implementation of the program will be based on various factors including life cycle cost analysis, which will include costs associated with personnel, record keeping, transportation, pollution control equipment, treatment, storage, disposal, liability, compliance and oversight. (author)

HEAVY METALS IN MAPLE AND DANDELION LEAVES FROM DIFERENT LAND-USE AREAS IN MOSCOW ’S EASTERN DISTRICT

Directory of Open Access Journals (Sweden)

Dmitry V. Vlasov

2015-01-01

Full Text Available This article is based on extensive biogeochemical research conducted in Moscow’s Eastern Administrative District, where motor-vehicle traffic and heavy industry have resulted in some of the highest levels of pollution in the city. For this study, 26 samples of maple leaves (Acer platanoides and 49 samples of dandelion leaves (Taraxacum officinalewere collected on a regular grid at 500–700 m intervals. Concentrations of Fe, Mn, Mo, Cd, Pb, Zn, Cu, As and Sb in these plants were measured using atomic absorption spectrometry after washing, drying and HNO3 + H2O2 digestion. Maples accumulated Sb9,7As4,6Mo2,2Fe2,0Zn1,5 Pb1,4Cu1,2, while dandelions accumulated Mo12,7Pb4,9Cd4,4Fe4,3As3,9Sb2,7Cu1,4 — normalized to concentrations in background samples from an unpolluted site west from Moscow. The plants’ geochemical specialization was detected and compared in the following land-use areas: industrial, traffic, recreational, agricultural, and high-, mid-, and low-rise residential development. For maples, the highest concentration factor levels were found in industrial areas, with accumulations of Sb19As2,4Mo1,7Zn1,7Fe1,5Cu1,4Pb1,4. These levels were 2–5 timeslower for maples in other land-use areas. Dandelions and maples do not accumulate Mnbecause of antagonism between Zn, Mo and Mn in soils. Copper is not concentrated byherbaceous species because of antagonism between Mo and Cu. Differences in  eochemical specialization were shown using the Sb/Mo ratio: in dandelions this was 5 times lower than in background samples, while in maples it was 4.5 times higher. A Zv ratio was used to evaluate the intensity of biogeochemical transformation in urban plants. The highest Zv ratios were found in plants near industrial zones and large roads.

Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s

International Nuclear Information System (INIS)

Wright, A.E.; Dutt, D.S.; Harrison, L.J.

1990-01-01

Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs

Risk Factors of Development of Iron-Deficiency Conditions in Moscow Adolescents

Directory of Open Access Journals (Sweden)

I. N. Zakharova

2015-01-01

Full Text Available The article presents data on prevalence structure and causes of iron-deficiency conditions (IDC in adolescents. The authors describe both literature data and the findings of their own study in the adolescents (n = 337 studying at Moscow comprehensive schools. Iron- deficiency anemia was revealed in 5.3% of the examined adolescents, latent iron deficiency — in 17%; vast majority of the last were females. The authors also determined the most common causes of IDC development in adolescents: growth spurt (according to the anamnesis, a source of chronic blood loss (prolonged and abundant menstruations [in girls], frequent nasal bleeding, vegetarianism, intense physical activity, diet compliance, excess weight, and obesity. 

Neutron activation analysis of airborne inorganic pollutants

International Nuclear Information System (INIS)

Oerdoegh, M.; Kalman, L.

1975-01-01

The aim of the studies was to determine the radioactive and non-radioactive pollution of the air in the environment of the atomic reactor WWR-S of the Hungarian Academy of Sciences. Accordingly the investigations were carried out by two ways: the samples were analysed partly without previous irradiation and partly by neutron activation analysis. The use of several filter papers was studied and the most suitable filter paper (Whatman No. 41) was chosen for this investigation. The quantitative determination of more than twenty elements has been performed. First the natural activity of the aerosol samples taken periodically was measured and subsequently they have been analysed after irradiation in the atomic reactor for 1 minute, 1 hour, and 50 hours, respectively. A 45 cm 3 Ge/Li detector/ Nuclear Diodes/ was used in connection with a 1024 channel analyzer /type NTA-512B/. The analyses were made nondestructively, and the gamma-spectra were evaluated by computer. (K.A.)

Preliminary assessment of an S.G.H.W. type research reactor

International Nuclear Information System (INIS)

Bicevskis, A.; Chapman, A.G.; Hesse, E.W.

1970-08-01

A preliminary design study has been made of a research reactor, based on the enriched S.G.H.W.R. concept, to be used for power reactor fuel irradiation, isotope production, basic research, and training in nuclear technology. A reactor physics assessment established a core size which would allow uninterrupted operation for the required irradiation period consistent with low capital and operating costs. A design was selected with 24 channels, a D 2 O calandria diameter of 2.7 m and an overall core height of 4.0 m. The capital cost was estimated as $750,000 for the fuel and $1,600,000 for the moderator, the refuelling cost being $340,000 per annum. A thermal design study showed that the fission heat of 65 MW could be transmitted to pressurised light water at 200 lb/in 2 abs. and rejected to sea water in two conventional U-tube heat exchangers. The basic design is flexible and can be adapted to meet many special requirements. (author)

Interview: Tatyana Lipovskaya, Sisters Sexual Assault Recovery Centre, Moscow, Russia.

Science.gov (United States)

1998-11-01

The Sisters' Sexual Assault Recovery Center was established in Moscow, Russia, in 1993, to address the needs of victims of sexual violence. The Center's help-line received 4029 crisis calls in 1994-97. Most clients are seeking information about medical services or legal aid. Others call about employment, HIV/AIDS, alcoholism, and drug abuse. Services are available without regard to age, sex, occupation, or sexual orientation. Program funding has come entirely from Western foundations and organizations. Although Russia has not passed a law on domestic violence, the post-Communism government is reluctantly starting to acknowledge that rape and domestic violence are serious social problems. The Center runs an educational program for law enforcement officers to increase their sensitivity and create an environment of safety for women who report sexual violence.

The regulation on commercial reactors and the management of high-level radioactive wastes in U.S

International Nuclear Information System (INIS)

Shimomura, Hidetsugu

2013-01-01

This article shows U.S. NRC's substantial and procedural regulations regarding commercial reactors and radioactive wastes. The commercial reactor's regulations are analyzed from an ensuring safety, and the radioactive waste' management is done from a locating a disposal site. (author)

"A Riddle, Wrapped in a Mystery, inside an Enigma": Teaching Post-Socialist Transformation to UK Students in Moscow

Science.gov (United States)

Moran, Dominique; Round, John

2010-01-01

In the 20 years since the fall of the Berlin Wall, teaching post-socialist transition to undergraduate students has become increasingly challenging. This paper relates the development, planning and operation of a fieldwork module in Moscow, for Year Three geography undergraduates. It argues that "on-street" teaching and imaginative use…

Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

International Nuclear Information System (INIS)

Ene, D.; Cepraga, D.G.

2002-01-01

The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

To question of NPP power reactor choice for Kazakhstan

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

2004-01-01

in the regions of Republic of Kazakhstan occurs. Southern and western regions import electric power and capacity because of undeveloped circuit of networks. Moreover, power intensity of an industrial-agrarian complex of the country is limited transmission capacity of lines is insufficient; plenty of small consumers are removed from power supply lines. Thus, nuclear stations of medium and low power are the most acceptable for construction in Kazakhstan. Recommendations for the choice of maximum safe, reliable and economically competitive reactors for Kazakhstan have been made in result of the carried out projects' comparison of the power reactors according to 15 criteria of safety and economic competitiveness, with respect to condition and perspectives of Kazakhstan power complex development: Recommended power reactors of medium capacity: - P-600 - passive PWR, developed of the Westinghouse company, USA; - CANDU-6, developed by Atomic Energy of Canada, Limited (AECL), Canada. - MS-600 - Mitsubishi Company, Japan. Recommended reactors of low power: - IRIS - reactor of IV generation developed by the international corporation of 13 organizations from 7 countries; - NPP 'UNITERM' - development NIKIET, Moscow, Russia; - MRX - the Project of sea reactor MRX for civil applications, is developed by the Japanese Research Institute of Atomic Energy (JAERI). The most important advantages of recommended medium and low power reactors are given

To question of NPP power reactor choice for Kazakhstan

International Nuclear Information System (INIS)

Batyrbekov, G.A.; Makhanov, Y.M.; Reznikova, R.A.; Sidorenco, A.V.

2004-01-01

regions of Republic of Kazakhstan occurs. Southern and western regions import electric power and capacity because of undeveloped circuit of networks. Moreover, power intensity of an industrial-agrarian complex of the country is limited transmission capacity of lines is insufficient; plenty of small consumers are removed from power supply lines. Thus, nuclear stations of medium and low power are the most acceptable for construction in Kazakhstan. Recommendations for the choice of maximum safe, reliable and economically competitive reactors for Kazakhstan have been made in result of the carried out projects' comparison of the power reactors according to 15 criteria of safety and economic competitiveness, with respect to condition and perspectives of Kazakhstan power complex development: Recommended power reactors of medium capacity: - P-600 - passive PWR, developed of the Westinghouse company, USA; - CANDU-6, developed by Atomic Energy of Canada, Limited (AECL), Canada. - MS-600 - Mitsubishi Company, Japan. Recommended reactors of low power: - IRIS - reactor of IV generation developed by the international corporation of 13 organizations from 7 countries; - NPP 'UNITERM' - development NIKIET, Moscow, Russia; - MRX - the Project of sea reactor MRX for civil applications, is developed by the Japanese Research Institute of Atomic Energy (JAERI). The most important advantages of recommended medium and low power reactors are given

Integral Inherently Safe Light Water Reactor (I2S-LWR)

International Nuclear Information System (INIS)

Petrovic, Bojan; Memmott, Matthew; Boy, Guy; Charit, Indrajit; Manera, Annalisa; Downar, Thomas; Lee, John; Muldrow, Lycurgus; Upadhyaya, Belle; Hines, Wesley; Haghighat, Alierza

2017-01-01

This final report summarizes results of the multi-year effort performed during the period 2/2013- 12/2016 under the DOE NEUP IRP Project ''Integral Inherently Safe Light Water Reactors (I 2 S-LWR)''. The goal of the project was to develop a concept of a 1 GWe PWR with integral configuration and inherent safety features, at the same time accounting for lessons learned from the Fukushima accident, and keeping in mind the economic viability of the new concept. Essentially (see Figure 1-1) the project aimed to implement attractive safety features, typically found only in SMRs, to a larger power (1 GWe) reactor, to address the preference of some utilities in the US power market for unit power level on the order of 1 GWe.

The CEA research reactors

International Nuclear Information System (INIS)

Schwartz, J.P.

1993-01-01

Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization

International Nuclear Information System (INIS)

Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

2004-01-01

The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies

Cosmic Rays in the 'Urusvati' Institute from Archives of Nicolas Roerich Centre-Museum (Moscow)

International Nuclear Information System (INIS)

Miroshnichenko, L I; V I Sidorov

2013-01-01

The history of cosmic ray study by means of ground-based methods in the 1930s contains some gaps. The press barely covered the study of cosmic rays at the 'Urusvati' Himalayan Research Institute that functioned in the Indian Himalayas in 1928-1939. Archival materials of the 'Urusvati' Institute now stored at the International Centre-Museum named after N.K. Roerich (Moscow), give evidence to the active participation of the Institute staff in the study of cosmic rays. By the initiative of A.H. Compton, in 1932 several expeditions on the studies of cosmic rays were organized in different parts of the world. One of these expeditions passed through the Himalayas in the region of the South-Eastern Ladakh. The report on this highland expedition which took place at the altitude of 19,500 feet above the sea level was published by J.M. Benade in the 'Urusvati Journal' (was issued during 1931-1933). Cooperation between George Roerich, the Institute Director, and Prof. J.M. Benade in expedition to Ladakh has been documented.

V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

Energy Technology Data Exchange (ETDEWEB)

Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

2010-07-15

V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

International Nuclear Information System (INIS)

Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

2010-07-01

V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

POST-SOCIALIST POST-SUBURBIA: GROWTH MACHINE AND THE EMERGENCE OF “EDGE CITY” IN THE METROPOLITAN CONTEXT OF MOSCOW

Directory of Open Access Journals (Sweden)

Oleg Golubchikov

2010-01-01

Full Text Available To what extent do the ideas of “edge city”, “post-suburbia” and associated models of urban growth apply in the transition economy case? The paper considers urban development and place-making on the periphery of Moscow, based on the case of Khimki, a former off-limits “satellite city” and more recently a fast-growing area. The forces and ideologies driving the growth on the edge of Moscow and the relationship between different actors are considered. The paper argues that while the Russian case shares some commonalities with the Western models of “edge city” and “growth machine”, growth in Khimki is fuelled by opportunistic profit-making initiatives that are disconnected from “local” city. It is yet to be seen whether a growing demand for new infrastructure, as well as emerging residents’ movements will restructure the modes of governing urban growth more in line with proactive place-focused post-suburban politics.

Passive Decay Heat Removal System Options for S-CO2 Cooled Micro Modular Reactor

International Nuclear Information System (INIS)

Moon, Jangsik; Jeong, Yong Hoon; Lee, Jeong Ik

2014-01-01

To achieve modularization of whole reactor system, Micro Modular Reactor (MMR) which has been being developed in KAIST took S-CO 2 Brayton power cycle. The S-CO 2 power cycle is suitable for SMR due to high cycle efficiency, simple layout, small turbine and small heat exchanger. These characteristics of S-CO 2 power cycle enable modular reactor system and make reduced system size. The reduced size and modular system motived MMR to have mobility by large trailer. Due to minimized on-site construction by modular system, MMR can be deployed in any electricity demand, even in isolated area. To achieve the objective, fully passive safety systems of MMR were designed to have high reliability when any offsite power is unavailable. In this research, the basic concept about MMR and Passive Decay Heat Removal (PDHR) system options for MMR are presented. LOCA, LOFA, LOHS and SBO are considered as DBAs of MMR. To cope with the DBAs, passive decay heat removal system is designed. Water cooled PDHR system shows simple layout, but has CCF with reactor systems and cannot cover all DBAs. On the other hand, air cooled PDHR system with two-phase closed thermosyphon shows high reliability due to minimized CCF and is able to cope with all DBAs. Therefore, the PDHR system of MMR will follows the air-cooled PDHR system and the air cooled system will be explored

LANDSCAPE-FUNCTIONAL ZONING OF CITY TERRITORIES (THE CASE OF EASTERN AND WESTERN DISTRICTS OF MOSCOW

Directory of Open Access Journals (Sweden)

I. A. Labutina

2013-01-01

Full Text Available Methodical approaches to landscape-functional mapping based on functional zoning and analysis of the landscape structure were developed. The technique was tested for the geoinformation mapping of Eastern and Western Districts of Moscow. The synthetic landscape-functional maps of the districts in scale of 1:50 000 showing the differentiation of urban landscapes in the degree of accumulation and the environmental risk of soils and snow cover pollution with heavy metals was compiled.

Topics in quantum groups and finite-type invariants mathematics at the independent University of Moscow

CERN Document Server

Arkhipov, S M; Odesskii, A V; Feigin, B; Vassiliev, V

1998-01-01

This volume presents the first collection of articles consisting entirely of work by faculty and students of the Higher Mathematics College of the Independent University of Moscow (IUM). This unique institution was established to train elite students to become research scientists. Covered in the book are two main topics: quantum groups and low-dimensional topology. The articles were written by participants of the Feigin and Vassiliev seminars, two of the most active seminars at the IUM.

The History with Two Prehistories. On the design of the Moscow Palace of Young Pioneers

Directory of Open Access Journals (Sweden)

Felix Novikov

2016-11-01

Full Text Available The article refers to the history of design of the Moscow Palace of Young Pioneers architectural complex on Leninskie (now Vorobievy Gory viewed in the context of evolution of the national architecture. While speaking about how the project came into being and which way was chosen to find the architectural character, the author proves that the Palace was a pivotal point in the history of Russian architecture and became one of the symbols of Soviet Modernism.

Safety evaluation report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission for U.S. Energy Research and Development Administration Light Water Breeder Reactor. Special project No. 561

International Nuclear Information System (INIS)

1976-07-01

The Safety Evaluation Report is presented for the Light Water Breeder Reactor (LWBR). The LWBR core is to be installed in the Shippingport reactor at the Shippingport Atomic Power Station. The Safety Evaluation Report is the result of an NRC staff review of the LWBR Safety Analysis Report submitted by the Division of Naval Reactors, U. S. Energy Research and Development Administration. As a result of its review, the NRC staff has recommended that: (1) a diverse trip signal, such as containment high pressure, be included in a 2-out-of-3 logic for initiation of safety injection; (2) power be locked out from the pressurizer surge isolation valve during normal operation; and (3) a chlorine monitor be installed in the main control room

Experimental study on Response Parameters of Ni-rich NiTi Shape Memory Alloy during Wire Electric Discharge Machining

Science.gov (United States)

Bisaria, Himanshu; Shandilya, Pragya

2018-03-01

Nowadays NiTi SMAs are gaining more prominence due to their unique properties such as superelasticity, shape memory effect, high fatigue strength and many other enriched physical and mechanical properties. The current studies explore the effect of machining parameters namely, peak current (Ip), pulse off time (TOFF), and pulse on time (TON) on wire wear ratio (WWR), and dimensional deviation (DD) in WEDM. It was found that high discharge energy was mainly ascribed to high WWR and DD. The WWR and DD increased with the increase in pulse on time and peak current whereas high pulse off time was favourable for low WWR and DD.

DEFINITION OF THE STRATEGIC DIRECTIONS FOR REGIONAL ECONOMIC DEVELOPMENT ON THE EXAMPLE OF THE MOSCOW OBLAST

Directory of Open Access Journals (Sweden)

Dmitriy V. Mikheev

2014-01-01

Full Text Available This article distinguishes methods applied to a definition of the strategicdirections for regional economic development on the economic basestatistical analysis identified sources of competitive advantage and disadvantage for the region, main risks for economic growth. The methodswere approved via the research work on the definition of the prioritiesand target goals for the Moscow Oblast economic development andframework improvement for strategy planning and public regulations.

Moscow, the third Rome: A contribution to history of Russian messianism, 2nd part

Directory of Open Access Journals (Sweden)

Subotić Milan

2011-01-01

Full Text Available In the second part of the text about the Filofei’s doctrine of “Moscow, Third Rome,” the author deals with its reception in later periods of Russian intellectual and political history. Although this doctrine in its original form had no explicit imperial or foreign-political connotation, this paper analyzes the interpretations of the “Third Rome idea” that had significant political consequences. Internally, this idea was used by Prince Kurbskii for the criticism of Ivan the Terrible’s politics (XVI Century, as well as the rejection of the church reforms of Patriarch Nikon in the Old Believers’ literature (XVII Century. However, the revival of interest in the idea of the “Third Rome” characterized the Russian nineteenth century when the discussions on the relationship between Russia and the West emerged. Criticizing the reforms by Peter the Great, the classical Slavophiles found confirmation of the Russian cultural originality and superiority in the past of traditional Muscovy. The author highlights the differences between religious-philosophical and geopolitical interpretations of Russian messianism in the works of Russian Slavophiles and Panslavs. In the final section of this article, Russian messianic ideas are put in a relation with the birth of nationalism in the context of the Russian Empire. In this way, the author’s findings call into question the widespread interpretation of the “Third Rome messianism” as a distinctive and exceptional Russian characteristic.

Radiation safety in the Moscow region: Experience of cooperation SUE SIA Radon with mass media and public

Energy Technology Data Exchange (ETDEWEB)

Grishin, O.; Rakov, S. [SUE SIA RADON, Moscow (Russian Federation)

2012-07-01

Radiation safety in the present period acquires complex character and closely corresponds with other elements of social and political process, with various spheres of public life. After earthquake in Japan in March 11, 2011 and emergency on the nuclear power plant Fukushima-1 the theme of radiating safety of megapolises has today become urgent, as never. Provision of radiation safety of the Moscow region, taking into account a number of factors, is an important problem in a context of modernization state. Today in sphere of radio ecological safety there are certain achievements: new monitoring systems are developed, technological processes are improved, new information-communicative channels of interaction with mass media and public are formed. Information policy of enterprises the functioning of which is connected with provision of safe ecological conditions and its monitoring is focused on constant and duly informing of public through mass-media. Experience and technologies of interaction with mass-media and public of Moscow State Unitary-Enterprise- united ecological, scientific and research centre of decontamination of radioactive waste and environmental protection (State Unitarian Enterprise, Scientific and Industrial Association Radon, SUE SIA RADON) is submitted in the article. (author)

Radiation safety in the Moscow region: Experience of cooperation SUE SIA Radon with mass media and public

International Nuclear Information System (INIS)

Grishin, O.; Rakov, S.

2012-01-01

Radiation safety in the present period acquires complex character and closely corresponds with other elements of social and political process, with various spheres of public life. After earthquake in Japan in March 11, 2011 and emergency on the nuclear power plant Fukushima-1 the theme of radiating safety of megapolises has today become urgent, as never. Provision of radiation safety of the Moscow region, taking into account a number of factors, is an important problem in a context of modernization state. Today in sphere of radio ecological safety there are certain achievements: new monitoring systems are developed, technological processes are improved, new information-communicative channels of interaction with mass media and public are formed. Information policy of enterprises the functioning of which is connected with provision of safe ecological conditions and its monitoring is focused on constant and duly informing of public through mass-media. Experience and technologies of interaction with mass-media and public of Moscow State Unitary-Enterprise- united ecological, scientific and research centre of decontamination of radioactive waste and environmental protection (State Unitarian Enterprise, Scientific and Industrial Association Radon, SUE SIA RADON) is submitted in the article. (author)

Training activities and perspectives in the radioactive waste management area of Moscow SIA 'Radon' - 16131

International Nuclear Information System (INIS)

Batyukhnova, O.G.; Arustamov, A.E.; Dmitriev, S.A.; Arustamova, N.A.; Ojovan, M.; Drace, Z.

2009-01-01

The education service for specialists dealing with radioactive waste was established in Russia (former USSR) in 1983 and was based on the capabilities of two organisations: Moscow Scientific and Industrial Association 'Radon' (SIA 'Radon') and Lomonosov's Moscow State University. These two organizations are able jointly to offer training programs in the science fundamentals, applied research and in practical operational areas of the all pre-disposal activities of the radioactive waste management (RWM). Since 1997 this system was upgraded to the international level and now acts as the International Education Training Centre (IETC) at SIA 'Radon' under the guidance of the IAEA. During last 12 years more than 350 specialists from 33 European and Asian countries enhanced their knowledge and skills in RWM. The IAEA supported many specialized regional training courses and workshops, fellowships, on-the-job training, and scientific visits which are additional means to assure development of personnel capabilities. Efficiency of training was analysed at IETC using the structural adaptation of educational process as well as factors, which have influence on education quality. In addition social-psychological aspects were also taken into account in assessing the overall efficiency. The analysis of the effect of individual factors and the efficiency of education activity were carried out based on appraisal results and post-course questioning of attendees. (authors)

U.S. Research Program to Support Advanced Reactors and Fuel Cycle Options

International Nuclear Information System (INIS)

Lyons, Peter

2013-01-01

• In recognition of possible future needs, the U.S. will perform R&D on advanced reactor and fuel cycle technologies that could dramatically improve nuclear energy safety and performance; • Multifaceted approach to support R&D: - National labs; - Universities; - Industry; - International partners

V.S.O.P.-computer code system for reactor physics and fuel cycle simulation

International Nuclear Information System (INIS)

Teuchert, E.; Hansen, U.; Haas, K.A.

1980-03-01

V.S.O.P. (Very Superior Old Programs) is a system of codes linked together for the simulation of reactor life histories. It comprises neutron cross section libraries and processing routines, repeated neutron spectrum evaluation, 2-D diffusion calculation based on neutron flux synthesis with depletion and shutdown features, incore and out-of-pile fuel management, fuel cycle cost analysis, and thermal hydraulics (at present restricted to Pebble Bed HTRs). Various techniques have been employed to accelerate the iterative processes and to optimize the internal data transfer. A limitation of the storage requirement to 360 K-bites is achieved by an overlay structure. The code system has been used extensively for comparison studies of reactors, their fuel cycles, and related detailed features. Beside its use in research and development work for the high temperature reactor the system has been applied successfully to LWR and Heavy Water Reactors. (orig.) [de

THE SCALE AND PREVALENCE OF INCLUSIVE EDUCATION FOR MINORS IN MOSCOW: THE POSSIBILITIES FOR QUANTITATIVE ASSESSMENT

Directory of Open Access Journals (Sweden)

Oksana V. Kuchmayeva

2014-01-01

Full Text Available The article is devoted to the problems of assessingthe prevalence of inclusive education. The authors on the issues of statistical accounting of such category of students as children with disabilities, aswell as the educational institutions providing educational services, are assessing the needs in inclusiveeducation. During the analysis the authors usedthe data of statistical accounting, materials of thesample study «Availability of educational services for children with disabilities in the Moscow».

Reactor coolant pump seal issues and their applicability to new reactor designs

International Nuclear Information System (INIS)

Ruger, C.J.; Higgins, J.C.

1993-01-01

Reactor Coolant Pumps (RCPs) of various types are used to circulate the primary coolant through the reactor in most reactor designs. RCPs generally contain mechanical seals to limit the leakage of pressurized reactor coolant along the pump drive shaft into the containment. The relatively large number of RCP seal and seal auxiliary system failures experienced at U.S. operating plants during the 1970's and early 1980's raised concerns from the U.S. Nuclear Regulatory Commission (NRC) that gross failures may lead to reactor core uncovery and subsequent core damage. Some seal failure events resulted in a loss of primary coolant to the containment at flow rates greater than the normal makeup capacity of Pressurized Water Reactor (PWR) plants. This is an example of RCP seal failures resulting in a small Loss of Coolant Accident (LOCA). This paper discusses observed and potential causes of RCP seal failure and the recommendations for limiting the likelihood of a seal induced small LOCA. Issues arising out of the research supporting these recommendations and subsequent public comments by the utility industry on them, serve as lessons learned, which are applicable to the design of new reactor plants

Nuclear non-proliferation: the U.S. obligation to accept spent fuel from foreign research reactors

International Nuclear Information System (INIS)

Shapar, Howard K.; Egan, Joseph R.

1995-01-01

The U.S. Department of Energy (DOE) had a 35-year program for the sale and receipt (for reprocessing) of high-enriched research reactor fuel for foreign research reactors, executed pursuant to bilateral agreements with nuclear trading partners. In 1988, DOE abruptly let this program lapse, citing environmental obstacles. DOE promised to renew the program upon completion of an environmental review which was to take approximately six months. After three and a half years, an environmental assessment was finally produced.Over a year and half elapsed since publication of the assessment before DOE finally took action to renew the program. The paper sets forth the nuclear non-proliferation and related foreign policy considerations which support renewal of the program. It also summarized the contractual and other commitments made to foreign research reactors and foreign governments and aspects of U.S. environmental law as they apply to continuation of the program. (author)

Semiotics and Cartomancy: Tartu-Moscow Semiotic School Legacy

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Mattia Thibault

2015-12-01

Full Text Available This paper aims to reconstruct the fortune of the semiotic analysis of cartomancy, considered as a proper semiotic system, focusing in particular on the point of view of Tartu-Moscow School of Semiotics (TMS. TMS, founded by the renowned semiotician Yuri Lotman, offers one of the most interesting semiotic approaches to culture and communication yet is still partially ignored in the West with the exception, of course, of its founder. Many TMS scholars approached cartomancy not only as an interesting cultural phenomenon but as a case study allowing them to test analytic tools that fit for many different forms of communication. Cartomancy is, at the same time, a quite simple semiotic system and a very sophisticated cultural phenomenon; this makes it a very useful object of study, allowing us to manipulate an entire (and rich language while looking for the basic workings of all kinds of communication. The article will show how TMS analysis of cartomancy has already been quite productive and has had a few entails as well as how these analyses could help us to reach a better understanding of play, which is one of the biggest challenges that communication studies are facing today.

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2001-04-01

The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

Dry reloading and packaging of spent fuel at TRIGA MARK I reactor of Medical University Hanover (MHH), Germany

International Nuclear Information System (INIS)

Haferkamp, D.

2008-01-01

Between 1994 and 1998 the equipment for dry reloading of a research reactor was developed by Noell, which was funded by the German Federal Government and State of Saxonia. The task of this development programme was the design and delivery of an equipment able to load the spent fuel into the shipping casks in a dry mode for research reactors, where wet loading inside the storage pool is impossible. ALARA and infrastructure conditions had to be taken into consideration. Most of the research reactors of TRIGA MARK I type or WWR-SM have operating modes for handling of spent fuel inside the pond or for transfer of spent fuel from pond to dry/wet storage pools. On the other hand, most of them cannot handle heavy weighted shipping casks inside the reactor building because of the crane capacity, or inside water pool because of dimensions and weight of shipping casks. A typical licensed normal operating procedure for spent fuel in research reactors (TRIGA MARK I) is shown. Dry unloading procedure is described. Additionally to the normal operating procedures at the MHH research reactor the following steps were necessary: - dry packaging of spent fuel elements into the loading units (six packs) in order to minimise the transfer and loading steps between the pool and shipping cask; - transfer of spent fuel loading units from dry storage pool to the shipping cask (outside the reactor building) in a shielded transfer cask; - dry reloading of loading units, into the shipping casks outside the reactor building. The Dry Reloading Equipment implies the following 5 items: 1. loading units (six packs), which includes: - capacity up to six spent fuel elements; - criticality safe placement of spent fuel elements; - handling of several spent fuel elements in an aluminium loading unit. 2. Special Transfer Cask, which includes: - shielded housing with locks; - gripper inside housing; - hoist outside housing; - computer aided operation mode for loading and unloading. 3. Transfer Vehicle

ROLE OF COMMON VESTRY OF ST. NICHOLAS CHURCH IN MAROSEIKA STREET IN SPIRITUAL LIFE OF MOSCOW IN XXTH CENTURY

Directory of Open Access Journals (Sweden)

Анна Филипповна Грушина

2015-12-01

Full Text Available The article concentrates on the history of the formation and development of the Common Vestry of Moscow Church of St. Nicholas in Klenniki. There are revealed the outstanding characteristics of the living, its spiritual origins and bonds. In the centre of the research is the ministration of two hegumens of the church, namely: archpriest Alexius Mechov and his son priest Sergius Mechov. The father started the penancing-liturgical family and the son continued the father's work, retained and enriched his pastoral heritage. The Common Vestry of the Church of St. Nicholas in Klenniki, which had been guided by father Sergius, turned out to be one of the most wonderful phenomena of the Russian Church history of the previous century. In the years of the persecutions against the Church it survived. The peculiarity of this living was that it was disintegrated after the shutdown of the church and the taking away of the pastors. This peculiarity is unique not only for Moscow, but also for all Russian Orthodox Church.

GIS-Based Education Course for Bachelor of Management Program in the Lomonosov Moscow State University Business School

OpenAIRE

A. Pirogov

2014-01-01

An optional course, "Geographical Aspects of Business" in the framework of the Bachelor of management program in the Lomonosov Moscow State University Business School is setting the goal to introduce future discipline specialists with geographical topics of current interest for management and provide knowledge, skills and expertise of geospatial analysis and the use of geoinformation technologies in finding solutions to economic and managerial tasks. The students' feedback shows inte...

Foreign Reports about Stepan Razin’s Execution. New Documents from the Stockholm Archive

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Gleb M. Kazakov

2017-12-01

Full Text Available This paper analyzes reports written by foreign authors about the execution of Stepan Razin. The main focus is on two dispatches written by the Swedish citizen and merchant in Moscow, Christoff Koch, in May–June 1671 and sent to Narva, and from there, they were forwarded to the Swedish capital, among other places. They are now kept at the State Archives in Stockholm, and they have not been discussed previously in the scholarly literature. The paper contains the full translation into Russian of two long reports written by Koch about Razin’s capture, delivery to Moscow, interrogation, and execution, with our comments. Special attention is given to a unique colored drawing, showing the brothers, Stepan and Frol Razin, as well as the body parts of the executed Stepan. From the written documents it becomes clear that the drawing was sent from Moscow to the governor of Swedish Ingria in Narva, and then forwarded to Stockholm, together with the two Koch dispatches. The authors come to the conclusion that several copies must have been made and that they were intentionally distributed among foreigners in Moscow. Most probably only one copy has survived to our days, the one in Stockholm. Arguments are given for the hypothesis that one copy of the drawing ended up in England and served as the prototype for the well-known imprint of 1672, which shows the Razin brothers when they were being delivered to Moscow. In our study we also compare the information given by Koch with descriptions of Razin’s death that were published in West-European newspapers, pamphlets, and books during the 1670s. This comparison brings us to the conclusion that the information about the execution of the leader of the rebellion reached the European press from several witnesses to the events, and that, over time, the original information was filled out with invented details.

[Epizootic and epidemic manifestation of natural foci of tularemia in Moscow region (1965-2013)].

Science.gov (United States)

Demidova, T N; Popov, V P; Polukhina, A N; Orlov, D S; Mescheryakova, I S; Mikhailova, T V

2015-01-01

Detection of contemporary features of tularemia focimanifestations, determination of territories of high epidemic risk in various landscape zones and creation of a map of foci territories of Moscow Region for isolation of tularemia infectious agent cultures and registered human morbidity for justified planning of prophylaxis measures. Report materials of epizootologic examinations of natural foci for 1965-2013, 156 maps of epidemiologic examination of cases of human infection with tularemia, results of studies of casting of predatory birds and dung of predatory mammals were used. Registered morbidity and isolation of tularemia infectious agent cultures from 1965 to date were applied to an electronic map of Moscow Region by sign method using modern. GIS-technologies (MapInfo 10.5 program). Electronic maps Ingit at 1:200,000 scale, as well as Google Earth program were used to search for base points. Analysis of morbidity has revealed structure change in human tularemia morbidity--an increase of the fraction of urban population and a decrease of the fraction of patients among rural inhabitants, unimmunized against this infection are mostly ill. The presence of DNA of tularemia causative agent in biological objects in the complex with serologic and bacteriological studies was shown to allow to detect flaccid epizootics even at low numbers of rodents. Cartographic reflection of registered morbidity and isolation of tularemia infectious agent cultures allowed to show territories with various degrees of epizootic activity and epidemic manifestation. Positive results of serologic and molecular-genetic studies of environmental objects gives evident on epizootic activity and constant risk of aggravation of epidemic situation for this infection.

Microwaves in the cold war: the Moscow embassy study and its interpretation. Review of a retrospective cohort study

Directory of Open Access Journals (Sweden)

Elwood J

2012-11-01

Full Text Available Abstract Background From 1953 to 1976, beams of microwaves of 2.5 to 4.0 GHz were aimed at the US embassy building in Moscow. An extensive study investigated the health of embassy staff and their families, comparing Moscow embassy staff with staff in other Eastern European US embassies. The resulting large report has never been published in peer reviewed literature. Methods The original report and other published comments or extracts from the report were reviewed. Results The extensive study reports on mortality and morbidity, recorded on medical records and by regular examinations, and on self-reported symptoms. Exposure levels were low, but similar or greater than present-day exposures to radiofrequencies sources such as cell phone base stations. The conclusions were that no adverse health effects of the radiation were shown. The study validity depends on the assumption that staff at the other embassies were not exposed to similar radiofrequencies. This has been questioned, and other interpretations of the data have been presented. Conclusions The conclusions of the original report are supported. Contrary conclusions given in some other reports are due to misinterpretation of the results.

Automation drying unit molybdenum-zirconium gel radioisotope production technetium-99M for nuclear medicine

International Nuclear Information System (INIS)

Chakrova, Y.; Khromushin, I.; Medvedeva, Z.; Fettsov, I.

2014-01-01

Full text : Since 2001 the Institute of Nuclear Physics of the Republic of Kazakhstan has began production of radiopharmaceutical based on technetium-99m from irradiated reactor WWR-K of natural molybdenum, which allows to obtain a solution of technetium-99m of the required quality and high volume activity. In 2013 an automated system is started, which is unique and urgent task is to develop algorithms and software in Python, as well as the manufacture of certain elements of technological systems for automated production

The concept of the sodium cooled small fast reactor 4S and the analyses of the loss of flow events

International Nuclear Information System (INIS)

Nishi, Yoshihisa; Ueda, Nobuyuki; Koga, Tomonari; Matsumiya, Hisato

2007-01-01

CRIEPI has been developing the 4S reactor (Super Safe, Small and Simple reactor) for application in dispersed energy supply and multipurpose use, in conjunction with Toshiba Corporation. The 4S is sodium cooled fast reactor and their electrical output has two options of 10MWe and 50MWe. In this paper, 10MWe 4S (4S-10M) was proposed. 4S-10M has some unique features. It employs a burn-up control system with annular reflector in place of the control rod that requires the frequent maintenance service. The core life time of the 4S-10M is 30 years and the fuel transport is not required during core life time. All temperature feedback coefficients are negative during core life time. In the latest design for 4S-10M, a pool and tall type reactor design was selected to reduce the construction cost. Two types of decay heat removal system (Reactor Vessel Auxiliary Cooling System; RVACS, Intermediate Reactor Auxiliary Cooling System; IRACS) using natural convection power were adopted. It is necessary to confirm that these two heat removal system can operate appropriately. The transition analyses were executed by the CERES code to evaluate the design feasibility and the thermal hydraulic characteristics of the 4S-10M. CERES is a multi-dimensional plant dynamics simulation code for liquid metal reactors developed by the CRIEPI. CERES can perform simulations ranging from forced circulation (full/partial power operation) to natural circulation. Components (pumps, IHXs, SGs, pipings, etc.) of the reactor are modeled as one-dimensional. Multi-dimensional plena are connected to such components. Two loss-of-flow accident sequences are considered. In the first case, it is assumed that the primary and the secondary pump were stopped by the total station black out. The reactor shut down system was assumed to be success. This sequence is referred to as the protected loss-of-flow accident (PLOF). In the second case, it is assumed that the reactor shut down systems fail to operate and the

Computational and Experimental Investigations of the Coolant Flow in the Cassette Fissile Core of a KLT-40S Reactor

Science.gov (United States)

Dmitriev, S. M.; Varentsov, A. V.; Dobrov, A. A.; Doronkov, D. V.; Pronin, A. N.; Sorokin, V. D.; Khrobostov, A. E.

2017-07-01

Results of experimental investigations of the local hydrodynamic and mass-exchange characteristics of a coolant flowing through the cells in the characteristic zones of a fuel assembly of a KLT-40S reactor plant downstream of a plate-type spacer grid by the method of diffusion of a gas tracer in the coolant flow with measurement of its velocity by a five-channel pneumometric probe are presented. An analysis of the concentration distribution of the tracer in the coolant flow downstream of a plate-type spacer grid in the fuel assembly of the KLT-40S reactor plant and its velocity field made it possible to obtain a detailed pattern of this flow and to determine its main mechanisms and features. Results of measurement of the hydraulic-resistance coefficient of a plate-type spacer grid depending on the Reynolds number are presented. On the basis of the experimental data obtained, recommendations for improvement of the method of calculating the flow rate of a coolant in the cells of the fissile core of a KLT-40S reactor were developed. The results of investigations of the local hydrodynamic and mass-exchange characteristics of the coolant flow in the fuel assembly of the KLT-40S reactor plant were accepted for estimating the thermal and technical reliability of the fissile cores of KLT-40S reactors and were included in the database for verification of computational hydrodynamics programs (CFD codes).

Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

Energy Technology Data Exchange (ETDEWEB)

1976-05-01

Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

Nuclear reactors. Introduction

International Nuclear Information System (INIS)

Boiron, P.

1997-01-01

This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

Synaptonemal complex analysis of interracial hybrids between the Moscow and Neroosa chromosomal races of the common shrew Sorex araneus showing regular formation of a complex meiotic configuration (ring-of-four

Directory of Open Access Journals (Sweden)

Sergey Matveevsky

2012-09-01

Full Text Available Immunocytochemical and electron microscopic analysis of synaptonemal complexes (SCs was carried out for the first time in homozygotes and complex Robertsonian heterozygotes (hybrids of the common shrew, Sorex araneus Linnaeus, 1758, from a newly discovered hybrid zone between the Moscow and the Neroosa chromosomal races. These races differ in four monobrachial homologous metacentrics, and closed SC tetravalent is expected to be formed in meiosis of a hybrid. Indeed, such a multivalent was found at meiotic prophase I in hybrids. Interactions between multivalent and both autosomes and/or the sex chromosomes were observed. For the first time we have used immunocytochemical techniques to analyse asynapsis in S. araneus and show that the multivalent pairs in an orderly fashion with complete synapsis. Despite some signs of spermatocytes arrested in the meiotic prophase I, hybrids had large number of active sperm. Thus, Moscow – Neroosa hybrid males that form a ring-of-four meiotic configuration are most likely not sterile. Our results support previous demonstrations that monobrachial homology of metacentrics of the common shrew does not lead to complete reproductive isolation between parapatric chromosomal races of the species.

THE HISTORY OF THE CONSTRUCTION EDUCATION: THE FIRST GRADUATES OF MOSCOW CONSTRUCTION SCHOOLS

Directory of Open Access Journals (Sweden)

Panteleeva Tat'yana Leonidovna

2015-12-01

Full Text Available The authors refer to several vivid examples to consider various patterns of urban planning and management with account for the ecological factors. Yekaterinburg serves as the basis for the ecological and urban planning safety model, designed as a digital printout indicating ecologically unsafe urban areas. Dushanbe, Bishkek and the Orenburg region examples are analyzed to prove that urban ecology factors, that shape up the typological urban structure and determine specific planning solutions, represent an integral constituent of sustainable development models for specific areas. Moscow exemplifies the statement that the ongoing maintenance of proportions in the course of development of urban ecosystems is a binding condition of the ecological and urban planning balance in urban areas.

[Monitoring of the chemical composition of snow cover pollution in the Moscow region].

Science.gov (United States)

Ermakov, A A; Karpova, E A; Malysheva, A G; Mikhaylova, R I; Ryzhova, I N

2014-01-01

Monitoring of snow cover pollution as an indicator of ambient air pollution in 20 districts in the Moscow region during 2009-2013 was performed. The identification with a quantitative assessment of a wide array of organic compounds and the control of the main physical and chemical and inorganic indices of snow water pollution were carried out. More than 60 organic substances for most of which there are no the hygienic standards were established. The assessment of pollution levels of basic inorganic indices was given by means of the comparing them with the average values in the snow cover in the European territory of Russia and natural content in areas not been exposed to human impact.

Progress in the U.S. department of energy sponsored in-depth safety assessments of VVER and RBMK reactors

International Nuclear Information System (INIS)

Binder, J.L.; Petri, M.C.; Pasedag, W.F.

2001-01-01

Since the disastrous accident at Chernobyl Nuclear Power Plant Unit 4 in 1986, there has been international recognition of the safety concerns posed by the operation of 67 Soviet-designed commercial nuclear reactors. These reactors are operated in eight countries from the former Soviet Union and its former satellite states in Central and Eastern Europe. The majority of these plants are in the Russian Federation (30 units) and Ukraine (14 units). New plants are in various stages of construction. U.S. support to improve the safety of Soviet-designed reactors over the past decade has been intended to enhance operational safety, provide for risk-reduction measures, and enhance regulatory capability. The U.S. approach to improving the safety of Soviet-designed reactors has matured into a large multi-year program known as the Soviet-Designed Reactor Safety Program that is managed by the U.S. Department of Energy (US DOE). The mission of the program is to implement a self-sustaining nuclear safety improvement program that would lead to internationally accepted safety practices at the plants. Those practices would create a safety culture that would be reflected in the operation, regulation, and professional attitudes of the designers, operators, and regulators of the nuclear facilities. A key component of this larger program has been the Plant Safety Evaluation Program, which supports in-depth safety assessments of VVER and RBMK plants. (author)

Teaching of foundations of radiochemistry on chemical faculty of Moscow State University after M.V. Lomonosov. Methodical ensuring of the subject

International Nuclear Information System (INIS)

Luk'yanov, V.B.; Berdonosov, S.S.; Fedoseev, V.M.

1995-01-01

The peculiarities of the lecture course on radiochemistry principles in the Moscow State University after M.V. Lomonosov are considered. The methodical provision of the lectures including the curriculum, methodical aids, tasks for self-control and for lecture control, as well as, summary questionary forms, is discussed. 3 refs

Preliminary S-CO_2 Compressor Design for Micro Modular Reactor

International Nuclear Information System (INIS)

Lee, Jekyoung; Cho, Seong Kuk; Kim, Seong Gu; Lee, Jeong Ik

2016-01-01

Due to economic benefit of S-CO_2 Brayton cycle which is came from high efficiency and compactness, active research is currently conducted by various research groups and various approaches are suggested to take benefits of S-CO_2 Brayton cycle. KAIST research team also has been working on advanced concept for application of S-CO_2 Brayton cycle to nuclear system and Micro Modular Reactor (MMR) concept was suggested. The preliminary compressor design of S-CO_2 compressor for MMR system was carried out to observe feasibility of compressor design. Preliminary S-CO_2 compressor design for MMR system was successfully conducted and some issues are discovered from the design study. From the previous work done by Cho, conceptual design for MMR system was provided. Thus, further preliminary design should be carried out to obtain feasible S-CO_2 compressor design for MMR system. KAIST_TMD which is turbomachinery in-house code for real gases including S-CO_2 is continuously updated and currently it has 3D geometry construction and design optimization capability

Status and program of development of the fast breeder reactor system in the U.S

International Nuclear Information System (INIS)

Roberts, R.W.

1977-01-01

The U.S. Energy Research and Development Administration's highest priority breeder concept is the Liquid Metal Fast Breeder Reactor (LMFBR). Its objective is the development of a broad technological and engineering base with extensive utility and industrial involvement which will establish a timely capability for a competitive and commercial breeder industry. In addition to technological development, an integral part of the LMFBR program is the transfer of LMFBR technology to the nuclear industry and the parallel development of utility capability. An important indicator of the effectiveness of this program is the successful construction and operation of a number of LMFBR experimental and test reactors and associated non-nuclear test facilities such as those located at Santa Susana, California, the Argonne (III). National Laboratory and the Hanford Engineering Development Laboratory at Richland, Washington. A principal element of the U.S. fast breeder reactor program is the Fast Flux Test Facility (FFTF). The largest test reactor facility in the world, the FFTF will focus on the testing of fuels and material. The FFTF, being built at the Hanford Engineering Development Laboratory, is scheduled for completion in the late 1970's. The next step toward timely commercial breeder capability is to implement a program for a large-scale demonstration of this concept. A 380 megawatt electrical demonstration plant - designated the Clinch River Breeder Reactor Plant (CRBRP) - will be constructed and operated near Oak Ridge, Tennessee, under a cooperative arrangement of industrial contractors, utilities, and the Government. The completion date is 1983. The estimated cost of the CRBRP project is 1.95 billion dollars. This includes the cost of design, construction, related research and development, and five years of operation - the full timespan from the project's beginning in 1972 through completion. The Nation's principal electric utilities have strongly endorsed the

Selection of NPP for Kazakhstan

International Nuclear Information System (INIS)

Zhotabaev, Zh.R.

2003-01-01

Commercial NPP for Kazakhstan should to meet to several main requirements: 1). Safety operation (accident probability not more than 10 -6 1/p. year). 2). High efficiency > 40 %. 3). Possibility of use for high-temperature chemistry and hydrogen production. 4). Possibility for manufacturing of considerable part of equipment in Kazakhstan. 5). Possibility for fuel production and reprocessing in Kazakhstan. 6). Independence from existence of large water-supply sources. Comparative analysis of several NPP with different reactors (WWR-1000, Candu, BREST, VG-400; graphite molten salt reactor) shows that NPP with the graphite molten salt reactor meets to all above requirements, but hydrogen production it is possible by more complete 4-stage technology, since coolant temperature is 800 Deg. C. The principle advantage is possibility of manufacturing of main equipment and fuel in Kazakhstan that reduce the cost of NPP construction and operation

LEO TOLSTOY’S POPULAR THEATRE: THE BEGINNING OF THE WRITER’S EDUCATIONAL SERVICE

Directory of Open Access Journals (Sweden)

Irina I. Sizova

2016-12-01

Full Text Available This article examines the first phase of Leo Tolstoy’s educational service in the field of the popular theatre on the example of the stage history of his comedy The First Distiller (1886. I see my task in the reconstruction of the first stage version of this play prepared by V. G. Chertkov on the author’s request, with the use of archival information and data from the periodicals of 1886. For the first time, the essay argues that Chertkov was working in four different directions. He was negotiating with Moscow Buffonery Theatre, Vasileostrovskiy Workers’ Theater, St. Petersburg scenic platforms, and the Theatre of Popular Entertainment in the village of Alexandrovskoe near St. Petersburg. Chertkov covered the first performance of The First Distiller (Alexandrovskoe, July 6 and 20 1886 that had a big resonance. The essay explains (for the first time in Tolstoy criticism why other performances of this play had never taken place. Technical and financial difficulties prevented performances in Moscow Buffonery Theater and Vasileostrovskiy Theater. The symbolism of Tolstoy’s comedy (his images of devils and hell became an impediment for staging the play at other popular theaters that Chertkov reached with the help of the patron of art, I. M. Sibiryakov.

Spent nuclear fuel discharges from U.S. reactors 1994

International Nuclear Information System (INIS)

1996-02-01

Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year's report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs

Testing of methods for decontamination of stainless steels and carbon steels conformably to demountable equipment of nuclear power plant with WWR type reactor

International Nuclear Information System (INIS)

Dergunova, G.M.; Nazarov, V.K.; Ozolin, A.B.; Smirnov, L.M.; Stel'mashuk, V.P.; Yulikov, E.I.; Vlasov, I.N.

1978-01-01

Results are given of experiments on decontamination of stainless steel by the oxidation-reduction method and also results of decontamination of carbon steel by means of solutions based on oxalic acid, citric acid and phosphoric acid. Investigations of efficiency of oxidation-reduction treatment were done on samples of stainless steel cut from the pipeline of the primary coolant circuit of reactor. Comparison is given of efficiency of oxidation-reduction methods of contamination of stainless steel in the case of application of different compositions of decontaminating solutions. Dependences are given for decontamination completeness on duration of operations, on temperature and on ratio of volume of decontaminating solutions to surface are of the sample. For carbon steels parameters are given for decontamination process by means of oxalic, citric and phosphoric acid solutions. (I.T.) [ru

Back from the Nikitsky Gates Theater: Reflections on Cross-Cultural Concerns in the Staging of Marsha Norman's "'night, Mother" in Moscow.

Science.gov (United States)

Karter, M. Joshua

1994-01-01

Discusses some of the problems the author encountered in staging a production of Marsha Norman's "'night, Mother" in Moscow. States that the area of largest concern was cultural variables, and whether a Russian audience would be able to understand some of the references. Concludes that, despite cultural differences, the audience was…

U.S. technology for mechanized/automated fabrication of fast reactor fuel

International Nuclear Information System (INIS)

Nyman, D.H.; Bennett, D.W.; Claudson, T.T.; Dahl, R.E.; Graham, R.A.; Keating, J.J.; Yatabe, J.M.

1978-01-01

The status of the U.S. fast reactor Fuel Fabrication Development Program is discussed. The objectives of the program are to develop and evaluate a high throughput pilot fuel fabrication line including close-coupled chemistry and wet scrap recycle operations. The goals of the program are to demonstrate by mechanized/automated and remote processes: reduced personnel exposure, enhanced safegurads/accountability, improved fuel performance, representative fabrication rates and reduced fuel costs

The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1983-01-01

A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

Aging management of PWR reactor internals in U.S. plants

International Nuclear Information System (INIS)

Amberge, K.J.; Demma, A.

2015-01-01

This paper describes the development, aging management strategies and inspection results of the Pressurized Water Reactor (PWR) vessel internals inspection and evaluation guidelines. The goal of these guidelines is to provide PWR owners with robust aging management strategies to monitor degradation of internals components to support life extension as well as the current period of operation and power up-rate activities. The implementation of these guidelines began in 2010 within the U.S. PWR fleet and several examinations have been performed since. Examples of inspection results are presented for selected vessel internals components and are compared with simulation results. In summary, to date there have been no observations of austenitic stainless steel stress corrosion cracking (SCC), which is consistent with expectations based on the current understanding of the mechanism. Observations of irradiation assisted stress corrosion cracking (IASCC) have been limited and only found in baffle former bolting. Additionally, no macroscopic effects or global observations of void swelling impacts on general conditions of reactor internal hardware have been observed. (authors)

APPROACHES TO FORMING A TECHNOLOGICAL HUB IN LOMONOSOV MOSCOW STATE UNIVERSITY

Directory of Open Access Journals (Sweden)

V. KomarovM.

2016-01-01

Full Text Available LomonosovMoscowStateUniversityis a leading Russian institution of higher education, the only one included in the top 100 authoritative global ranking – ARWU (Shanghairanking. Since 2014 it is planned to implement a large-scale project of theTechnologyValleyinRussia, the research world-class center associated with the University. The paper analyzes the main approaches to the implementation of the project, based on the analysis of international experience. We formulated recommendations for its implementation. In the modern world, the competitiveness of the country is determined by its ability to create opportunities for human potential, to attract and retain the most talented people. TheTechnologyValleyproject inRussiashould be developed regarding to its local position advantages and theMoscowuniversity development goals should also be taken into account. The accelerated development of the project can become a successful anti-crisis strategy. 

U.S. Status of Fast Reactor Research and Technology

International Nuclear Information System (INIS)

Hill, Robert

2012-01-01

Summary: • Fast reactor R&D is focused on key technologies innovations for performance improvement (cost reduction) and safety: 1. System Integration and Concept Development; 2. Safety Technology; 3. Advanced Materials; 4. Ultrasonic Viewing; 5. Advanced Energy Conversion (Supercritical CO 2 Brayton cycle); 6. Reactor Simulation; 7. Nuclear Data; 8. Advanced Fuels. • Fast reactors have flexible capability for actinide management: – A wide variety of fuel cycle options are being considered; • International R&D collaboration pursued in Generation-IV and multilateral arrangements

Neutron diffraction radiation of solid solution of carbon and hydrogen in the α-titanium in the homogeneity domain

International Nuclear Information System (INIS)

Mirzaev, B.B.; Khidirov, I.; Mukhtarova, N.N.

2005-01-01

In the work by the neutron-graph the homogeneity domain of the introduction solid solution TiC x H y is determined. The sample neutron grams have been taken on the neutron diffractometer (λ=.1085 nm) installed at the thermal column of the WWR-SM reactor (INF AN RUz). For the phase analysis and estimation of solid solutions homogeneity the X-ray graph was used. X-ray grams were taken on the X-ray diffractometer DRON-3M with use of CuK α radiation (λ=0.015418 nm)

Reactor container

International Nuclear Information System (INIS)

Naruse, Yoshihiro.

1990-01-01

The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

DIRECT ENERGY CONVERSION (DEC) FISSION REACTORS - A U.S. NERI PROJECT

International Nuclear Information System (INIS)

Beller, D.; Polansky, G.

2000-01-01

The direct conversion of the electrical energy of charged fission fragments was examined early in the nuclear reactor era, and the first theoretical treatment appeared in the literature in 1957. Most of the experiments conducted during the next ten years to investigate fission fragment direct energy conversion (DEC) were for understanding the nature and control of the charged particles. These experiments verified fundamental physics and identified a number of specific problem areas, but also demonstrated a number of technical challenges that limited DEC performance. Because DEC was insufficient for practical applications, by the late 1960s most R and D ceased in the US. Sporadic interest in the concept appears in the literature until this day, but there have been no recent programs to develop the technology. This has changed with the Nuclear Energy Research Initiative that was funded by the U.S. Congress in 1999. Most of the previous concepts were based on a fission electric cell known as a triode, where a central cathode is coated with a thin layer of nuclear fuel. A fission fragment that leaves the cathode with high kinetic energy and a large positive charge is decelerated as it approaches the anode by a charge differential of several million volts, it then deposits its charge in the anode after its kinetic energy is exhausted. Large numbers of low energy electrons leave the cathode with each fission fragment; they are suppressed by negatively biased on grid wires or by magnetic fields. Other concepts include magnetic collimators and quasi-direct magnetohydrodynamic generation (steady flow or pulsed). We present the basic principles of DEC fission reactors, review the previous research, discuss problem areas in detail and identify technological developments of the last 30 years relevant to overcoming these obstacles. A prognosis for future development of direct energy conversion fission reactors will be presented

Advanced boiling water reactors for the 90's and beyond

International Nuclear Information System (INIS)

Rao, A.S.; Sawyer, C.D.; Qurik, J.F.; McCandless, R.J.

1990-01-01

This paper discusses how the advanced boiling water reactor (ABWR) is being developed by an international team of BWR manufacturers to respond to worldwide utility needs in the 1990s. Major objectives of the ABWR program are design simplification; improved safety and reliability; reduced construction, fuel and operating costs; improved maneuverability and reduced occupational exposure and radwaste. International cooperative efforts are also under way aimed at development of a simplified BWR employing natural circulation and passive safety systems. The SBWR conceptual design is complete. This BWR concept shows technical and economic promise. The SBWR program is aimed at providing a U.S. NRC certified design in an investor-ready state by 1995. With its short construction schedule, the 600 MWe SBWR will provide an option for commercial operation worldwide by the mid-to-late 1990s

Integral Inherently Safe Light Water Reactor (I²S-LWR)

Energy Technology Data Exchange (ETDEWEB)

Petrovic, Bojan [Georgia Inst. of Technology, Atlanta, GA (United States); Memmott, Matthew [Brigham Young Univ., Provo, UT (United States); Boy, Guy [Florida Inst. of Technology, Melbourne, FL (United States); Charit, Indrajit [Univ. of Idaho, Moscow, ID (United States); Manera, Annalisa [Univ. of Michigan, Ann Arbor, MI (United States); Downar, Thomas [Univ. of Michigan, Ann Arbor, MI (United States); Lee, John [Univ. of Michigan, Ann Arbor, MI (United States); Muldrow, Lycurgus [Morehouse College, Atlanta, GA (United States); Upadhyaya, Belle [Univ. of Tennessee, Knoxville, TN (United States); Hines, Wesley [Univ. of Tennessee, Knoxville, TN (United States); Haghighat, Alierza [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)

2017-10-02

This final report summarizes results of the multi-year effort performed during the period 2/2013- 12/2016 under the DOE NEUP IRP Project “Integral Inherently Safe Light Water Reactors (I²S-LWR)”. The goal of the project was to develop a concept of a 1 GWe PWR with integral configuration and inherent safety features, at the same time accounting for lessons learned from the Fukushima accident, and keeping in mind the economic viability of the new concept. Essentially (see Figure 1-1) the project aimed to implement attractive safety features, typically found only in SMRs, to a larger power (1 GWe) reactor, to address the preference of some utilities in the US power market for unit power level on the order of 1 GWe.

Engineering progress of CNS concept in Hanaro

International Nuclear Information System (INIS)

Choi, C.O.; Park, K.N.; Park, S.H.

1997-01-01

The Korea Atomic Energy research Institute (KAERI) strives to provide utilizing facilities on and around the Hanaro reactor in order to activate advanced researches by neutron application. As one of the facilities to be installed, the conceptual design work of CNS was started in 1996 with a project schedule of 5 years so that its installation work can be finished by the year 2000. And the major engineering targets of this CNS facility are established for a minimum physical interference with the present facilities of the Hanaro, a reach-out of very-high-gain factors in the cold neutron flux, a simplicity of the maintenance of the facility, and a safety in the operation of the facility as well as the reactor. For the conceptual design of Hanaro CNS, the experience of utilization and production of cold neutron at WWR-M reactor Gatchina, Russia has been used with that of elaborations for PIK reactor in design for neutron guide systems and instruments. (author)

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

Trends in Life Expectancy of Cystic Fibrosis Patients in Moscow and their Connection with the Treatment Received: Retrospective Analysis for 1993–2013

Directory of Open Access Journals (Sweden)

N. Yu. Kashirskaya

2015-01-01

Full Text Available Cystic fibrosis is multiple organ pathology that requires a complex treatment. Its standardization and pharmacoeconomic analysis are absolutely necessary. We performed a retrospective analysis of the trends in life expectancy of cystic fibrosis patients who lived inMoscow in 1993, 1998, 2003, 2008, and 2013. It was found that the survival rate of these patients depended on the choice of drug therapy (pancreatic enzymes, dornase alfa, intravenous and inhaled antipseudomonal antibiotics, changes in diet, active dispensary observation at a specialized center for cystic fibrosis, and neonatal screening. We determined the cost of drug therapy per patient. From 1993 to 2013, the survival rate of patients who lived in Moscow increased by more than 20 years (from 16 to 39 years, respectively. The average cost of therapy increased more than 10 times (from USD 1.8 to 21.9 thousand, respectively.

Russian atomic energy reaches critical masses

International Nuclear Information System (INIS)

Ustinov, A.

1996-01-01

With more than 200 malfunctions recorded in the early 1990's the outmoded nuclear reactors in the former Soviet Union are in critical condition. Unfortunatly, there may not be enough money to monitor them, much less update them, says Artiom Ustinov, an expert in the Russian Ministry of Foreign Affairs in Moscow. In on short decade, Russia's nuclear research budget has been slashed from $1.5 billion to $250 million. That amount of money simply cannot be stretched far enough to address safety issues, Ustinov says. open-quotes Currently, nuclear reactors in the former Soviet Union pose a greater environmental threat than ever before,close quotes ustinov says. open-quotes In fact, almost half the nuclear power plants operating in Russia today are Chernobyl-like.close quotes and most of these facilities are located in such large industrial centers as Moscow and st. Petersburg, Ustinov says. The future of nuclear power in the Soviet Union remains cloudy, Ustinov concludes. open-quotes It is likely that the legacy of its development will continue to generate electricity-and controversy-in the years ahead.close quotes

The American Hospital in Moscow: A Lesson in International Cooperation, 1917-23.

Science.gov (United States)

Grant, Susan

2015-10-01

In its examination of American Medical Aid to Russia, this article shows how the best of intentions can have the potential to go horribly awry. It argues that the competing binary forces of international collaboration and goodwill versus political tensions and uncertainty combined to create an environment wherein actors and agents inhabited an ever changing and unpredictable international stage. Could American philanthropic organisations and individuals overcome political volatility, financial restrictions and ideological barriers? Just what would it take to establish an American hospital in Moscow, the Bolshevik seat of power? The attempt to establish the hospital proved to be an exercise in patience, persistence and prudence (although not always in equal measure). This article shows that international cooperation, while undoubtedly complicated, was certainly possible. The flow of information, materiel and personnel between the United States, Germany and Russia proved that good intentions, trust and a will to help others were valued. The history of American Medical Aid to Russia also demonstrates that the Quaker role of facilitator and interlocutor was vital in establishing a relationship of trust between Soviet Russia and the United States. This article discusses the difficulties that philanthropic organisations faced when navigating the choppy international waters of the early 1920s and highlights the rewards of successfully doing this. It argues that basic human relationships and trust were just as, if not sometimes more, important than ideology in determining the tenor of early US-Soviet relations.

Successive and large-scale synthesis of InP/ZnS quantum dots in a hybrid reactor and their application to white LEDs

Science.gov (United States)

Kim, Kyungnam; Jeong, Sohee; Woo, Ju Yeon; Han, Chang-Soo

2012-02-01

We report successive and large-scale synthesis of InP/ZnS core/shell nanocrystal quantum dots (QDs) using a customized hybrid flow reactor, which is based on serial combination of a batch-type mixer and a flow-type furnace. InP cores and InP/ZnS core/shell QDs were successively synthesized in the hybrid reactor in a simple one-step process. In this reactor, the flow rate of the solutions was typically 1 ml min-1, 100 times larger than that of conventional microfluidic reactors. In order to synthesize high-quality InP/ZnS QDs, we controlled both the flow rate and the crystal growth temperature. Finally, we obtained high-quality InP/ZnS QDs in colors from bluish green to red, and we demonstrated that these core/shell QDs could be incorporated into white-light-emitting diode (LED) devices to improve color rendering performance.

Application of S-CO_2 Cycle for Small Modular Reactor coupled with Desalination System

International Nuclear Information System (INIS)

Lee, Won Woong; Bae, Seong Jun; Lee, Jeong Ik

2016-01-01

The Korean small modular reactor, SMART (System-integrated Modular Advanced ReacTor, 100MWe), is designed to achieve enhanced safety and improved economics through reliable passive safety systems, a system simplification and component modularization. SMART can generate electricity and provide water by seawater desalination. However, due to the desalination aspect of SMART, the total amount of net electricity generation is decreased from 100MWe to 90MWe. The authors suggest in this presentation that the reduction of electricity generation can be replenished by applying S-CO_2 power cycle technology. The S-CO_2 Brayton cycle, which is recently receiving significant attention as the next generation power conversion system, has some benefits such as high cycle efficiency, simple configuration, compactness and so on. In this study, the cycle performance analysis of the S-CO_2 cycles for SMART with desalination system is conducted. The simple recuperated S-CO_2 cycle is revised for coupling with desalination system. The three revised layout are proposed for the cycle performance comparison. In this results of the 3rd revised layout, the cycle efficiency reached 37.8%, which is higher than the efficiency of current SMART with the conventional power conversion system 30%

Recent progress in stellarator reactor conceptual design

International Nuclear Information System (INIS)

Miller, R.L.

1985-01-01

The Stellarator/Torsatron/Heliotron (S/T/H) class of toroidal magnetic fusion reactor designs continues to offer a distinct and in several ways superior approach to eventual commercial competitiveness. Although no major, integrated conceptual reactor design activity is presently underway, a number of international research efforts suggest avenues for the substantial improvement of the S/T/H reactor embodiment, which derive from recent experimental and theoretical progress and are responsive to current trends in fusion-reactor projection to set the stage for a third generation of designs. Recent S/T/H reactor design activity is reviewed and the impact of the changing technical and programmatic context on the direction of future S/T/H reactor design studies is outlined

Work Breakdown Structure and Work Packages for Decommissioning the Nuclear Research Reactor VVR-S Magurele-Bucharest

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-06-15

The research reactor type VVR-S (tank type, water cooled, moderator and reflector, thermal power 2 MW, thermal energy 9.52 GWd) was put into service in July 1957, and in December 1997, was shut down. In 2002, the Romanian Government decided to put the research reactor into a permanent shutdown condition in order to start decommissioning. This nuclear facility had been used in nuclear research and radioisotope production for 40 years without any events, incidents or accidents. At the same site, in the immediate vicinity of the research reactor, there are many other nuclear facilities: a radioactive waste treatment plant, a tandem Van de Graaff heavy ion accelerator, a cyclotron, an industrial irradiator and a radioisotope production centre.

Construction of high-rise building with underground parking in Moscow

Directory of Open Access Journals (Sweden)

Ilyichev Vyacheslav

2018-01-01

Full Text Available Paper presents results of scientific support to construction of unique residential building 108 m high with one storey underground part under high-rise section and 3-storey underground parking connected by underground passage. On-site soils included anthropogenic soil, clayey soils soft-stiff, saturated sands of varied grain coarseness. Design of retaining structure and support system for high-rise part excavation was developed. It suggested installation of steel pipes and struts. Construction of adjacent 3-storey underground parking by “Moscow method” is described in the paper. This method involves implementation of retaining wall consisted of prefabricated panels, truss structures (used as struts and reinforced concrete slabs. Also design and construction technology is provided for foundations consisted of bored piles 800 MM in diameter joined by slab with base widening diameter of 1500 MM. Experiment results of static and dynamic load testing (ELDY method are considered. Geotechnical monitoring data of adjacent building and utility systems settlement caused by construction of presented high-rise building were compared to numerical modelling results, predicted and permissible values.

Construction of high-rise building with underground parking in Moscow

Science.gov (United States)

Ilyichev, Vyacheslav; Nikiforova, Nadezhda; Konnov, Artem

2018-03-01

Paper presents results of scientific support to construction of unique residential building 108 m high with one storey underground part under high-rise section and 3-storey underground parking connected by underground passage. On-site soils included anthropogenic soil, clayey soils soft-stiff, saturated sands of varied grain coarseness. Design of retaining structure and support system for high-rise part excavation was developed. It suggested installation of steel pipes and struts. Construction of adjacent 3-storey underground parking by "Moscow method" is described in the paper. This method involves implementation of retaining wall consisted of prefabricated panels, truss structures (used as struts) and reinforced concrete slabs. Also design and construction technology is provided for foundations consisted of bored piles 800 MM in diameter joined by slab with base widening diameter of 1500 MM. Experiment results of static and dynamic load testing (ELDY method) are considered. Geotechnical monitoring data of adjacent building and utility systems settlement caused by construction of presented high-rise building were compared to numerical modelling results, predicted and permissible values.

Application of LiF for determining the gamma-radiation characteristics of the shut-down reactor

Energy Technology Data Exchange (ETDEWEB)

Ibragimova, E M; Musaeva, M A; Ashrapov, U T; Kalanov, M U; Muminov, M I [Inst. of Nuclear Physics, Tashkent (Uzbekistan)

2005-07-01

Full text: The power of {sup 60}Co {approx}1.25 MeV gamma-radiation source at the INP AS RUz is limited by 8 Gy/s, which does not satisfy several tasks of material science now. Therefore, we were first to suggest the irradiation of materials with gamma-rays of 0.1-7 MeV, which are emitted by the uranium fission products ({sup 41}Ar, {sup 135}Xe, {sup 125}Xe, {sup 125}I,{sup 137}Cs, {sup 134}Cs, {sup 144}Ce, {sup 95}Zr, {sup 140}Ba, {sup 140}La, {sup 99}Mo, {sup 60}Co) and {sup l6}N, {sup 24}Na, {sup 28}Al radio-nuclides in water during prophylactic shut-downs of our nuclear reactor WWR-SM. The gamma-dose rate kinetics was monitored with the ion current in ionization chambers KNK-53M fixed outside the reactor core from the stop-moment. The current kinetics comprised 4 steps with a high reproducibility at 2 and 0.5 {mu}A, then 50 and 10 nA, each lasting for 1,10, 40 and up to 200 hours, according to the isotope life-times. LiF crystal is known as a thermal luminescence dosimeter of mixed radiations up to 100 Gy. Yet in this work the absorbed gamma-energy dose D{sub {gamma}} was determined by accumulation of the known stable structure defects in thin cleaved LiF crystals: by induced optical absorption and luminescence of F- and M-centers. The samples were irradiated in Al-containers filled with water to keep the temperature of {approx}40 deg. C in the time range from 30 minutes to 150 hours. Optical absorption spectra were registered at spectrometer Specord M-40. Then the induced color center concentration was calculated by the Smakula relation, which is proportional to the absorbed dose D{gamma}. For a better reliability the photoluminescence center content was also determined. Selecting comparable close intensities of the induced absorption and luminescence bands obtained after irradiations of LiF references in the certified {sup 60}Co gamma-sources of the known gamma fluxes 0.7 and 7.5 Gy/s, the gamma-radiation intensity of the shut-down reactor was estimated in

Application of LiF for determining the gamma-radiation characteristics of the shut-down reactor

International Nuclear Information System (INIS)

Ibragimova, E.M.; Musaeva, M.A.; Ashrapov, U.T.; Kalanov, M.U.; Muminov, M.I.

2005-01-01

Full text: The power of 60 Co ∼1.25 MeV gamma-radiation source at the INP AS RUz is limited by 8 Gy/s, which does not satisfy several tasks of material science now. Therefore, we were first to suggest the irradiation of materials with gamma-rays of 0.1-7 MeV, which are emitted by the uranium fission products ( 41 Ar, 135 Xe, 125 Xe, 125 I, 137 Cs, 134 Cs, 144 Ce, 95 Zr, 140 Ba, 140 La, 99 Mo, 60 Co) and l6 N, 24 Na, 28 Al radio-nuclides in water during prophylactic shut-downs of our nuclear reactor WWR-SM. The gamma-dose rate kinetics was monitored with the ion current in ionization chambers KNK-53M fixed outside the reactor core from the stop-moment. The current kinetics comprised 4 steps with a high reproducibility at 2 and 0.5 μA, then 50 and 10 nA, each lasting for 1,10, 40 and up to 200 hours, according to the isotope life-times. LiF crystal is known as a thermal luminescence dosimeter of mixed radiations up to 100 Gy. Yet in this work the absorbed gamma-energy dose D γ was determined by accumulation of the known stable structure defects in thin cleaved LiF crystals: by induced optical absorption and luminescence of F- and M-centers. The samples were irradiated in Al-containers filled with water to keep the temperature of ∼40 deg. C in the time range from 30 minutes to 150 hours. Optical absorption spectra were registered at spectrometer Specord M-40. Then the induced color center concentration was calculated by the Smakula relation, which is proportional to the absorbed dose Dγ. For a better reliability the photoluminescence center content was also determined. Selecting comparable close intensities of the induced absorption and luminescence bands obtained after irradiations of LiF references in the certified 60 Co gamma-sources of the known gamma fluxes 0.7 and 7.5 Gy/s, the gamma-radiation intensity of the shut-down reactor was estimated in correlation with the ion current as 10 nA = 15 Gy/s. At short times of irradiation the linear dose dependence

Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

International Nuclear Information System (INIS)

1975-06-01

The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

Benzo[a]pyrene in urban environments of eastern Moscow: pollution levels and critical loads

Science.gov (United States)

Kasimov, Nikolay S.; Kosheleva, Natalia E.; Nikiforova, Elena M.; Vlasov, Dmitry V.

2017-02-01

Polycyclic aromatic hydrocarbons (PAHs), particularly benzo[a]pyrene (BaP), are toxic compounds emitted from various anthropogenic sources. Understanding the BaP concentrations, dynamics and decomposition in soil is required to assess the critical loads of BaP in urban environments. This study is the first attempt to evaluate all major input and output components of benzo[a]pyrene (BaP) balance and to calculate the permissible load on the urban environment in different land-use zones in the Eastern district of Moscow. BaP contamination of the snow cover in the Eastern district of Moscow was related to daily BaP fallout from the atmosphere. In 2010, the mean content of the pollutant in the snow dust was 1942 ng g-1, whereas the average intensity of its fallout was 7.13 ng m-2 per day. Across the territory, BaP winter fallout intensities varied from 0.3 to 1100 ng m-2 per day. The average BaP content in the surface (0-10 cm) soil horizons was 409 ng g-1, which is 83 times higher than the local background value and 20 times higher than the maximum permissible concentration (MPC) accepted in Russia. The variations in soil and snow BaP concentrations among different land-use zones were examined. A significant contribution of BaP from the atmosphere to urban soils was identified. Based on the measurements of BaP atmospheric fallout and BaP reserves in the soils, the critical loads of BaP for the land-use zones in the Eastern district were calculated for different values of degradation intensity and different exposure times. It was established that at an annual degradation intensity of 1-10 %, ecologically safe BaP levels in the soils of all land-use zones, excluding the agricultural zone, will only be reached after many decades or centuries.

Update on reactors and reactor instruments in Asia

Science.gov (United States)

Rao, K. R.

1991-10-01

The 1980s have seen the commissioning of several medium flux (∼10 14 neutrons/cm 2s) research reactors in Asia. The reactors are based on indigenous design and development in India and China. At Dhruva reactor (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high- Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand.

Update on reactors and reactor instruments in Asia

International Nuclear Information System (INIS)

Rao, K.R.

1991-01-01

The 1980s have seen the commissioning of several medium flux (∝10 14 neutrons/cm 2 s) research reactors in Asia. The reactors are based on indigenous design and development in India and China. At Dhruva reactor (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high-Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand. (orig.)

Internet accessible hot cell with gamma spectroscopy at the Missouri S and T nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Grant, Edwin [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States); Mueller, Gary, E-mail: gmueller@mst.edu [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States); Castano, Carlos; Usman, Shoaib; Kumar, Arvind [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States)

2011-08-15

Highlights: > A dual-chambered internet-accessible heavily shielded facility has been built. > The facility allows distance users to analyze neutron irradiated samples remotely. > The Missouri S and T system uses computer automation with user feedback. > The system can analyze multiple samples and assist several researchers concurrently. - Abstract: A dual-chambered internet-accessible heavily shielded facility with pneumatic access to the University of Missouri Science and Technology (Missouri S and T) 200 kW Research Nuclear Reactor (MSTR) core has been built and is currently available for irradiation and analysis of samples. The facility allows authorized distance users engaged in collaborative activities with Missouri S and T to remotely manipulate and analyze neutron irradiated samples. The system consists of two shielded compartments, one for multiple sample storage, and the other dedicated exclusively for radiation measurements and spectroscopy. The second chamber has multiple detector ports, with graded shielding, and has the capability to support gamma spectroscopy using radiation detectors such as an HPGe detector. Both these chambers are connected though a rapid pneumatic system with access to the MSTR nuclear reactor core. This new internet-based system complements the MSTR's current bare pneumatic tube (BPT) and cadmium lined pneumatic tube (CPT) facilities. The total transportation time between the core and the hot cell, for samples weighing 10 g, irradiated in the MSTR core, is roughly 3.0 s. This work was funded by the DOE grant number DE-FG07-07ID14852 and expands the capabilities of teaching and research at the MSTR. It allows individuals who do not have on-site access to a nuclear reactor facility to remotely participate in research and educational activities.

Archeological Phase I Survey for the Columbia Falls and Moscow OTHB-E Radar Stations, Washington and Somerset Counties, Maine

Science.gov (United States)

2004-11-01

depression (kettles) on the landscape. Some kettles fill with water and become small ponds and lakes. The landscape in the north and eastern half of Sector... depression with employment opportunities elsewhere as a result of the Work Progress Administration (WPA). Many local inhabitants, including Passamaquoddy and... cranberry production (see Plate 1). The Passamaquoddy and Micmac tribes also lease land from the ACC 11 COLUMBIA FALLS AND MOSCOW OTHB-E RADAR STATIONS

Outcomes 18 years after implementation of a nonoperative caries preventive program - the Nexö-method - on children in Moscow, Russia

DEFF Research Database (Denmark)

Kuzmina, Irina; Ekstrand, Kim R

2015-01-01

OBJECTIVES: To report the long-term effect (18 years) of the Nexö-method, initially implemented in groups of children in Moscow in 1994. METHODS: Three groups of children were included in the initial study in 1994. This study is a follow-up study of two of the three initial groups: a group of 6-y...

Successive and large-scale synthesis of InP/ZnS quantum dots in a hybrid reactor and their application to white LEDs

International Nuclear Information System (INIS)

Kim, Kyungnam; Jeong, Sohee; Woo, Ju Yeon; Han, Chang-Soo

2012-01-01

We report successive and large-scale synthesis of InP/ZnS core/shell nanocrystal quantum dots (QDs) using a customized hybrid flow reactor, which is based on serial combination of a batch-type mixer and a flow-type furnace. InP cores and InP/ZnS core/shell QDs were successively synthesized in the hybrid reactor in a simple one-step process. In this reactor, the flow rate of the solutions was typically 1 ml min −1 , 100 times larger than that of conventional microfluidic reactors. In order to synthesize high-quality InP/ZnS QDs, we controlled both the flow rate and the crystal growth temperature. Finally, we obtained high-quality InP/ZnS QDs in colors from bluish green to red, and we demonstrated that these core/shell QDs could be incorporated into white-light-emitting diode (LED) devices to improve color rendering performance. (paper)

U.S. NRC training for research and training reactor inspectors

International Nuclear Information System (INIS)

Sandquist, G.M.; Kunze, J.F.

2011-01-01

Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

Stylized whole-core benchmark of the Integral Inherently Safe Light Water Reactor (I2S-LWR) concept

International Nuclear Information System (INIS)

Hon, Ryan; Kooreman, Gabriel; Rahnema, Farzad; Petrovic, Bojan

2017-01-01

Highlights: • A stylized benchmark specification of the I2S-LWR core. • A library of cross sections were generated in both 8 and 47 groups. • Monte Carlo solutions generated for the 8 group library using MCNP5. • Cross sections and pin fission densities provided in journal’s repository. - Abstract: The Integral, Inherently Safe Light Water Reactor (I 2 S-LWR) is a pressurized water reactor (PWR) concept under development by a multi-institutional team led by Georgia Tech. The core is similar in size to small 2-loop PWRs while having the power level of current large reactors (∼1000 MWe) but using uranium silicide fuel and advanced stainless steel cladding. A stylized benchmark specification of the I 2 S-LWR core has been developed in order to test whole-core neutronics codes and methods. For simplification the core was split into 57 distinct material regions for cross section generation. Cross sections were generated using the lattice physics code HELIOS version 1.10 in both 8 and 47 groups. Monte Carlo solutions, including eigenvalue and pin fission densities, were generated for the 8 group library using MCNP5. Due to space limitations in this paper, the full cross section library and normalized pin fission density results are provided in the journal’s electronic repository.

Western Siberia leads slide in former U.S.S.R.'s oil production

International Nuclear Information System (INIS)

Anon.

1992-01-01

The huge western Siberian basin, which Moscow had counted on to ensure rising Soviet petroleum production into the next century, is in steady leading the sharp decline in the former U.S.S.R.'s total oil flow. New data indicate that western Siberia's 1991 crude and condensate production fell to less than 6.5 million b/d. That's down from nearly 7.5 million b/d in 1990 and a peak of 8.28 million b/d in 1988. This paper reports that such low production would make it difficult for Russia to meet the oil needs of other members of the new Commonwealth of Independent States, let alone earn substantial amounts of desperately needed hard currency from crude and refined products sales to foreign countries

Fourth Generation Reactor Concepts

International Nuclear Information System (INIS)

Furtek, A.

2008-01-01

Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

Reactor building

International Nuclear Information System (INIS)

Ebata, Sakae.

1990-01-01

At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

Russian Political, Economic, and Security Issues and U.S. Interests

Science.gov (United States)

2007-01-18

polonium 210 from Moscow, through Germany, to London, apparently carried by one of the Russians Litvinenko met November 1. Russian authorities deny...Russia’s needs — food and food processing, oil and gas extraction technology, computers, communications, transportation, and investment capital — are

Participation in the U.S. Department of Energy Reactor Sharing Program

International Nuclear Information System (INIS)

Mulder, R. U.; Benneche, P. E.; Hosticka, B.

1998-01-01

The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these users institutions is enhanced by the use of the nuclear facilities

Reactor feedwater system

International Nuclear Information System (INIS)

Hikabe, Katsumi.

1978-01-01

Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

The Role of Identity, Ethnic Stereotypesand Acculturation Strategies in the Adaptation of Migrantsfrom Central Asia in the Moscow Region

Directory of Open Access Journals (Sweden)

Galyapina V.N.,

2017-12-01

Full Text Available The paper focuses on the study of the of impact ethnic, religious, civil and Russian identities, ethnic stereotypes on the strategies of acculturation and on the adaptation of migrants from Central Asia in the Moscow region. Representatives of two ethnic groupsparticipated in the research: 105 Uzbeks and 96 Tajiks (N= 201. The methods of the study included the scales of acculturation strategies, ethnic and national identities from the MIRIPS (Mutual Intercultural Relations in Plural Societies project questionnaire. The results of path analysis in AMOS program showed that integration and assimilation are the most successful strategies for migrants from Central Asia: integration contributed to self-esteem, while assimilation promoted life satisfaction. Integration is basically determined by ethnic and Russian identities, whereas assimilation is determined mostly by identification with the country of origin and by Russian identity as well as by the negative impact of ethnic identity. Separation and marginalization do not contribute to self-esteem of the migrants; however, positive heterostereotype of the Russians and Russian national identity prevent the migrants from choosing separation and marginalization. The choice of strategy is largely affected by religious identity. Expressed religious identity has a negative impact on the socio-cultural adaptation of the migrants from Central Asia in the Moscow region.

Reactor Coolant Pump seal issues and their applicability to new reactor designs

International Nuclear Information System (INIS)

Ruger, C.J.; Higgins, J.C.

1993-01-01

Reactor Coolant Pumps (RCPs) of various types are used to circulate the primary coolant through the reactor in most reactor designs. RCPs generally contain mechanical seals to limit the leakage of pressurized reactor coolant along the pump drive shaft into the containment. The relatively large number of RCP seal and seal auxiliary system failures experienced at US operating plants during the 1970's and early 1980's raised concerns from the US Nuclear Regulatory Commission (NRC) that gross failures may lead to reactor core uncovery and subsequent core damage. Some seal failure events resulted in a loss of primary coolant to the containment at flow rates greater than the normal makeup capacity of Pressurized Water Reactor (PWR) plants. This is an example of RCP seal failures resulting in a small Loss of Coolant Accident (LOCA). This paper discusses observed and potential causes of RCP seal failure and the recommendations for limiting the likelihood of a seal induced small LOCA. Issues arising out of the research supporting these recommendations and subsequent public comments by the utility industry on them, serve as lessons learned, which are applicable to the design of new reactor plants

Prevalence of Helicobacter pylori among medical workers in Moscow and Kazan according to ¹³С-urease breath test

Directory of Open Access Journals (Sweden)

D. S. Bordin

2018-01-01

Full Text Available Rationale: The relevance of the problem is related to the lack of data on Helicobacter pylori (HP prevalence in Russia, which is associated with the risk of peptic ulcer and gastric cancer, and also, on the other hand, to the non-adherence of the doctors to the existing expert guidelines on diagnosis of this infection and HP eradication therapy.Aim: To assess the prevalence of HP among medical workers and their willingness to undergo eradication therapy.Materials and methods: A total of 315 medical workers (61 men and 254 women aged 18 to 76 years were examined, among them 221 in Moscow and 94 in Kazan. To assess the HP contamination rate, all participants performed a ¹³С-urease breath test with the “HELICARB” test kit according to the “four-point” technique. All participants were asked to complete the questionnaires to access the impact of social and occupational factors on the prevalence of HP.Results: HP was identified in 54.9% of the examined subjects, including 45.9% of men and 57.1% of women. The prevalence of HP in Moscow was substantially lower (49.8% than in Kazan (67%. The proportion of HP-positive subjects increased with age from 41.8% in those below 25 years of age to 76.9% in those above their 60s. 60.2% of married participants and 49% of the singles were HP-positive. Among doctors, HP prevalence rate was the largest in the endoscopy specialists (61.5% and internists (60.9%. Only 61.4% of HP-positive medical workers expressed their willingness to undergo eradication therapy.Conclusion: The study showed a high prevalence of HР in medical workers increasing with age. It is presumably related to hygiene habits and conditions during childhood of each generation; however, one cannot exclude their potential contamination during their occupational activities.

Platinum-Group Elements in Soils and Street Dust of the Southeastern Administrative District of Moscow

Science.gov (United States)

Ladonin, D. V.

2018-03-01

The contents of five platinum-group metals (Ru, Rh, Pd, Ir, and Pt) in soils and street dust of the Southeastern administrative district (SEAD) of Moscow have been determined. The contents of these elements in soils may considerably exceed their natural abundances in the lithosphere and are characterized by considerable variability and asymmetric frequency distribution. A close correlation between Rh, Pd, and Pt contents in soils and street dust has been shown. The data on the contents of the elements and the ratios between them suggest that motor vehicles are the major source of pollution of soils and street dust in the studied district.

Reactor building

International Nuclear Information System (INIS)

Maruyama, Toru; Murata, Ritsuko.

1996-01-01

In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

Development and applications of reactor noise analysis at Ontario Hydro`s CANDU reactors

Energy Technology Data Exchange (ETDEWEB)

Gloeckler, O [Ontario Hydro, Toronto, ON (Canada); Tulett, M V [Ontario Hydro, Pickering, ON (Canada). Pickering Generating Station

1996-12-31

In 1992 a program was initiated to establish reactor noise analysis as a practical tool for plant performance monitoring and system diagnostics in Ontario Hydro`s CANDU reactors. Since then, various CANDU-specific noise analysis applications have been developed and validated. The noise-based statistical techniques are being successfully applied as powerful troubleshooting and diagnostic tools to a wide variety of actual operational I and C problems. The dynamic characteristics of critical plant components, instrumentation and processes are monitored on a regular basis. Recent applications of noise analysis include (1) validating the dynamics of in-core flux detectors (ICFDS) and ion chambers, (2) estimating the prompt fraction ICFDs in noise measurements at full power and in power rundown tests, (3) identifying the cause of excessive signal fluctuations in certain flux detectors, (4) validating the dynamic coupling between liquid zone control signals, (5) detecting and monitoring mechanical vibrations of detector tubes induced by moderator flow, (6) estimating the dynamics and response time of RTD (Resistance Temperature Detector) temperature signals, (7) isolating the cause of RTD signal anomalies, (8) investigating the source of abnormal flow signal behaviour, (9) estimating the overall response time of flow and pressure signals, (10) detecting coolant boiling in fully instrumented fuel channels, (11) monitoring moderator circulation via temperature noise, and (12) predicting the performance of shut-off rods. Some of these applications are performed on an as-needed basis. The noise analysis program, in the Pickering-B station alone, has saved Ontario Hydro millions of dollars during its first three years. The results of the noise analysis program have been also reviewed by the regulator (Atomic Energy Control Board of Canada) with favorable results. The AECB have expressed interest in Ontario Hydro further exploiting the use of noise analysis technology. (author

Long-Term Variability of UV Irradiance in the Moscow Region according to Measurement and Modeling Data

Science.gov (United States)

Chubarova, N. E.; Pastukhova, A. S.; Galin, V. Ya.; Smyshlyaev, S. P.

2018-03-01

We have found distinct long-period changes in erythemal UV radiation ( Q er) characterized by a pronounced decrease at the end of the 1970s and a statistically significant positive trend of more than 5%/10 years since 1979 over the territory of the Moscow region according to the measurements and reconstruction model. The positive Q er trend is shown to be associated mainly with a decrease in the effective cloud amount and total ozone content (TOC). Due to these variations, UV resources have significantly changed in spring for the population with the most vulnerable skin type I, which means a transition from the UV optimum to UV moderate excess conditions. The simulation experiments using the INM-RSHU chemistry climate model (CCM) for several scenarios with and without anthropogenic factors have revealed that the variations in the anthropogenic emissions of halogens have the most significant impact on the variability of TOC and Q er. Among natural factors, noticeable effects are observed due to volcanic aerosol. The calculations of the cloud transmittance of Q er are generally consistent with the measurements; however, they do not reproduce the observed value of the positive trend.

Overview of U.S. Fast Reactor Technology Program

International Nuclear Information System (INIS)

Hill, Robert

2013-01-01

• Concept development studies guide R&D tasks by evaluating system impact for broad variety of technology options: – Small-scale facilities for R&D on key technology; – No near-term plan for demonstration reactor. • Fast reactor R&D is focused on key technologies innovations for performance improvement (cost reduction): – Advanced Structural Materials; – Advanced Energy Conversion; – Advanced Modeling and Simulation. • Other R&D is conducted to address known technology challenges: – Safety and Licensing; – Fuels Development; – Undersodium Viewing

Experience in using a research reactor for the training of power reactor operators

International Nuclear Information System (INIS)

Blotcky, A.J.; Arsenaut, L.J.

1972-01-01

A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

Seven years of operation of the U. S. geological survey TRIGA reactor

International Nuclear Information System (INIS)

Kraker, Pat

1976-01-01

February 1976 marks 7 years of operation of the U. S. Geological Survey TRIGA Reactor (GSTR) facility. In these 7 years we have generated more than 5800 MWH's of thermal energy and irradiated more than 47,000 samples for experimenters from the Survey, universities, and other Governmental agencies. Several mechanical and electrical components have required attention. Changes to the technical specifications have included one minor wording change involving the evacuation alarm, a reevaluation of the measurement of argon-41 concentrations, a revision concerning transient-rod maintenance, and a reduction in the frequency of fuel-element measurements. To improve physical security we have increased building security, installed an intrusion alarm, and, most recently, expanded the boundaries of the facility within the building to provide better control access. There also have been major changes to our operating procedures and the initiation of a reactor-operator requalification program. (author)

Industrial structure at research reactor suppliers

International Nuclear Information System (INIS)

Roegler, H.-J.; Bogusch, E.; Friebe, T.

2001-01-01

Due to the recent joining of the forces of Framatome S. A. from France and the Nuclear Division of Siemens AG Power Generation (KWU) from Germany to a Joint Venture named Framatome Advanced Nuclear Power S.A.S., the issue of the necessary and of the optimal industrial structure for nuclear projects as a research reactor is, was discussed internally often and intensively. That discussion took place also in the other technical fields such as Services for NPPs but also in the field of interest here, i. e. Research Reactors. In summarizing the statements of this presentation one can about state that: Research Reactors are easier to build than NPPs, but not standardised; Research Reactors need a wide spectrum of skills and experiences; to design and build Research Reactors needs an experienced team especially in terms of management and interfaces; Research Reactors need background from built reference plants more than from operating plants; Research Reactors need knowledge of suitable experienced subsuppliers. Two more essential conclusions as industry involved in constructing and upgrading research reactors are: Research Reactors by far are more than a suitable core that generates a high neutron flux; every institution that designs and builds a Research Reactor lacks quality or causes safety problems, damages the reputation of the entire community

ZEEP: Canada's first nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Green, R.E.; Okazaki, A. [retired, Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

2015-09-15

In 1905 Albert Einstein published his historic paper on special relativity, which contained the equation E=mc 2. The significance of this mass-energy relationship became evident with the discovery of nuclear fission in 1939, when it was realized that large amounts of energy would be released in a fission chain reaction. Canadian scientists were involved in this field from the beginning and their efforts resulted in the startup in September 1945 of the ZEEP reactor at Chalk River, the first reactor to go critical outside the USA. In this paper we recall some of the events that led to the construction of ZEEP, and describe the role it played in the development of the Canadian nuclear energy program. (author)

Direct energy conversion in fission reactors: A U.S. NERI project

International Nuclear Information System (INIS)

Slutz, Stephen A.; Seidel, David B.; Polansky, Gary F.; Rochau, Gary E.; Lipinski, Ronald J.; Besenbruch, G.; Brown, L.C.; Parish, T.A.; Anghaie, S.; Beller, D.E.

2000-01-01

In principle, the energy released by a fission can be converted directly into electricity by using the charged fission fragments. The first theoretical treatment of direct energy conversion (DEC) appeared in the literature in 1957. Experiments were conducted over the next ten years, which identified a number of problem areas. Research declined by the late 1960's due to technical challenges that limited performance. Under the Nuclear Energy Research Initiative the authors are determining if these technical challenges can be overcome with todays technology. The authors present the basic principles of DEC reactors, review previous research, discuss problem areas in detail, and identify technological developments of the last 30 years that can overcome these obstacles. As an example, the fission electric cell must be insulated to avoid electrons crossing the cell. This insulation could be provided by a magnetic field as attempted in the early experiments. However, from work on magnetically insulated ion diodes they know how to significantly improve the field geometry. Finally, a prognosis for future development of DEC reactors will be presented

Notes on Women Who Rock: Making Scenes, Building Communities: Participatory Research, Community Engagement, and Archival Practice

Directory of Open Access Journals (Sweden)

Michelle Habell-Pallán

2014-07-01

Full Text Available Since 2011, Women Who Rock (WWR has brought together scholars, archivists, musicians, media-makers, performers, artists, and activists to explore the role of women and popular music in the creation of cultural scenes and social justice movements in the Americas and beyond. The project promotes generative dialogue and documentation by “encompassing several interwoven components: project-based coursework at the graduate and undergraduate levels; an annual participant-driven conference and film festival; and an oral history archive hosted by the University of Washington Libraries Digital Initiatives Program that ties the various components together” (Bartha 8. In our courses, programming, and archive, we examine the politics of performance, social identity, and material access in music scenes, cultures, and industries. Performance studies scholar Daphne Brooks argues that the “confluence of cultural studies, rock studies, and third wave feminist critical studies makes it possible now more than ever to continue to critique and re-interrogate the form and content of popular music histories” (58. WWR implements this approach, asking how particular stories of popular music determine a performer, band, or scene’s “legendary” status or excision from the official annals of memory. WWR reshapes conventional understandings of popular music studies by initiating collective methods of participatory research, as well as community collaboration and dialogue. By way of WWR, we seek to transform traditional models of popular music studies, instigating new convergences between academic disciplines and critical approaches that create alternative histories and new forms of knowledge.

Internet accessible hot cell with gamma spectroscopy at the Missouri S and T nuclear reactor

International Nuclear Information System (INIS)

Grant, Edwin; Mueller, Gary; Castano, Carlos; Usman, Shoaib; Kumar, Arvind

2011-01-01

Highlights: → A dual-chambered internet-accessible heavily shielded facility has been built. → The facility allows distance users to analyze neutron irradiated samples remotely. → The Missouri S and T system uses computer automation with user feedback. → The system can analyze multiple samples and assist several researchers concurrently. - Abstract: A dual-chambered internet-accessible heavily shielded facility with pneumatic access to the University of Missouri Science and Technology (Missouri S and T) 200 kW Research Nuclear Reactor (MSTR) core has been built and is currently available for irradiation and analysis of samples. The facility allows authorized distance users engaged in collaborative activities with Missouri S and T to remotely manipulate and analyze neutron irradiated samples. The system consists of two shielded compartments, one for multiple sample storage, and the other dedicated exclusively for radiation measurements and spectroscopy. The second chamber has multiple detector ports, with graded shielding, and has the capability to support gamma spectroscopy using radiation detectors such as an HPGe detector. Both these chambers are connected though a rapid pneumatic system with access to the MSTR nuclear reactor core. This new internet-based system complements the MSTR's current bare pneumatic tube (BPT) and cadmium lined pneumatic tube (CPT) facilities. The total transportation time between the core and the hot cell, for samples weighing 10 g, irradiated in the MSTR core, is roughly 3.0 s. This work was funded by the DOE grant number DE-FG07-07ID14852 and expands the capabilities of teaching and research at the MSTR. It allows individuals who do not have on-site access to a nuclear reactor facility to remotely participate in research and educational activities.

Estudio de un reactor catalítico para la obtención de gas de síntesis

OpenAIRE

Romero Sayago, Sara Isabel

2016-01-01

Este trabajo se centra en el estudio del proceso de reformado de gas natural con vapor de agua para producir gas de síntesis. Un compuesto, que como su nombre indica, es de gran importancia en la síntesis de muchos productos. En concreto, se estudia el reactor heterogéneo catalítico donde tiene lugar la reacción de reformado. Mediante un programa de simulación de procesos químicos, se optimiza el proceso de reformado para obtener un rendimiento elevado en el reactor con el mínimo consumo e...

The U.S. reduced enrichment research and test reactor (RERTR) program

International Nuclear Information System (INIS)

Travelli, A.

1993-01-01

Research and test reactors are widely deployed to study the irradiation behavior of materials of interest in nuclear engineering, to produce radioisotopes for medicine, industry, and agriculture, and as a basic research and teaching tool. In order to maximize neutron flux per unit power and/or to minimize capital costs and fuel cycle costs, most of these reactors were de- signed to utilize uranium with very high enrichment (in the 70% to 95% range). Research reactor fuels with such high uranium enrichment cause a potential risk of nuclear weapons proliferation. Over 140 research and test reactors of significant power (between 10 kW and 250 MW) are in operation with very highly enriched uranium in more than 35 countries, with total power in excess of 1,700 MW. The overall annual fuel requirement of these reactors corresponds to approximately 1,200 kg of 235 U. This highly strategic material is normally exported from the United States, converted to metal form, shipped to a fuel fabricator, and then shipped to the reactor site in finished fuel element form. At the reactor site the fuel is first stored, then irradiated, stored again, and eventually shipped back to the United States for reprocessing. The whole cycle takes approximately four years to complete, bringing the total required fuel inventory to approximately 5,000 kg of 235 U. The resulting international trade in highly-enriched uranium may involve several countries in the process of refueling a single reactor and creates a considerable concern that the highly-enriched uranium may be diverted for non-peaceful purposes while in fabrication, transport, or storage, particularly when it is in the unirradiated form. The proliferation resistance of nuclear fuels used in research and test reactors can be considerably improved by reducing their uranium enrichment to a value less than 20%, but significantly greater than natural to avoid excessive plutonium production

Pediatrics Department of the Russian Medical Academy of Continuous Professional Education and Moscow Research Clinical Institute of Pediatry and Children Surgery – half century hand in hand

Directory of Open Access Journals (Sweden)

I. N. Zakharova

2018-01-01

Full Text Available The long-term cooperation of the two scientific institutions contributing to the professional development of pediatricians is based on the long-term scientific relations of the Department of Pediatrics of the Russian Medical Academy of Continuing Professional Education and the Moscow Research Institute of Pediatrics and Pediatric Surgery (now the Research Institute of Pediatrics named after Academician Yu.E.Veltischev. The role of remarkable pediatric scientists – G.N. Speransky, Yu.E. Veltstschev, M.S. Ignatova, N.A. Korovina in the development of these links and pediatric science in Russia. 

Reactor container

International Nuclear Information System (INIS)

Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

1997-01-01

In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

Activity on non-destructive testing as constituent element of the quality management in accordance with ISO 9001:2000 standard at The Institute of Nuclear Physics, Kazakhstan

International Nuclear Information System (INIS)

Kadyrzhanov, K.K.; Kislitsin, S.B.; Ablanov, M.B.

2004-01-01

An increase of technical and public safety requirements for facilities of nuclear industries, an efficient quality control based on non-destructive testing (NDT) techniques is crucial. Therefore, Institute of Nuclear Physics (INP) through NDT Division makes efforts towards a competent NDT inspection of its facilities starting from research reactor of WWR-K type with a further activity according to the National Program for Development in Nuclear Industry. The additional objective is to harmonize the present codes and standards for Nuclear Industry as an integral part of the INP policy in a quality management according ISO 9001:2000 Standard. (author)

U.S. progress in the development of very high density low enrichment research reactor fuels

International Nuclear Information System (INIS)

Meyer, M. K.; Wachs, D. M.; Jue, J.-F.; Keiser, D. D.; Gan, J.; Rice, F.; Robinson, A.; Woolstenhulme, N. E.; Medvedev, P.; Hofman, G. L.; Kim, Y.-S.

2012-01-01

The effort to develop low-enriched fuels for high power research reactors began world-wide in 1996. Since that time, hundreds of fuel specimens have been tested to investigate the operational limits of many variations of U-Mo alloy dispersion and monolithic fuels. In the U.S., the fuel development program has focused on the development of monolithic fuel, and is currently transitioning from conducting research experiments to the demonstration of large scale, prototypic element assemblies. These larger scale, integral fuel performance demonstrations include the AFIP-7 test of full-sized, curved plates configured as an element, the RERTR-FE irradiation of hybrid fuel elements in the Advanced Test Reactor, reactor specific Design Demonstration Experiments, and a multi-element Base Fuel Demonstration. These tests are conducted alongside mini-plate tests designed to prove fuel stability over a wide range of operating conditions. Along with irradiation testing, work on collecting data on fuel plate mechanical integrity, thermal conductivity, fission product release, and microstructural stability is underway. (authors)

Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center

Energy Technology Data Exchange (ETDEWEB)

Bottomley, D., E-mail: paul.bottomley@ec.europa.eu [ITU Institut fuer Transurane, PO box 2340, 76125 Karlsruhe (Germany); Stuckert, J.; Hofmann, P. [KIT Campus Nord, Hermann-von-Helmholtz Pl. 1, 76344 Eggenstein-Leopoldshafen (Germany); Tocheny, L. [ISTC Krasnoproletarskaya 32-34, PO Box 20, 127473 Moscow (Russian Federation); Hugon, M. [European Commission DG - Research and Tech. Development, Sq. de Meeus, B-1049 Brussels (Belgium); Journeau, C. [CEA, DEN, Cadarache, F13108 St Paul lez Durance (France); Clement, B. [IRSN PSN-RES/SAG Cadarache, BP3 F13115, St Paul lez Durance (France); Weber, S. [GRS Muenchen, Thermal Hydraulics Div., Garching 85748,Germany (Germany); Guentay, S. [PSI NES/LTH OHSA C11, 5232 Villigen (Switzerland); Hozer, Z. [AEKI Fuel Department, P.O. Box 49, Budapest H-1525 (Hungary); Herranz, L. [CIEMAT, Energy -Nuclear Fission Division, Complutense 40, 28040 Madrid (Spain); Schumm, A. [EDF - R and D, SINETICS, Avenue du General de Gaulle 1, Clamart 92140 (France); Oriolo, F. [Pisa University, Ing. Mecc. Nucl. Prod., Largo Lazarino 2, Pisa 56126 (Italy); Altstadt, E. [HZDR Structural Matls, Rossendorf, Postfach 51 01 19, 01314 Dresden (Germany); Krause, M. [AECL - Reactor Safety, Chalk River, Ontario, Canada K0J 1J0 (Canada); Fischer, M. [AREVA NP GMBH, Dept. PEPA-G, 91058 Erlangen (Germany); Khabensky, V.B. [Alexandrov Institute of Technologies (NITI), Sosnovy Bor (Russian Federation); Bechta, S.V. [Kungliga Tekniska Hoegskolan (KTH), AlbaNova University Centre, Roslagstullsbacken 21, SE-106 91 Stockholm (Sweden); Veshchunov, M.S. [Nuclear Safety Institute (IBRAE), Russian Academy of Sciences, 52 B. Tulskaya, Moscow 115191 (Russian Federation); Palagin, A.V. [KIT Campus Nord, Hermann-von-Helmholtz Pl. 1, 76344 Eggenstein-Leopoldshafen (Germany); and others

2012-11-15

Highlights: Black-Right-Pointing-Pointer ISTC supported successful nuclear safety projects between EU and Russian institutes. Black-Right-Pointing-Pointer Two-tier project monitoring has proved to be very successful and flexible. Black-Right-Pointing-Pointer Examples are reactor degradation, corium steel corrosion, and corium thermodynamics. - Abstract: The International Science and Technology Center (ISTC) was set up in Moscow to support non-proliferation of sensitive knowledge and technologies in biological, chemical and nuclear domains by engaging scientists in peaceful research programmes with a broad international cooperation. The paper has two following objectives: Bullet to describe the organization of complex, international, experimental and analytical research of material processes under extreme conditions similar to those of severe accidents in nuclear reactors and, Bullet to inform briefly about some results of these studies. The main forms of ISTC activity are Research Projects and Supporting Programs. In the Research Projects informal contact expert groups (CEGs) were set up by ISTC to improve coordination between adjacent projects and to encourage international collaboration. The European Commission was the first to use this. The CEG members - experts from the national institutes and industry - evaluated and managed the projects' scientific results from initial stage of proposal formulation until the final reporting. They were often involved directly in the project's details by joining the Steering Committees of the project. The Contact Expert Group for Severe Accidents and Management (CEG-SAM) is one of these groups, five project groups from this area from the total of 30 funded projects during 10 years of activity are detailed to demonstrate this: (1) QUENCH-VVER from RIAR, Dimitrovgrad and IBRAE, Moscow, and PARAMETER projects (SF1-SF4) from LUCH, Podolsk and IBRAE, Moscow; these concerned a detailed study of bundle quenching from high

Researches in radiation protection and safety at Moscow engineering physics institute

International Nuclear Information System (INIS)

Kramer-Ageev, E.A.; Lebedev, L.A.

1994-01-01

Department of Radiation Physics of Moscow Engineering Physics Institute is a research and teaching institution in the field of radiation protection, dosimetry, shielding and in radioecology. The scientific activity which has been doing at the department for many years includes the following directions: 1. Development of mathematical models and computational methods for an evaluation of external and internal exposure of people living on contaminated areas. Recently the computational model for forecast of internal irradiation via food chains was linked with computer geographical information systems. 2. Development of techniques and instruments for the measurements of radioactive contamination of soil, air, water and agricultural products. Department has special laboratory for this. 3. Application of computational methods to the problem of nuclear medicine. The whole body spectrometry and radiation 'coding' are used as an efficient methods of obtaining information on the radionuclides location in the human body. 4. Application of computational methods to the problem of radiation safety at nuclear power plants. It allows one to calculate radiation fields in shielding and the characteristics of nuclear wastes. (author)

STATE OF THE ART OF CANCER CARE DELIVER Y IN MOSCOW

Directory of Open Access Journals (Sweden)

A. P. Gnatyuk

2015-01-01

Full Text Available Abstract:The globally increased concern with the situation, existing in oncology, is conditioned by a steady incidence rate of malignant neoplasms, having a tendency to its growth. Annually over 7 million people die in the world due to cancer, by 2020, according to WHO estimations, this index will increase to 10 million. By the end of the 2013 report year patient population with cancer, registered in cancer care facilities of the Russian Federation, is 3 098 855 (2 995 566 in 2012, i. e. 2,1% of the population of the country. The system of cancer care delivery to the population in the Russian Federation and in Moscow is aimed at an early diagnostics and prevention of malignant neoplasms. Municipal cancer care service establishes the patients’ routes at suspicion on oncological disease and determines the functions of all links of health care for this type of patients. Stateof-the-art delivery of oncological specialty care has been built up with account of modern demands and is functionally structured in accordance with tree-level municipal health care system.

Power Trip Set-points of Reactor Protection System for New Research Reactor

International Nuclear Information System (INIS)

Lee, Byeonghee; Yang, Soohyung

2013-01-01

This paper deals with the trip set-point related to the reactor power considering the reactivity induced accident (RIA) of new research reactor. The possible scenarios of reactivity induced accidents were simulated and the effects of trip set-point on the critical heat flux ratio (CHFR) were calculated. The proper trip set-points which meet the acceptance criterion and guarantee sufficient margins from normal operation were then determined. The three different trip set-points related to the reactor power are determined based on the RIA of new research reactor during FP condition, over 0.1%FP and under 0.1%FP. Under various reactivity insertion rates, the CHFR are calculated and checked whether they meet the acceptance criterion. For RIA at FP condition, the acceptance criterion can be satisfied even if high power set-point is only used for reactor trip. Since the design of the reactor is still progressing and need a safety margin for possible design changes, 18 MW is recommended as a high power set-point. For RIA at 0.1%FP, high power setpoint of 18 MW and high log rate of 10%pp/s works well and acceptance criterion is satisfied. For under 0.1% FP operations, the application of high log rate is necessary for satisfying the acceptance criterion. Considering possible decrease of CHFR margin due to design changes, the high log rate is suggested to be 8%pp/s. Suggested trip set-points have been identified based on preliminary design data for new research reactor; therefore, these trip set-points will be re-established by considering design progress of the reactor. The reactor protection system (RPS) of new research reactor is designed for safe shutdown of the reactor and preventing the release of radioactive material to environment. The trip set point of RPS is essential for reactor safety, therefore should be determined to mitigate the consequences from accidents. At the same time, the trip set-point should secure margins from normal operational condition to avoid

Tank type reactor

International Nuclear Information System (INIS)

Otsuka, Fumio.

1989-01-01

The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

Advanced reactor development: The LMR integral fast reactor program at Argonne

International Nuclear Information System (INIS)

Till, C.E.

1990-01-01

Reactor technology for the 21st Century must develop with characteristics that can now be seen to be important for the future, quite different from the things when the fundamental materials and design choices for present reactors were made in the 1950s. Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 3 figs

A Compilation of Boiling Water Reactor Operational Experience for the United Kingdom's Office for Nuclear Regulation's Advanced Boiling Water Reactor Generic Design Assessment

Energy Technology Data Exchange (ETDEWEB)

Wheeler, Timothy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Liao, Huafei [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-12-01

United States nuclear power plant Licensee Event Reports (LERs), submitted to the United States Nuclear Regulatory Commission (NRC) under law as required by 10 CFR 50.72 and 50.73 were evaluated for reliance to the United Kingdom’s Health and Safety Executive – Office for Nuclear Regulation’s (ONR) general design assessment of the Advanced Boiling Water Reactor (ABWR) design. An NRC compendium of LERs, compiled by Idaho National Laboratory over the time period January 1, 2000 through March 31, 2014, were sorted by BWR safety system and sorted into two categories: those events leading to a SCRAM, and those events which constituted a safety system failure. The LERs were then evaluated as to the relevance of the operational experience to the ABWR design.

Inspection program for U.S. research reactors

International Nuclear Information System (INIS)

Isaac, Patrick J.

2010-01-01

This paper presents an established program for inspection of nuclear research reactors to ensure that systems and techniques are in accordance with regulatory requirements and to provide protection for the health and safety of the public. The inspection program, implemented from the time a facility gets licensed, remains in effect through operations, shutdown, decommissioning, and until the license is terminated. The program establishes inspection methodology for operating, safeguards, and decommissioning activities. Using a performance- based approach, inspectors focus their attention on activities important to safety. Inspection procedures allow the inspectors to assess facility safety and compliance to applicable requirements. A well designed inspection program is an integral part of the mechanism to ensure that the level of performance in the strategic areas of reactor safety, radiation safety, and safeguards is acceptable and provides adequate protection of public health and safety. (author)

Reactor BR2

Energy Technology Data Exchange (ETDEWEB)

Gubel, P

2000-07-01

The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

Personnel training experience in the radioactive waste management: 10 years of Moscow SIA 'RADON' international education training centre

International Nuclear Information System (INIS)

Batyukhnova, Olga; Dmitriev, Sergey; Arustamov, Artur; Ojovan, Mikhael

2007-01-01

Available in abstract form only. Full text of publication follows: The education service for specialists dealing with radioactive waste was established in Russia (former USSR) in 1983 and was based on the capabilities of two organisations: the Moscow Scientific and Industrial Association 'Radon' (SIA 'Radon') and the Chemical Department of Lomonosov's Moscow State University. These two organizations are able to offer training programs in the science fundamentals, applied research and in practical operational areas of the all pre-disposal activities of the radioactive waste management. Since 1997 this system was upgraded to the international level and now acts as International Education Training Centre (IETC) at SIA 'Radon' under the guidance of the IAEA. During 10 years more than 300 specialists from 26 European and Asian countries enhanced their knowledge and skills in radioactive waste management. The IAEA supported specialized regional training courses and workshops, fellowships, on-the-job training, and scientific visits are additional means to assure development of personnel capabilities. Efficiency of training was carefully analysed using the structural adaptation of educational process as well as factors, which have influence on education quality. Social-psychological aspects were also taken into account in assessing the overall efficiency. The analysis of the effect of individual factors and the efficiency of education activity were carried out based on attestation results and questioning attendees. A number of analytical methods were utilised such as Ishikawa's diagram method and Pareto's principle for improving of training programs and activities. (authors)

Planning the Decommissioning of Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Podlaha, J., E-mail: pod@ujv.cz [Nuclear Research Institute Rez, 25068 Rez (Czech Republic)

2013-08-15

In the Czech Republic, three research nuclear reactors are in operation. According to the valid legislation, preliminary decommissioning plans have been prepared for all research reactors in the Czech Republic. The decommissioning plans shall be updated at least every 5 years. Decommissioning funds have been established and financial resources are regularly deposited. Current situation in planning of decommissioning of research reactors in the Czech Republic, especially planning of decommissioning of the LVR-15 research reactor is described in this paper. There appeared new circumstances having wide impact on the decommissioning planning of the LVR-15 research reactor: (1) Shipment of spent fuel to the Russian Federation for reprocessing and (2) preparation of processing of radioactive waste from reconstruction of the VVR-S research reactor (now LVR-15 research reactor). The experience from spent fuel shipment to the Russian Federation and from the process of radiological characterization and processing of radioactive waste from reconstruction of the VVR-S research reactor (now the LVR-15 research reactor) and the impact on the decommissioning planning is described in this paper. (author)

Postirradiation thermocyclic loading of ferritic-martensitic structural materials

Science.gov (United States)

Belyaeva, L.; Orychtchenko, A.; Petersen, C.; Rybin, V.

Thermonuclear fusion reactors of the Tokamak-type will be unique power engineering plants to operate in thermocyclic mode only. Ferritic-martensitic stainless steels are prime candidate structural materials for test blankets of the ITER fusion reactor. Beyond the radiation damage, thermomechanical cyclic loading is considered as the most detrimental lifetime limiting phenomenon for the above structure. With a Russian and a German facility for thermal fatigue testing of neutron irradiated materials a cooperation has been undertaken. Ampule devices to irradiate specimens for postirradiation thermal fatigue tests have been developed by the Russian partner. The irradiation of these ampule devices loaded with specimens of ferritic-martensitic steels, like the European MANET-II, the Russian 05K12N2M and the Japanese Low Activation Material F82H-mod, in a WWR-M-type reactor just started. A description of the irradiation facility, the qualification of the ampule device and the modification of the German thermal fatigue facility will be presented.

Design, fabrication and transportation of Si rotating device

International Nuclear Information System (INIS)

Kimura, Nobuaki; Imaizumi, Tomomi; Takemoto, Noriyuki; Tanimoto, Masataka; Saito, Takashi; Hori, Naohiko; Tsuchiya, Kunihiko; Romanova, Nataliya; Gizatulin, Shamil; Martyushov, Alexandr; Nakipov, Darkhan; Chakrov, Petr; Tanaka, Futoshi; Nakajima, Takeshi

2012-06-01

Si semiconductor production by Neutron Transmutation Doping (NTD) method using the Japan Materials Testing Reactor (JMTR) has been investigated in Neutron Irradiation and Testing Reactor Center, Japan Atomic Energy Agency (JAEA) in order to expand industry use. As a part of investigations, irradiation test of silicon ingot for development of NTD-Si with high quality was planned using WWR-K in Institute of Nuclear Physics (INP), National Nuclear Center of Republic of Kazakhstan (NNC-RK) based on one of specific topics of cooperation (STC), Irradiation Technology for NTD-Si (STC No.II-4), on the implementing arrangement between NNC-RK and the JAEA for 'Nuclear Technology on Testing/Research Reactors' in cooperation in research and development in nuclear energy and technology. As for the irradiation test, Si rotating device was fabricated in JAEA, and the fabricated device was transported with irradiation specimens from JAEA to INP-NNC-RK. This report described the design, the fabrication, the performance test of the Si rotating device and transportation procedures. (author)

Revised reactor accident source terms in the U.S. and implementation for light water reactors

International Nuclear Information System (INIS)

Soffer, L.; Lee, J.Y.

1992-01-01

Current NRC reactor accident source terms used for licensing are contained in Regulatory Guides 1.3 and 1.4 and specify that 100 % of the core inventory of noble gases and 25 % of the iodine fission products are assumed to be instantaneously available for release from the containment. The chemical form of the iodine fission products is also assumed to be predominantly elemental (I 2 ) iodine. These assumptions have strongly affected present nuclear plant designs. Severe accident research results have confirmed that although the current source term is very substantial and has resulted in a very high level of plant capability, the present source term is no longer compatible with a realistic understanding of severe accidents. The NRC has issued a proposed revision of the reactor accident source terms as part of several regulatory activities to incorporate severe accident insights for future plants. A revision to 10 CFR 100 is also being proposed to specify site criteria directly and to eliminate source terms and doses for site evaluation. Reactor source terms will continue to be important in evaluating plant designs. Although intended primarily for future plants, existing and evolutionary power plants may voluntarily apply revised accident source term insights as well in licensing. The proposed revised accident source terms are presented in terms of fission product composition, magnitude, timing and iodine chemical form. Some implications for light water reactors are discussed. (author)

An overview of the U.S. Department of Energy Experimental Boiling Water Reactor Decontamination and Decommissioning Project

International Nuclear Information System (INIS)

Murphie, W.E.; Mckernan, M.L.

1991-01-01

This paper provides an overview of the U.S. Department of Energy's (DOE) Experimental Boiling Water Reactor (EBWR) Decontamination and Decommissioning (D and D) Project. Physical decommissioning work started in 1986 and is scheduled for completion in 1994. The project total estimated cost is 14.3 million (1990, U.S.) dollars. The reactor pressure vessel will be removed by segmentation. Another notable project feature is that D and D operations were planned for and carried out with a small work force comprised of four to six D and D laborers, one or two health physics technicians, an engineer, and a project manager. When the D and D work is completed the facility will be recycled for other productive uses. (author)

Use of enriched uranium in Canada's power reactors

International Nuclear Information System (INIS)

Dormuth, K.W.; Jackson, D.P.

2011-01-01

Recent trends in Canadian nuclear power reactor design and proposed development of nuclear power in Canada have indicated the possibility that Canada will break with its tradition of natural uranium fuelled systems, designed for superior neutron economy and, hence, superior uranium utilization. For instance, the Darlington B new reactor project procurement process included three reactor designs, all employing enriched fuel, although a natural uranium reactor design was included at a late stage in the ensuing environmental assessment for the project as an alternative technology. An evaluation of the alternative designs should include an assessment of the environmental implications through the entire fuel cycle, which unfortunately is not required by the environmental assessment process. Examples of comparative environmental implications of the reactor designs throughout the fuel cycle indicate the importance of these considerations when making a design selection. As Canada does not have enrichment capability, a move toward the use of enriched fuel would mean that Canada would be exporting natural uranium and buying back enriched uranium with value added. From a waste management perspective, Canada would need to deal with mill, refinery, and conversion tailings, as well as with the used fuel from its own reactors, while the enrichment supplier would retain depleted uranium with some commercial value. On the basis of reasoned estimates based on publicly available information, it is expected that enrichment in Canada is likely to be more profitable than exporting natural uranium and buying back enriched uranium. Further, on the basis of environmental assessments for enrichment facilities in other countries, it is expected that an environmental assessment of a properly sited enrichment facility would result in approval. (author)

Advanced CANDU reactors

International Nuclear Information System (INIS)

Dunn, J.T.; Finlay, R.B.; Olmstead, R.A.

1988-12-01

AECL has undertaken the design and development of a series of advanced CANDU reactors in the 700-1150 MW(e) size range. These advanced reactor designs are the product of ongoing generic research and development programs on CANDU technology and design studies for advanced CANDU reactors. The prime objective is to create a series of advanced CANDU reactors which are cost competitive with coal-fired plants in the market for large electricity generating stations. Specific plant designs in the advanced CANDU series will be ready for project commitment in the early 1990s and will be capable of further development to remain competitive well into the next century

K-East and K-West Reactors

Data.gov (United States)

Federal Laboratory Consortium — Hanford's "sister reactors", the K-East and the K-West Reactors, were built side-by-side in the early 1950's. The two reactors went operational within four months of...

Reactor pressure tank

International Nuclear Information System (INIS)

Dorner, H.; Scholz, M.; Jungmann, A.

1975-01-01

In a reactor pressure tank for a nuclear reactor, self-locking hooks engage a steel ring disposed over the removable cover of the steel vessel. The hooks exert force upon the cover to maintain the cover in a closed position during operation of the reactor pressure tank. The force upon the removal cover is partly the result of the increasing temperature and thermal expansion of the steel vessel during operation. The steel vessel is surrounded by a reinforced-concrete tank. (U.S.)

Application of S-CO{sub 2} Cycle for Small Modular Reactor coupled with Desalination System

Energy Technology Data Exchange (ETDEWEB)

Lee, Won Woong; Bae, Seong Jun; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

2016-10-15

The Korean small modular reactor, SMART (System-integrated Modular Advanced ReacTor, 100MWe), is designed to achieve enhanced safety and improved economics through reliable passive safety systems, a system simplification and component modularization. SMART can generate electricity and provide water by seawater desalination. However, due to the desalination aspect of SMART, the total amount of net electricity generation is decreased from 100MWe to 90MWe. The authors suggest in this presentation that the reduction of electricity generation can be replenished by applying S-CO{sub 2} power cycle technology. The S-CO{sub 2} Brayton cycle, which is recently receiving significant attention as the next generation power conversion system, has some benefits such as high cycle efficiency, simple configuration, compactness and so on. In this study, the cycle performance analysis of the S-CO{sub 2} cycles for SMART with desalination system is conducted. The simple recuperated S-CO{sub 2} cycle is revised for coupling with desalination system. The three revised layout are proposed for the cycle performance comparison. In this results of the 3rd revised layout, the cycle efficiency reached 37.8%, which is higher than the efficiency of current SMART with the conventional power conversion system 30%.

HE CADASTRAL VA LUE OF REAL ESTATE — AN INDICATOR OF THE EFFICIENCY OF CITY DEVELOPMENT PROGRAMS (ON THE EXAMPLE OF MOSCOW

Directory of Open Access Journals (Sweden)

Belyakov Sergey Igorevich

2015-06-01

Full Text Available At the recent time the Moscow authority developed and im-plements a number of programs on city development aimed at raising the living comfort level of the population, advancing the urban development system, improvement of investment climate, etc. The most important role is played by the State program of Moscow “Town-Planning Policy” for 2012—2018. Different indicators are used to assess the efficiency of the programs. At the present time it is reasonable to consider all the processes connected with attraction and application of budget means of different levels, including for programs implementation, in the whole context of transition from the old taxation system where the real estate tax was calculated according to its inventory value to the new system, where the cadastral value of real estate objects is the basis for tax charge. The author considers the prerequisites and justification of the approach to territorial taxable capacity formation, which supposes application of cadastral value of real estate objects as efficiency indicator of city development programs. This indicator reflects a variety of fundamental factors characterizing an objective value of real estate objects and the development level of spatial-territorial environment as a whole.

Prevalence and characteristics of various types of lichen planus in the Moscow Region

Directory of Open Access Journals (Sweden)

Yu. V. Molochkova

2018-01-01

Full Text Available Rationale: Lichen planus (LP is an important problem for the healthcare due to its increasing prevalence, as well as typical, atypical and prone to malignization types of the disease that can be both severe and poorly responding to treatment. Accurate data on the prevalence of LP are lacking.Aim: To assess the prevalence of various LP types in the patient population of the Moscow Region.Materials and methods: We analyzed the results of examination of 338 patients with LP, who were getting standard treatment in the Department of Dermatovenereology and Dermato-oncology of the Moscow Regional Research and Clinical Institute (MONIKI in 1999 to 2017.Results: Among 338 LP patients, atypical LP of the skin was diagnosed in 81 (23.96%: hypertrophic type, in 31 (38.27%, pigmented, in 23 (28.4%, atrophic, in 11 (13.58%, follicular, in 8 (9.88%, lichen obtusus, in 3 (3.7%, bullous, in 1 (1.23%, erythematous, in 1 (1.23%, vulvovaginal-gingival syndrome, in 2 (2.47%, and Grinspan's syndrome, in 1 (1.23%. In 35 (43.21% of patients, cutaneous LP was associated with atypical oral LP (OLP: in 17 (48.57% of cases with hyperkeratotic, in 11 (31.43%, with erosive, and in 7 (20%, with exudative-hyperemic type. In 19 (23.46% cases, atypical cutaneous LP was associated with LP of the genital mucosae, including in 12 (63.16% cases with a typical reticular type, in 6 (31.58%, with atypical erosive, and in 1 (5.26%, with hypertrophic type. In 16 (4.73% of the patients there was atypical OLP only; in 6 (37.5% of them it had the exudative-hyperemic type, in 5 (31.25%, erosive, and in 5 (31.25%, hyperkeratotic. The most severe course of the dermatosis was observed for follicular, atrophic, hypertrophic types of cutaneous LP, vulvovaginal-gingival syndrome, and erosive OLP.Conclusion: Atypical LP was diagnosed in 81 (23.96% cases, and in 45 (55.6% cases it was associated with the OLP. The latter in 35 (43.21% of cases was characterized by atypical lesions of OLP, including

Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

Energy Technology Data Exchange (ETDEWEB)

Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Mueller, Donald E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Patton, Bruce W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Powers, Jeffrey J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

2016-08-31

Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 ⁷LiF-BeF₂) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.

Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

International Nuclear Information System (INIS)

Brown, Nicholas R.; Mueller, Donald E.; Patton, Bruce W.; Powers, Jeffrey J.

2016-01-01

Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 "7LiF-BeF_2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.

A Short Assessment of Select Remediation Issues at the Russian Research Center-Kurchatov Institute, Moscow, Russia

International Nuclear Information System (INIS)

Gephart, Roy E.

2007-01-01

At the invitation of the National Academies, Roy Gephart traveled to Russia with an eight-member U.S. team during June, 2008 to participate in a workshop hosted by the National Academies and the Russian Academy of Sciences on radiation contamination and remediation issues in the former Soviet Union. Cleanup problems were assessed by the American participants for six Russian sites: Kurchatov Institute, Lakes 10 and 11 at Mayak, Andreev Bay, Krasnokamensk Mining Enterprise (Siberia), Almaz Mining Enterprise (North Caucasus), and one site for testing peaceful nuclear explosions. Roy lead the Russian Research Center-Kurchatov Institute review session and wrote an assessment of key cleanup issues. Kurchatov is the leading institute in the Former Soviet Union devoted to military and civilian nuclear programs. Founded in 1943 in the outskirts of Moscow, this 100 hectare site of nearly undeveloped, prime real estate is now surrounded by densely populated urban and business districts. Today there are growing concerns over the public safety and environmental security of the site resulting from increasingly obsolete nuclear facilities and a legacy of inadequate waste management practices that resulted in contaminant releases and challenging remediation problems. In addition, there is growing concern over the presence of nuclear facilities within urban areas creating potential targets for terrorist attacks.

Luncheon address: Development of the CANDU reactor

International Nuclear Information System (INIS)

Bain, A.S.

1997-01-01

The paper is a highlight of the some of the achievements in the development of the CANDU Reactor, taken from the book C anada Enters the Nuclear Age . The CANDU reactor is one of Canada's greatest scientific/engineering achievements, that started in the 1940's and bore fruit with the reactors of the 60's, 70's, and 80's. The Government decided in the 1950's to proceed with a demonstration nuclear power reactor (NPD), AECL invited 7 Canadian corporations to bid on a contract to design and construct the NPD plant. General Electric was selected. A utility was also essential for participation and Ontario Hydro was chosen. In May 1957 it was concluded that the minimum commercial size would be about 200MWe and it should use horizontal pressure tubes to contain the fuel and pressurized heavy water coolant. The book also talks of standard out-reactor components such as pumps, valves, steam generators and piping. A major in-reactor component of interest was the fuel, fuel channels and pressure tubes. A very high level of cooperation was required for the success of the CANDU program

Reactor feedwater system

International Nuclear Information System (INIS)

Kagaya, Hiroyuki; Tominaga, Kenji.

1993-01-01

In a simplified water type reactor using a gravitationally dropping emergency core cooling system (ECCS), the present invention effectively prevents remaining high temperature water in feedwater pipelines from flowing into the reactor upon occurrence of abnormal events. That is, (1) upon LOCA, if a feedwater pipeline injection valve is closed, boiling under reduced pressure of the remaining high temperature water occurs in the feedwater pipelines, generated steams prevent the remaining high temperature water from flowing into the reactor. Accordingly, the reactor is depressurized rapidly. (2) The feedwater pipeline injection valve is closed and a bypassing valve is opened. Steams generated by boiling under reduced pressure of the remaining high temperature water in the feedwater pipelines are released to a condensator or a suppression pool passing through bypass pipelines. As a result, the remaining high temperature water is prevented from flowing into the reactor. Accordingly, the reactor is rapidly depressurized and cooled. It is possible to accelerate the depressurization of the reactor by the method described above. Further, load on the depressurization valve disposed to a main steam pipe can be reduced. (I.S.)

German research reactor back-end provisions

International Nuclear Information System (INIS)

Koester, Siegfried; Gruber, Gerhard

2002-01-01

Germany has several types of Research Reactors in operation. These reactors use fuel containing uranium of U.S. origin. Basically all the fuel which will be spent until May 2006 will be returned to the U.S. under existing contracts with the U.S. Department of Energy. The contracts are based on the U.S. FRR SNF (Foreign Research Reactor Spent Nuclear Fuel) Program which started in May 1996 and which will last for 10 years. In 1990, the German Federal Government started a program to long-term store (approx. 40 years) and finally dispose of spent fuel in Germany after the so-called U.S. fuel return window will be closed. In order to long-term store the fuel, a special container was designed which covers all different types of spent fuel from the Research Reactors. The container called 'CASTOR MTR 2' is basically licensed and is already in use for the spent fuel of Russian origin from the 'Research Reactor Rossendorf' in the eastern part of Germany. All that fuel is expected to be stored in the existing intermediate storage facility, the so-called BZA (Brennelemente Zwischenlager Ahaus). BZA already accomodates spent fuel from the former THTR-300 high temperature reactor. A final repository does not yet exist in Germany. Alternative provisions to close the back-end of the Research Reactor fuel cycle are reprocessing at COGEMA (France) or in Russian facilities, perspectively. Waste return in a form to be agreed will be mandatory, at least in France. (author)

Research reactor safety - an overview of crucial aspects

Energy Technology Data Exchange (ETDEWEB)

Laverie, M. [Atomic Energy Commission, Saclay, F-91191 Gif sur Yvette (France)

1998-07-01

Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

Meeting the reactor operator's information needs using functional analysis

Energy Technology Data Exchange (ETDEWEB)

Nelson, W.R.; Clark, M.T.

1980-01-01

Since the accident at Three Mile Island, many ideas have been proposed for assisting the reactor operator during emergency situations. However, some of the suggested remedies do not alleviate an important shortcoming of the TMI control room: the operators were not presented with the information they needed in a manner which would allow prompt diagnosis of the problem. To address this problem, functional analysis is being applied at the LOFT facility to ensure that the operator's information needs are being met in his procedures and graphic displays. This paper summarizes the current applications of functional analysis at LOFT.

"Telling our stories": Print media interpretations of Moscow lesbians' life stories in 2004 and 2005.

Science.gov (United States)

Bingham, Natasha

2017-01-02

This article analyzes print media interviews of Moscow lesbians in Moskovsky Komsomolets in 2004 and 2005 using qualitative content analysis. The qualitative content analysis shows recurring and consistent themes: (1) the stereotypes lesbians face; (2) public negativity toward same-sex relations and the impact on their families; (3) the expectations of heterosexuality and all that that entails; (4) the existence of lesbian-only spaces in Russia and the importance of those spaces; and (5) the complexities of navigating motherhood, previous heterosexual relationships, and current partnerships. Analysis of print media representations of female same-sex sexuality in a period of economic prosperity, popular culture visibility, and before restrictive laws were passed that suppress homosexuality adds to the previous literature on lesbianism in Russia.

The nuclear question at the start of the '80s: the breeder reactor

International Nuclear Information System (INIS)

Owen, R.; Svensson, B.

1980-01-01

The four newspaper articles and the letter cover the following matters: general introduction about breeder reactors and the situation in Swedish politics; visit to Dounreay to discuss breeder reactors (breeding, safety, plutonium production, radiation protection); PuO 2 -UO 2 mixed fuel; description of breeder reactors; efficiency in use of U-235; DFR and PFR; breeder reactors in Swedish politics (arguments for and against nuclear power in general, breeder reactors in particular); discussion of the future of nuclear power in Sweden. (U.K.)

78 FR 71675 - Update of the Office of Nuclear Reactor Regulation's Electronic Operating Reactor Correspondence

Science.gov (United States)

2013-11-29

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0260] Update of the Office of Nuclear Reactor Regulation's Electronic Operating Reactor Correspondence The U.S. Nuclear Regulatory Commission (NRC) is issuing this Federal Register notice to inform the public of a slight change in the manner of distribution of publicly available operating reactor licensing...

Design and construction of a preamplifier for research reactor control system using Russia’s neutron detectors

International Nuclear Information System (INIS)

Trinh Dinh Hai; Vo Van Tai; Le Van Diep; Nguyen Nhi Dien

2016-01-01

This paper presents the design and construction of a preamplifier device for Research Reactor Control System, using Russia’s Neutron Detectors of ionization and fission chambers. In this work, the preamplifier device which consists of a wide range Current to Frequency Converter block used with a compensation ionization chamber type KNK-3 to measure the thermal neutron flux in the range of 1x10"6 - 1x10"1"1 n/cm"2.s, a Pulse Preamplifier block used with a fission chamber type KNK-15 to measure the thermal neutron flux in the range of 1x10"0 - 1x10"6 n/cm"2.s, and a Power Supply block, was designed and tested in different conditions in the laboratory and at Dalat Nuclear Research Reactor (DNRR). Obtained results show that, the above blocks have almost design specifications as equivalent or better in comparison with the same function blocks of the DNRR Control System which were designed by the former Soviet Union. They also meet the utilization requirements as well as the experimental and training purposes. (author)

Fusion Reactor Materials

Energy Technology Data Exchange (ETDEWEB)

Decreton, M

2002-04-01

The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

Nuclear Power: Outlook for New U.S. Reactors

National Research Council Canada - National Science Library

Parker, Larry; Holt, Mark

2007-01-01

.... The renewed interest in nuclear power has resulted primarily from higher prices for natural gas, improved operation of existing reactors, and uncertainty about future restrictions on coal emissions...

Reactor power measuring device

International Nuclear Information System (INIS)

Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

1993-01-01

The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

Deuterated fibre Z-pinch on the S-300 generator

NARCIS (Netherlands)

Klir, D.; Kravarik, J.; Kubes, P.; Bakshaev, Yu L.; Blinov, P. I.; Chernenko, A. S.; Danko, S. A.; Korolev, V. D.; Ustroev, G. I.; Ivanov, M. I.; Cai, Hongchun

2006-01-01

Dense Z-pinch experiments were carried out on the S-300 generator (3.5 MA, 100 ns, 0.15 Omega) at the Kurchatov Institute in Moscow. The experiments were performed at a peak current of 2 MA with a rise time of about 100 ns. The Z-pinch was formed from a deuterated polyethylene fibre of 100 mu m

[Analysis of the causes of cancer negligence and low survival in the patients with malignant neoplasms of ENT and oral cavity in the city of Moscow].

Science.gov (United States)

Sdvizhkov, A M; Kozhanov, L G; Shatskaia, N Kh; Belov, E N

2014-01-01

The objective of the present study was to elucidate the causes of late detection of malignant neoplasms of ENT and oral cavity and low survival of the patents with these tumours in Moscow. The secondary objective was to elaborate the organizational measures for reducing the level of negligence and mortality from these malignancies among the city population. It was shown that the main cause behind the negligence is the late application of the patients for the medical assistance. Next in importance are asymptomatic clinical course of the disease in the absence of the pathognomonic and early signs of malignant neoplasms, a combination of several pathologies, imperfection of medical knowledge, and the poor resolving power of the modern methods. It is emphasized that the lack of vigilance against cancer among the practicing health providers is one of the main causes of medical errors. A few ways to address the problem of negligence with respect to malignant neoplasms of ENT and oral cavity in Moscow are proposed.

Peculiarities of adaptation reactions in female migrants and health disorders risks occuring after different periods of staying on Moscow region territory

OpenAIRE

N.F. Izmerov; N.I. Izmerova; I.V. Bukhtiyarov; M. Khodzhiev

2017-01-01

The article gives the results of determining peculiarities which are characteristic for adaptation in female migrants de-pending on a period of their staying in Moscow region. Adaptation was assessed as per variants of functional stress status and functional abilities of circulatory system. We detected that female migrants during their adaptation to impacts exerted by neuro-emotional factors, social-psychological factors, and physical (muscular) loads which varied in their intensity and lengt...

Reactor technology

International Nuclear Information System (INIS)

Erdoes, P.

1977-01-01

This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

Advanced Reactor Development in the United States

Energy Technology Data Exchange (ETDEWEB)

Giessing, D. F.; Griffith, J. D.; McGoff, D. J.; Rosen, Sol [U. S. Department of Energy, Texas (United States)

1990-04-15

In the United States, three technologies are employed for the new generation of advanced reactors. These technologies are Advanced Light Water Reactors (A LWRs) for the 1990s and beyond, the Modular High Temperature Gas Reactor (M HTGR) for commercial use after the turn of the century, and Liquid Metal Reactors (LWRs) to provide energy production and to convert reactor fission waste to a more manageable waste product. Each technology contributes to the energy solution. Light Water Reactors For The 1990s And Beyond--The U. S. Program The economic and national security of the United States requires a diversified energy supply base built primarily upon adequate, domestic resources that are relatively free from international pressures. Nuclear energy is a vital component of this supply and is essential to meet current and future national energy demands. It is a safe, economically continues to contribute to national energy stability, and strength. The Light Water Reactor (LWR) has been a major and successful contributor to the electrical generating needs of many nations throughout the world. It is being counted upon in the United States as a key to revitalizing nuclear energy option in the 1990s. In recent years, DOE joined with the industry to ensure the availability and future viability of the LWR option. This national program has the participation of the Nation's utility industry, the Electric Power Research Institute (EPRI), and several of the major reactor manufacturers and architect-engineers. Separate but coordinated parts of this program are managed by EPRI and DOE.

Nuclear blenders: blended learning from Rensselaer's Reactor Critical Facility

Energy Technology Data Exchange (ETDEWEB)

Haley, T.C. [Rensselaer Polytechnic Inst., Troy, NY (United States)

2011-07-01

Rensselaer's senior level undergraduate nuclear engineering course 'Critical Reactor Laboratory' is highly regarded and much loved. If you can get in, that is. But now it's a required course, nuclear engineering enrollment is up, and others are knocking on our door to get in. How might one offer such a unique course to the masses, without losing the whole point of a laboratory experience? This presentation looks at the costs and benefits of the transition to a 'blended learning' mode -- the merging of traditional, face-to-face instruction and web-based instruction as a solution. As part of the presentation, the course and the facility will be highlighted by short excepts from the 50 minute movie 'Everything You Always Wanted to Know about Neutron Chain Reactions (but were afraid to ask)'.

IAEA Mission Sees High Commitment to Safety at Ghana's Research Reactor After HEU to LEU Fuel Conversion

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts said the operator of Ghana’s research reactor has demonstrated a high commitment to safety following the conversion of the reactor core to use low enriched uranium (LEU) as fuel instead of high enriched uranium (HEU). The team also made recommendations for further safety enhancements. The Integrated Safety Assessment for Research Reactors (INSARR) team concluded a five-day mission today to assess the safety of the GHARR-1 research reactor, originally commissioned in 1994. The 30 kW reactor, operated by the Ghana Atomic Energy Commission (GAEC) at the National Nuclear Research Institute in the capital Accra, is used primarily for trace element analysis for industrial or agricultural purposes, research, education and training. In 2017, the reactor core was converted in a joint effort by Ghana, the United States and China, with assistance from the IAEA. The IAEA supported the operation to eliminate proliferation risks associated with HEU, while maintaining important scientific research. The team made recommendations for improvements to the GAEC, including: • Completing the revision of reactor safety and operating documents to reflect the results of the commissioning of the reactor after the core fuel conversion. • Enhancing the training and qualification programme for operating personnel. • Improving the capability for monitoring operational safety parameters under all conditions. • Strengthening radiation protection by establishing an effective radiation monitoring of workplace. The GAEC said it will request a follow-up INSARR mission by 2020.

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016 (ICNRP-2016)

International Nuclear Information System (INIS)

2017-01-01

We are pleased to introduce the Proceedings of the International research conference «International Conference for young scientists, specialists and post-graduates on Nuclear Reactor Physics 2016 (ICNRP-2016)» (5-9 September 2016, Health resort «Volga», Moscow, Russia) organized by the National Research Nuclear University MEPhI, with ROSATOM partnership. Representatives of research organizations and universities from twelve countries (Russia, Germany, Norway, Finland, Kazakhstan, Belarus, Italy, Slovakia etc.), delivered their presentations on various topics. The major topics are features of fast reactors, calculation for the needs of operation and design of nuclear reactors, computational reactor tests, codes and databases. Over a hundred people from 37 organizations attended the conference. More than 93 papers were presented. The received papers were reviewed according to the standards of the Journal of Physics: Conference Series and developed by the organizers’ scientific criteria. This volume of the journal includes 65 papers devoted to various branches of nuclear reactor physics and technology. During the conference, various sports activities were held, as well as a workshop on the problems of nuclear education in Russia. Most of the participants, according to the results of the survey were satisfied and expressed a desire to take part in the next conference in 2018. The organizing committee is very grateful to the: • Participants of the conference for their valuable contribution with the delivered presentations and interesting papers, • Conference program committee chairman Strikhanov M.N., rector of National Research Nuclear University MEPhI, • Program committee co-chairs: Caruso G., professor, Sapienza University of Rome, Hascik J., professor, Technical University of Bratislava, Janardhanan N.K., assistant professor, Jawaharlala Nehru University, Pershukov V.A., deputy director general, Rosatom, Tikhomirov G.V., dean of Physical

Solid State Reactor Final Report

Energy Technology Data Exchange (ETDEWEB)

Mays, G.T.

2004-03-10

The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas

Nonproliferation and Threat Reduction Assistance: U.S. Programs in the Former Soviet Union

Science.gov (United States)

2012-03-06

funds the International Science and Technology Center ( ISTC ) in Moscow and its companion Science and Technology Center (STCU) in Kiev, Ukraine. In...European Union, and Russia established the International Science and Technology Center ( ISTC ) in Moscow. Several other former Soviet states joined the...provided $9.5 million to support 34 projects. Between 1994 and 2009, the ISTC in Moscow had received more than $803 million in funding from its

Super critical water reactors

International Nuclear Information System (INIS)

Dumaz, P.; Antoni, O; Arnoux, P.; Bergeron, A; Renault, C.; Rimpault, G.

2005-01-01

Water is used as a calori-porter and moderator in the most major nuclear centers which are actually in function. In the pressurized water reactor (PWR) and boiling water reactor (BWR), water is maintained under critical point of water (21 bar, 374 Centigrade) which limits the efficiency of thermodynamic cycle of energy conversion (yield gain of about 33%) Crossing the critical point, one can then use s upercritical water , the obtained pressure and temperature allow a significant yield gains. In addition, the supercritical water offers important properties. Particularly there is no more possible coexistence between vapor and liquid. Therefore, we don't have more boiling problem, one of the phenomena which limits the specific power of PWR and BWR. Since 1950s, the reactor of supercritical water was the subject of studies more or less detailed but neglected. From the early 1990s, this type of conception benefits of some additional interests. Therefore, in the international term G eneration IV , the supercritical water reactors had been considered as one of the big options for study as Generation IV reactors. In the CEA, an active city has engaged from 1930 with the participation to a European program: The HPWR (High Performance Light Water Reactor). In this contest, the R and D studies are focused on the fields of neutrons, thermodynamic and materials. The CEA intends to pursue a limited effort of R and D in this field, in the framework of international cooperation, preferring the study of versions of rapid spectrum. (author)