Wet storage of nuclear spent fuel from nuclear research reactor WWR-S

International Nuclear Information System (INIS)

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

2001-01-01

robustness of this type of repository. The ponds are supplied with distilled water from reactor tank No 1. The spent fuel assemblies used in the WWR-S reactor and stored in this repository contain two types of fuel: the EK-10 (153 pieces) and the S-36 (70 pieces). The EK-10 and S-36 fuel assemblies have the same shape but distinct numbers of fuel rods and different percentage of U-235 enrichment. So, the EK-10 contains 16 fuel rods and 10% enrichment while the S-36 contains 15 fuel rods of 36% U-235 enrichment. Total activity of the fuel assemblies is about 10.69 x 10 4 Ci. The most important fission products in fuel rods are Sr-90 and Cs-137. Depending on fuel assembly type the calculated values of the activity of these elements are: - a. 7.14 x 10 3 Ci (Sr-90) and 7.67 x 10 3 Ci (Cs-137) for EK-10 and, - b. 8.21 x 10 3 Ci (Sr-90) and 8.08 x 10 3 Ci (Cs-137) for S-36. The gamma spectrometry analysis performed on water samples from storage ponds showed the dominant presence of Cs and other nuclides. The presence of Cs in the water is due to fuel rods flaws, the occurrence of pores and cracks because of fuel manipulation in active core of the reactor or in the storage pond or because of corrosion pits due to a low quality of water. The manufacturer have specified the water conditions for the EK-10 and S-36 fuel assemblies, which they believe will avoid corrosion problems. These are displayed in a table which enlists for EK-10 and C-36 the values of the water parameters, namely the values of pH, conductivity, constant residuals, corrosion products, Cl - and O 2 concentration. The IAEA recommends values of 1 μS/cm, but values up to 2 μS/cm might be accepted if the chlorine, copper and sulphate concentrations are very low. To maintain these parameters of the water in compliance with IAEA recommendations, it was designed and realised a filtration installation for the distilled water produced at the reactor. Till this installation will be assembled the water chemistry is

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.

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)

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)

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.

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.)

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)

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

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

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)

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

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.

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

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)

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

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)

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

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)

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.

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

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)

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

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)

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

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

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

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

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)

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

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

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).

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

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 Battle of Moscow - Turning Point of World War II

Directory of Open Access Journals (Sweden)

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.

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.

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...

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

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

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

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

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

Sanitary-epidemiological assessment of quality of atmospheric air in Moscow

Directory of Open Access Journals (Sweden)

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

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.

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)

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

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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.

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

Exarh of the Bulgarian Church metropolitan Stephen and the Moscow Patriarchy

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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

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)

Moscow and St. Petersburgpsychological schools: from opposition to friendship

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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.

Chemical compatibility issues associated with use of SiC/SiC in advanced reactor concepts

Energy Technology Data Exchange (ETDEWEB)

Wilson, Dane F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-09-01

Silicon carbide/silicon carbide (SiC/SiC) composites are of interest for components that will experience high radiation fields in the High Temperature Gas Cooled Reactor (HTGR), the Very High Temperature Reactor (VHTR), the Sodium Fast Reactor (SFR), or the Fluoride-cooled High-temperature Reactor (FHR). In all of the reactor systems considered, reactions of SiC/SiC composites with the constituents of the coolant determine suitability of materials of construction. The material of interest is nuclear grade SiC/SiC composites, which consist of a SiC matrix [high-purity, chemical vapor deposition (CVD) SiC or liquid phase-sintered SiC that is crystalline beta-phase SiC containing small amounts of alumina-yttria impurity], a pyrolytic carbon interphase, and somewhat impure yet crystalline beta-phase SiC fibers. The interphase and fiber components may or may not be exposed, at least initially, to the reactor coolant. The chemical compatibility of SiC/SiC composites in the three reactor environments is highly dependent on thermodynamic stability with the pure coolant, and on reactions with impurities present in the environment including any ingress of oxygen and moisture. In general, there is a dearth of information on the performance of SiC in these environments. While there is little to no excess Si present in the new SiC/SiC composites, the reaction of Si with O₂ cannot be ignored, especially for the FHR, in which environment the product, SiO₂, can be readily removed by the fluoride salt. In all systems, reaction of the carbon interphase layer with oxygen is possible especially under abnormal conditions such as loss of coolant (resulting in increased temperature), and air and/ or steam ingress. A global outline of an approach to resolving SiC/SiC chemical compatibility concerns with the environments of the three reactors is presented along with ideas to quickly determine the baseline compatibility performance of SiC/SiC.

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

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

Science.gov (United States)

Belova, Iya; Ginzburg, Alexander

2010-05-01

Urbanization, particularly with respect to its sustainability, remains to be a great challenge in all regions of the world. Urbanization has an influence on soils, hydrology, and climate, these changes have effect on global climate, pollution, increase of anthropogenic greenhouse gases in the earth's atmosphere and human health. Thus anthropogenic heat flux is an important factor for estimation of development of global climate. The simple formula for anthropogenic heat fluxes (AHF) was proposed in the EGU General Assembly 2008 presentation [1] AHF = k × PD × EC, were PD is urban population density and EC is total energy consumption per capita. It was estimated that two of the world megacities - Seoul and Moscow - have the highest AHF values - 83 and 56 W/m2 correspondently. In presented paper it was studied the reasons of such high anthropogenic heat fluxes within Moscow region as well as AHF over the major Russian cities. It was shown that main reason of this circumstance is the administrative divisions in Moscow region. Moscow is ringed by Moscow circle motor road. Accordingly the city has sharply defined boundaries and densely populated residential suburbs are cut off and don't included in Moscow city administrative area. It was constructed the special graph to illuminate why Moscow city has such a high anthropogenic heat factor and how much Moscow agglomeration AHF could be if consider not only Moscow city itself but also the nearest suburb towns. Using the data from World Bank [2] and Russian governmental statistic agency [3] anthropogenic heat fluxes for Russian cities with population more than 500 000 were estimated. Energy consumption data for different Russian regions were calculated by special routine using in the Web-atlas [4]. This research is supported by RAS Fundamental Research Project 'Influence of anthropogenic heat fluxes and aerosol pollution on heat balance and climate of urbanized areas'. Other results of this project is presented in paper [5

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%

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

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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.

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

Prometheus Reactor I&C Software Development Methodology, for Action

Energy Technology Data Exchange (ETDEWEB)

T. Hamilton

2005-07-30

The purpose of this letter is to submit the Reactor Instrumentation and Control (I&C) software life cycle, development methodology, and programming language selections and rationale for project Prometheus to NR for approval. This letter also provides the draft Reactor I&C Software Development Process Manual and Reactor Module Software Development Plan to NR for information.

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)

[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.

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

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...

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

[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

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

Directory of Open Access Journals (Sweden)

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.

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.

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)

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 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

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)

Prometheus Reactor I and C Software Development Methodology, for Action

International Nuclear Information System (INIS)

T. Hamilton

2005-01-01

The purpose of this letter is to submit the Reactor Instrumentation and Control (I and C) software life cycle, development methodology, and programming language selections and rationale for project Prometheus to NR for approval. This letter also provides the draft Reactor I and C Software Development Process Manual and Reactor Module Software Development Plan to NR for information

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

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)

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

Directory of Open Access Journals (Sweden)

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.

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

C-Reactor I and E loading instability limits

Energy Technology Data Exchange (ETDEWEB)

Hess, K.W.

1957-01-24

The pilot charging of I & E fuel elements has been implemented at C-Reactor under Production Test IP-19-A. It was necessary to provide adequate tube protection against flow interruption by establishing proper trip setting on the Panellit pressure gauges. the administration of these Panellit trip settings is done by trip-before- boiling tube outlet temperature limits, which are similar in principle to the current instability limits. Trip-before-boiling limits for C-Reactor I & E fuel elements loadings are presented in this document.

“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...

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

Directory of Open Access Journals (Sweden)

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.

Tasks for development of SiC/SiC composites as structural material in a fusion reactor

International Nuclear Information System (INIS)

Yamada, Reiji

1997-01-01

SiC/SiC composites are chosen for a structural material of blankets in DREAM Reactor that has been proposed as a power reactor by JAERI. The main requirements and the target values in the DREAM conceptual design were described, and compared to available experimental data. (author)

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

Prototype tokamak fusion reactor based on SiC/SiC composite material focusing on easy maintenance

International Nuclear Information System (INIS)

Nishio, S.; Ueda, S.; Kurihara, R.; Kuroda, T.; Miura, H.; Sako, K.; Takase, H.; Seki, Y.; Adachi, J.; Yamazaki, S.; Hashimoto, T.; Mori, S.; Shinya, K.; Murakami, Y.; Senda, I.; Okano, K.; Asaoka, Y.; Yoshida, T.

2000-01-01

If the major part of the electric power demand is to be supplied by tokamak fusion power plants, the tokamak reactor must have an ultimate goal, i.e. must be excellent in construction cost, safety aspect and operational availability (maintainability and reliability), simultaneously. On way to the ultimate goal, the approach focusing on the safety and the availability (including reliability and maintainability) issues must be the more promising strategy. The tokamak reactor concept with the very high aspect ratio configuration and the structural material of SiC/SiC composite is compatible with this approach, which is called the DRastically Easy Maintenance (DREAM) approach. This is because SiC/SiC composite is a low activation material and an insulation material, and the high aspect ratio configuration leads to a good accessibility for the maintenance machines. As the intermediate steps along this strategy between the experimental reactor such as international thermonuclear experimental reactor (ITER) and the ultimate goal, a prototype reactor and an initial phase commercial reactor have been investigated. Especially for the prototype reactor, the material and technological immaturities are considered. The major features of the prototype and commercial type reactors are as follows. The fusion powers of the prototype and the commercial type are 1.5 and 5.5 GW, respectively. The major/minor radii for the prototype and the commercial type are of 12/1.5 m and 16/2 m, respectively. The plasma currents for the prototype and the commercial type are 6 and 9.2 MA, respectively. The coolant is helium gas, and the inlet/outlet temperatures of 500/800 and 600/900 deg. C for the prototype and the commercial type, respectively. The thermal efficiencies of 42 and 50% are obtainable in the prototype and the commercial type, respectively. The maximum toroidal field strengths of 18 and 20 tesla are assumed in the prototype and the commercial type, respectively. The thermal

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

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. 

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

Nuclear design for high temperature gas cooled reactor (GTHTR300C) using MOX fuel

International Nuclear Information System (INIS)

Mouri, Tomoaki; Kunitomi, Kazuhiko

2008-01-01

A design study of the hydrogen cogeneration high temperature gas cooled reactor (GTHTR300C) that can produce both electricity and hydrogen has been carried out in Japan Atomic Energy Agency. The GTHTR300C is the system with thermal power of 600MW and reactor outlet temperature of 950degC, which is expected to supply the hydrogen to fuel cell vehicles after 2020s. In future, the full deployment of fast reactor cycle without natural uranium will demand the use of Mixed-Oxide (MOX) fuels in the GTHTR300C. Therefore, a nuclear design was performed to confirm the feasibility of the reactor core using MOX fuels. The designed reactor core has high performance and meets safety requirements. In this paper, the outline of the GTHTR300C and the nuclear design of the reactor core using MOX fuels are described. (author)

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%.

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)

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.

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

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. 

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...

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

Directory of Open Access Journals (Sweden)

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.

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…

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

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.

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)

Project management plan for Reactor 105-C Interim Safe Storage project

International Nuclear Information System (INIS)

Plagge, H.A.

1996-09-01

Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

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

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.

Building reactor operator sustain expert system with C language integrated production system

International Nuclear Information System (INIS)

Ouyang Qin; Hu Shouyin; Wang Ruipian

2002-01-01

The development of the reactor operator sustain expert system is introduced, the capability of building reactor operator sustain expert system is discussed with C Language Integrated Production System (Clips), and a simple antitype of expert system is illustrated. The limitation of building reactor operator sustain expert system with Clips is also discussed

[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.

Neutronics and thermohydraulics of the reactor C.E.N.E.-Part I; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte I

Energy Technology Data Exchange (ETDEWEB)

Caro, R; Ahnert, C; Naudin, A E; Martinez Fanegas, R; Minguez, E; Rovira, A

1976-07-01

In this report the analysis of neutronics (both statics and kinetics), of the 10 MWt swimming pool reactor C.E.N.E, is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking, carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

Neutronics and thermohydraulics of the reactor C.E.N.E. Part II; Analisis neutronico y termohidraulico del reactor C.E.N.E. Parte II

Energy Technology Data Exchange (ETDEWEB)

Caro, R

1976-07-01

In this report the analysis of neutronics thermohydraulics and shielding of the 10 HWt swimming pool reactor C.E.N.E is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs.

Qualification of SiC materials for fusion and fission reactors

International Nuclear Information System (INIS)

Ryazanov, Alexander

2009-01-01

Ceramic materials such as silicon carbide (SiC) and SiC/SiC composites are both considered, due to their high-temperature strength, pseudo-ductile fracture behavior and low-induced radioactivity, as candidate materials for fusion reactor (test blanket module for ITER) and high temperature gas-cooled reactors (HTGR). The radiation swelling and creep of SiC are very important physical phenomena that determine the radiation resistance of them in these reactors. Other important problem which exists especially in fusion reactor is an effect of accumulation of high concentrations of helium atoms in SiC (up to 15000-20000 at.ppm) due to (n,α) nuclear reaction on physical mechanical properties. An understanding of the physical mechanism of this phenomenon is very important for the investigations of helium atom effect on radiation swelling in SiC. In this report a compilation of non-irradiated and irradiated properties of SiC are provided and analyzed in terms of their application to fusion and high temperature gas cooled reactors. Special topic of this report is oriented on the micro structural changes in chemically vapor-deposited (CVD) high-purity beta-SiC during neutron and ion irradiations at elevated temperatures. The evolutions of various radiation induced defects including dislocation loops, network dislocations and cavities are presented here as a function of irradiation temperature and fluencies. These observations are discussed in relation with such irradiation phenomena in SiC as low temperature swelling and cavity swelling. One of the main difficulties in the radiation damage studies of SiC materials lies in the absence of theoretical models and interpretation of many physical mechanisms of radiation phenomena including the radiation swelling and creep. The point defects in ceramic materials are characterized by the charge states and they can have an effective charge. The internal effective electrical field is formed due to the accumulation of charged point

Characterization of 14C in Swedish light water reactors.

Science.gov (United States)

Magnusson, Asa; Aronsson, Per-Olof; Lundgren, Klas; Stenström, Kristina

2008-08-01

This paper presents the results of a 4-y investigation of 14C in different waste streams of both boiling water reactors (BWRs) and pressurized water reactors (PWRs). Due to the potential impact of 14C on human health, minimizing waste and releases from the nuclear power industry is of considerable interest. The experimental data and conclusions may be implemented to select appropriate waste management strategies and practices at reactor units and disposal facilities. Organic and inorganic 14C in spent ion exchange resins, process water systems, ejector off-gas and replaced steam generator tubes were analyzed using a recently developed extraction method. Separate analysis of the chemical species is of importance in order to model and predict the fate of 14C within process systems as well as in dose calculations for disposal facilities. By combining the results of this investigation with newly calculated production rates, mass balance assessments were made of the 14C originating from production in the coolant. Of the 14C formed in the coolant of BWRs, 0.6-0.8% was found to be accumulated in the ion exchange resins (core-specific production rate in the coolant of a 2,500 MWth BWR calculated to be 580 GBq GW(e)(-1) y(-1)). The corresponding value for PWRs was 6-10% (production rate in a 2,775 MWth PWR calculated to be 350 GBq GW(e)(-1) y(-1)). The 14C released with liquid discharges was found to be insignificant, constituting less than 0.5% of the production in the coolant. The stack releases, routinely measured at the power plants, were found to correspond to 60-155% of the calculated coolant production, with large variations between the BWR units.

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.

A new SiC/C bulk FGM for fusion reactor

International Nuclear Information System (INIS)

Changchun, G.; Anhua, W.; Wenbin, C.; Jiangtao, L.

2001-01-01

Graphite is widely used in present Tokamak facilities and a C/C composite has been selected as one of the candidate materials for the ITER. But C-based material has an excessive chemical sputtering yield at 600-1000 K and exhibits irradiation enhanced sublimation at >1200 K under plasma erosion condition, causing serious C-contamination of plasma. Low Z material SiC has several advantages for use in fusion reactor, such as excellent high temperature properties, corrosion resistance, low density, and especially its low activation irradiation. To reduce C contamination during plasma exposure, previously SiC coatings were chemically deposited on the surface of C-substrate, however, the thermal stresses arise on the interface between the coating layers and the substrate under high temperature. Heating/cooling cycle leading to cracks in SiC/C interface, small thickness of coating and long processing time are limiting factors for FGM made with CVD process. In this paper, a new SiC/C bulk FGM has been successfully fabricated with P/M hot pressing process. The chemical sputtering yield, gas desorption performance, thermal shock resistance and physical sputtering performance in Tokamak are outlined in this paper. (author)

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

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)

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

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.)

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

[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...

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...

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)

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.

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

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

The determination of neutron energy spectrum in reactor core C1 of reactor VR-1 Sparrow

Energy Technology Data Exchange (ETDEWEB)

Vins, M. [Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University, V Holesovickach 2, 180 00 Prague 8 (Czech Republic)], E-mail: vinsmiro@seznam.cz

2008-07-15

This contribution overviews neutron spectrum measurement, which was done on training reactor VR-1 Sparrow with a new nuclear fuel. Former nuclear fuel IRT-3M was changed for current nuclear fuel IRT-4M with lower enrichment of 235U (enrichment was reduced from former 36% to 20%) in terms of Reduced Enrichment for Research and Test Reactors (RERTR) Program. Neutron spectrum measurement was obtained by irradiation of activation foils at the end of pipe of rabit system and consecutive deconvolution of obtained saturated activities. Deconvolution was performed by computer iterative code SAND-II with 620 groups' structure. All gamma measurements were performed on Canberra HPGe. Activation foils were chosen according physical and nuclear parameters from the set of certificated foils. The Resulting differential flux at the end of pipe of rabit system agreed well with typical spectrum of light water reactor. Measurement of neutron spectrum has brought better knowledge about new reactor core C1 and improved methodology of activation measurement. (author)

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

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. 

IMPROVING SYSTEMS OF POWER COLLECTION OF THE MOSCOW MONORAIL TRANSPORT SYSTEM

Directory of Open Access Journals (Sweden)

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.

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

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.

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

Production and release of {sup 14}C from a swimming pool reactor

Energy Technology Data Exchange (ETDEWEB)

Krishnamoorthy, T M [Bhabha Atomic Research Centre, Mumbai (India). Environmental Assessment Div.; Sadarangani, S H [Bhabha Atomic Research Centre, Mumbai (India). Radiation Safety Systems Div.; Doshi, G R [Bhabha Atomic Research Centre, Bombay (India). Health Physics Div.

1994-04-01

The annual production rate of {sup 14}C in the Apsara swimming pool reactor works out to be about 2.94 mCi. The concentration distribution of {sup 14}C in different compartments viz. pool water, reactor hall air and ion-exchange resin ranged from 200 to 440 pCi/l, 0.09 to 0.38 pCi/l, an average concentration of 8.16 pCi/g respectively. The mean residence time of {sup 14}C in pool water is evaluated to be about 7 days taking into account various sinks. The study revealed atmospheric exchange at the air-water interface as the dominant process responsible for the loss of {sup 14}C from the pool water. (author). 7 refs., 2 figs., 4 tabs.

Upgrade of VR-1 training reactor I and C

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Chab, V.

2003-01-01

The contribution describes the upgrade of the VR-1 training reactor I and C (Instrumentation and Control). The reactor was put into operation in the 1990, and its I and C seems to be obsolete now. The new I and C utilises the same digital technology as the old one. The upgrade has been done gradually during holidays in order not to disturb the reactor utilisation during teaching and training. The first stage consisted in the human-machine interface and the control room upgrade in 2001. A new operator's desk, displays, indicators and buttons were installed. Completely new software and communication interface to the present I and C were developed. During the second stage in 2002, new control rod drivers and safety circuits were installed. The rod motors were replaced and necessary mechanical changes on the control rod mechanism, induced by the utilisation of the new motor, were done. The new safety circuits utilise high quality relays with forced contacts to guarantee high reliability of their operation. The third stage, the control system upgrade is being carried out now. The new control system is based on an industrial PC mounted in a 19 inch crate. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. A large amount of work has been devoted to the software requirements to specify all dependencies, modes and permitted actions, safety measures, etc. The Department took an active part in the setting of software requirements and later in verification and validation of the software and the whole control system. Finally, a new protection system consisting of power measuring and power protection channels will be installed in 2004 or 2005. (author)

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

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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”

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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.

Determination of the NPP Krsko reactor core safety limits using the COBRA-III-C code

International Nuclear Information System (INIS)

Lajtman, S.; Feretic, D.; Debrecin, N.

1989-01-01

This paper presents the NPP Krsko reactor core safety limits determined by the COBRA-III-C code, along with the methodology used. The reactor core safety limits determination is a part of reactor protection limits procedure. The results obtained were compared to safety limits presented in NPP Krsko FSAR. The COBRA-III-C NPP Krsko design core steady state thermal hydraulics calculation, used as the basis for the safety limits calculation, is presented as well. (author)

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.

Engineering and planning for reactor 105-C interim safe storage project subcontract no. 0100C-SC-G0001 conceptual design report. Volume 1

International Nuclear Information System (INIS)

1996-04-01

The 105-C Reactor, one of eight surplus production reactors at the Hanford Site, has been proposed by the U.S. Department of Energy, Richland, Operations Office to be the first large-scale technology demonstration project in the decontamination and decommissioning (D ampersand D) focus area as part of the project for dismantlement and interim safe storage. The 105-C Reactor will be placed in an interim safe storage condition, then undergo the decontamination and decommissioning phase. After D ampersand D, the reactor will be placed in long- term safe storage. This report provides the conceptual design for these activities

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

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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.

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

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L. G. Moiseykina

2017-01-01

Full Text Available Purpose of the study. The fuel and energy complex is one of the important components of the mechanism of functioning of the national economy in general and municipal economy in particular, since the main tasks of the complex include: provision of hot water supply all year round and heat during the winter period, meeting the needs of the population and municipal economy in gas, supply of gasoline and diesel fuel to satisfy consumers, as well as the supply of coal, peat, fuel oil and other fuels for the urban economy. An important role is played by enterprises of the fuel and energy complex in terms of providing jobs to the population. The fuel and energy complex of Moscow is one of the largest in Russia. A feature of its functioning is the concentrated consumption of gas, fuel, electricity, heat energy and other energy resources. The formation and development of the fuel and energy complex in Moscow is largely due to the rapidly developing economy of the megapolis – large-scale construction of housing and infrastructure, sustainable population growth entails a constant increase in consumption of fuel and energy resources. Monitoring the efficiency of the use of fuel and energy resources makes it possible to identify ways to reduce the volume of consumption to a level that allows, within the approved limit, to implement the planned rate of social and economic development of the city. Materials and methods. Information base of the research was made by statistical data characterizing the volume of consumption of certain types of fuel and energy resources in the market of the Moscow region. The methodological basis of the study is made up of statistical methods of analysis of structure and structural shifts, dynamics. Their use made it possible to conduct a thorough analysis of the differentiation of consumption of various types of fuel and energy resources, as well as structural changes in the differentiations in question. It made it possible to

Joining of SiCf/SiC composites for thermonuclear fusion reactors

International Nuclear Information System (INIS)

Ferraris, M.; Badini, C.; Montorsi, M.; Appendino, P.; Scholz, H.W.

1994-01-01

Due to their favourable radiological behaviour, SiC f /SiC composites are promising structural materials for future use in fusion reactors. A problem to cope with is the joining of the ceramic composite material (CMC) to itself for more complex structures. Maintenance concepts for a reactor made of SiC f /SiC will demand a method of joining. The joining agents should comply with the low-activation approach of the base material. With the acceptable elements Si and Mg, sandwich structures of composite/metal/composite were prepared in Ar atmosphere at temperatures just above the melting points of the metals. Another promising route is the use of joining agents of boro-silicate glasses: their composition can be tailored to obtain softening temperatures of interest for fusion applications. The glassy joint can be easily ceramised to improve thermomechanical properties. The joining interfaces were investigated by SEM-EDS, XRD and mechanical tests. ((orig.))

Calibration of new I and C at VR-1 training reactor

International Nuclear Information System (INIS)

Kropik, Martin; Jurickova, Monika

2011-01-01

The paper describes a calibration of the new instrumentation and control (I and C) at the VR-1 training reactor in Prague. The I and C uses uncompensated fission chambers for the power measurement that operate in a pulse or a DC current and a Campbell regime, according to the reactor power. The pulse regime uses discrimination for the avoidance of gamma and noise influence of the measurement. The DC current regime employs a logarithmic amplifier to cover the whole reactor DC current power range with only one electronic circuit. The system computer calculates the real power from the logarithmic data. The Campbell regime is based on evaluation of the root mean square (RMS) value of the neutron noise. The calculated power from Campbell range is based on the square value of the RMS neutron noise data. All data for the power calculation are stored in computer flash memories. To set proper data there, it was necessary to carry out the calibration of the I and C. At first, the proper discrimination value was found while examining the spectrum of the neutron signal from the chamber. The constants for the DC current and Campbell calculations were determined from an independent reactor power measurement. The independent power measuring system that was used for the calibration was accomplished by a compensated current chamber with an electrometer. The calculated calibration constants were stored in the computer flash memories, and the calibrated system was again successfully compared with the independent power measuring system. Finally, proper gamma discrimination of the Campbell system was carefully checked.

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

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)

Neutronics and thermohydraulics of the reactor C.E.N.E. Pt. 1

International Nuclear Information System (INIS)

Caro, R.; Ahnert, C.; Esteban Naudin, A.; Martinez Fanegas, R.; Minguez, E.; Rovira, A.

1976-01-01

The analysis of neutronics (both statics and kinetics), of the 10 Mwt swimming pool reactor C.E.N.E. is included. A short description of the theoretical model used, along with the theoretical versus experimental cheking, carried out, whenever possible, with the reactors JEN-1 and JEN-2 of Junta de Energia Nuclear, is given in each of these chapters. (author) [es

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.)

Project management plan for the 105-C Reactor interim safe storage project. Revision 1

International Nuclear Information System (INIS)

Miller, R.L.

1997-01-01

In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

Advanced Reactor Licensing: Experience with Digital I&C Technology in Evolutionary Plants

Energy Technology Data Exchange (ETDEWEB)

Wood, RT

2004-09-27

This report presents the findings from a study of experience with digital instrumentation and controls (I&C) technology in evolutionary nuclear power plants. In particular, this study evaluated regulatory approaches employed by the international nuclear power community for licensing advanced l&C systems and identified lessons learned. The report (1) gives an overview of the modern l&C technologies employed at numerous evolutionary nuclear power plants, (2) identifies performance experience derived from those applications, (3) discusses regulatory processes employed and issues that have arisen, (4) captures lessons learned from performance and regulatory experience, (5) suggests anticipated issues that may arise from international near-term deployment of reactor concepts, and (6) offers conclusions and recommendations for potential activities to support advanced reactor licensing in the United States.

Physicochemical interactions resulting from the use of a SiC/SiC composite material in typical environments of future nuclear reactors

International Nuclear Information System (INIS)

Braun, James

2014-01-01

The development of high purity SiC fibers during the nineties has led to their consideration as nuclear reactors components through the use of SiC/SiC composites. SiC and SiC/SiC composites are considered as core materials of future nuclear reactors (SFR, GFR) and as a potential replacement for the zirconium cladding of PWR. Therefore, the thermochemical compatibility of these materials with typical environments of those nuclear reactors has been studied. The composition and the growth kinetics of the reaction zone of SiC towards niobium and tantalum (considered as materials to ensure the leak-tightness of a SiC/SiC cladding for GFR) have been studied between 1050 and 1500 C. High temperature heat treatments in open and closed systems between SiC and UO 2 have shown a significant reactivity over 1200 C characterized by the formation of CO and uranium silicides. Moreover, a liquid phase has been detected between 1500 and 1650 C. The exposure of SiC/SiC to liquid sodium (550 C, up to 2000 h) has been studied as a function of the oxygen concentration dissolved in liquid sodium. An improvement of the mechanical properties of the composites elaborated for this study (increase of the tensile strength and strain at failure) has been highlighted after immersion in the liquid sodium independently of its oxygen concentration. It is believed that this phenomenon is due to the presence of residual sodium in the material. (author) [fr

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

Neutronics and thermohydraulics of the reactor C.E.N.E. Part II

International Nuclear Information System (INIS)

Caro, R.

1976-01-01

In this report the analysis of neutronics thermohydraulics and shielding of the 10 HWt swimming pool reactor C.E.N.E is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs

Neutronics and thermohydraulics of the reactor C.E.N.E.-Part I

International Nuclear Information System (INIS)

Caro, R.; Ahnert, C.; Naudin, A. E.; Martinez Fanegas, R.; Minguez, E.; Rovira, A.

1976-01-01

In this report the analysis of neutronics (both statics and kinetics), of the 10 MWt swimming pool reactor C.E.N.E, is included. In each of these chapters is given a short description of the theoretical model used, along with the theoretical versus experimental checking, carried out, whenever possible, with the reactors JEN-I and JEN-II of Junta de Energia Nuclear. (Author) 11 refs

Carbon balance of the typical grain crop rotation in Moscow region assessed by eddy covariance method

Science.gov (United States)

Meshalkina, Joulia; Yaroslavtsev, Alexis; Vassenev, Ivan

2017-04-01

Croplands could have equal or even greater net ecosystem production than several natural ecosystems (Hollinger et al., 2004), so agriculture plays a substantial role in mitigation strategies for the reduction of carbon dioxide emissions. In Central Russia, where agricultural soils carbon loses are 9 time higher than natural (forest's) soils ones (Stolbovoi, 2002), the reduction of carbon dioxide emissions in agroecosystems must be the central focus of the scientific efforts. Although the balance of the CO2 mostly attributed to management practices, limited information exists regarding the crop rotation overall as potential of C sequestration. In this study, we present data on carbon balance of the typical grain crop rotation in Moscow region followed for 4 years by measuring CO2 fluxes by paired eddy covariance stations (EC). The study was conducted at the Precision Farming Experimental Fields of the Russian Timiryazev State Agricultural University, Moscow, Russia. The experimental site has a temperate and continental climate and situated in south taiga zone with Arable Sod-Podzoluvisols (Albeluvisols Umbric). Two fields of the four-course rotation were studied in 2013-2016. Crop rotation included winter wheat (Triticum sativum L.), barley (Hordeum vulgare L.), potato crop (Solanum tuberosum L.) and cereal-legume mixture (Vicia sativa L. and Avena sativa L.). Crops sowing occurred during the period from mid-April to mid-May depending on weather conditions. Winter wheat was sown in the very beginning of September and the next year it occurred from under the snow in the phase of tillering. White mustard (Sinapis alba) was sown for green manure after harvesting winter wheat in mid of July. Barley was harvested in mid of August, potato crop was harvested in September. Cereal-legume mixture on herbage was collected depending on the weather from early July to mid-August. Carbon uptake (NEE negative values) was registered only for the fields with winter wheat and white

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Spent fuel, high-level radioactive waste, or reactor... RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.108 Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation. The...

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

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 ...

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.

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...

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

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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.

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.

Performance and microbial community composition dynamics of aerobic granular sludge from sequencing batch bubble column reactors operated at 20 degrees C, 30 degrees C, and 35 degrees C.

Science.gov (United States)

Ebrahimi, Sirous; Gabus, Sébastien; Rohrbach-Brandt, Emmanuelle; Hosseini, Maryam; Rossi, Pierre; Maillard, Julien; Holliger, Christof

2010-07-01

Two bubble column sequencing batch reactors fed with an artificial wastewater were operated at 20 degrees C, 30 degrees C, and 35 degrees C. In a first stage, stable granules were obtained at 20 degrees C, whereas fluffy structures were observed at 30 degrees C. Molecular analysis revealed high abundance of the operational taxonomic unit 208 (OTU 208) affiliating with filamentous bacteria Leptothrix spp. at 30 degrees C, an OTU much less abundant at 20 degrees C. The granular sludge obtained at 20 degrees C was used for the second stage during which one reactor was maintained at 20 degrees C and the second operated at 30 degrees C and 35 degrees C after prior gradual increase of temperature. Aerobic granular sludge with similar physical properties developed in both reactors but it had different nutrient elimination performances and microbial communities. At 20 degrees C, acetate was consumed during anaerobic feeding, and biological phosphorous removal was observed when Rhodocyclaceae-affiliating OTU 214 was present. At 30 degrees C and 35 degrees C, acetate was mainly consumed during aeration and phosphorous removal was insignificant. OTU 214 was almost absent but the Gammaproteobacteria-affiliating OTU 239 was more abundant than at 20 degrees C. Aerobic granular sludge at all temperatures contained abundantly the OTUs 224 and 289 affiliating with Sphingomonadaceae indicating that this bacterial family played an important role in maintaining stable granular structures.

Irradiation capsule for testing magnetic fusion reactor first-wall materials at 60 and 2000C

International Nuclear Information System (INIS)

Conlin, J.A.

1985-08-01

A new type of irradiation capsule has been designed, and a prototype has been tested in the Oak Ridge Research Reactor (ORR) for low-temperature irradiation of Magnetic Fusion Reactor first-wall materials. The capsule meets the requirements of the joint US/Japanese collaborative fusion reactor materials irradiation program for the irradiation of first-wall fusion reactor materials at 60 and 200 0 C. The design description and results of the prototype capsule performance are presented

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

Directory of Open Access Journals (Sweden)

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.

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)

Study on Optimization of I and C Architecture for Research Reactors Using Bayesian Networks

Energy Technology Data Exchange (ETDEWEB)

Rahman, Khaili Ur; Shin, Jinsoo; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of)

2013-07-01

The optimization in terms of redundancy of modules and components in Instrumentation and Control (I and C) architecture is based on cost and availability assuming regulatory requirements are satisfied. The motive of this study is to find an optimized I and C architecture, either in hybrid formation, fully digital or analog, with respect to system availability and relative cost of architecture. The cost of research reactors I and C systems is prone to have effect on marketing competitiveness. As a demonstrative example, the reactor protection system of research reactors is selected. The four cases with different architecture formation were developed with single and double redundancy of bi-stable modules, coincidence processor module, and safety or protection circuit actuation logic. The architecture configurations are transformed to reliability block diagram (RBD) based on logical operation and function of modules. A Bayesian Network (BN) model is constructed from RBD to assess availability. The cost estimation was proposed and reliability cost index RI was suggested.

Study on Optimization of I and C Architecture for Research Reactors Using Bayesian Networks

International Nuclear Information System (INIS)

Rahman, Khaili Ur; Shin, Jinsoo; Heo, Gyunyoung

2013-01-01

The optimization in terms of redundancy of modules and components in Instrumentation and Control (I and C) architecture is based on cost and availability assuming regulatory requirements are satisfied. The motive of this study is to find an optimized I and C architecture, either in hybrid formation, fully digital or analog, with respect to system availability and relative cost of architecture. The cost of research reactors I and C systems is prone to have effect on marketing competitiveness. As a demonstrative example, the reactor protection system of research reactors is selected. The four cases with different architecture formation were developed with single and double redundancy of bi-stable modules, coincidence processor module, and safety or protection circuit actuation logic. The architecture configurations are transformed to reliability block diagram (RBD) based on logical operation and function of modules. A Bayesian Network (BN) model is constructed from RBD to assess availability. The cost estimation was proposed and reliability cost index RI was suggested

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

Basic safety principles of KLT-40C reactor plants

International Nuclear Information System (INIS)

Beliaev, V.; Polunichev, V.

2000-01-01

The KLT-40 NSSS has been developed for a floating power block of a nuclear heat and power station on the basis of ice-breaker-type NSSS (Nuclear Steam Supply System) with application of shipbuilding technologies. Basic reactor plant components are pressurised water reactor, once-through coil-type steam generator, primary coolant pump, emergency protection rod drive mechanisms of compensate group-electromechanical type. Basic RP components are incorporated in a compact steam generating block which is arranged within metal-water shielding tank's caissons. Domestic regulatory documents on safety were used for the NSSS design. IAEA recommendations were also taken into account. Implementation of basic safety principles adopted presently for nuclear power allowed application of the KLT-40C plant for a floating power unit of a nuclear co-generation station. (author)

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)

[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.

Experience with safety assessment of digital upgrading of IandC in VVER type reactors

International Nuclear Information System (INIS)

Wach, D.; Mulka, B.; Schnuerer, G.

1997-01-01

The digital upgrading of IandC systems important to safety in WWER type reactors requires a broad expertise in various knowledge fields. The approach of the Institute for safety Technology to the qualification and categorization of safety-critical software systems is highlighted. The role of the Institute in the qualification of the Teleperm XS and the type testing of its components is described. The aspects of the safety assessment of digital IandC systems in WWER type reactors is discussed in some detail. (A.K.)

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)

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

Advanced Reactor Licensing: Experience with Digital I and C Technology in Evolutionary Plants

International Nuclear Information System (INIS)

Wood, RT

2004-01-01

This report presents the findings from a study of experience with digital instrumentation and controls (I and C) technology in evolutionary nuclear power plants. In particular, this study evaluated regulatory approaches employed by the international nuclear power community for licensing advanced l and C systems and identified lessons learned. The report (1) gives an overview of the modern l and C technologies employed at numerous evolutionary nuclear power plants, (2) identifies performance experience derived from those applications, (3) discusses regulatory processes employed and issues that have arisen, (4) captures lessons learned from performance and regulatory experience, (5) suggests anticipated issues that may arise from international near-term deployment of reactor concepts, and (6) offers conclusions and recommendations for potential activities to support advanced reactor licensing in the United States

SiC epitaxial layer growth in a novel multi-wafer VPE reactor

Energy Technology Data Exchange (ETDEWEB)

Burk, A.A. Jr.; O`Loughlin, M.J. [Northrop Grumman Advanced Technology Lab., Baltimore, MD (United States); Mani, S.S. [Northrop Grumman Science and Technology Center, Pittsburgh, PA (United States)

1998-06-01

Preliminary results are presented for SiC epitaxial layer growth employing a unique planetary SiC-VPE reactor. The high-throughput, multi-wafer (7 x 2-inch) reactor, was designed for atmospheric and reduced pressure operation at temperatures up to and exceeding 1600 C. Specular epitaxial layers have been grown in the reactor at growth rates from 3-5 {mu}m/hr. The thickest layer grown to data was 42 {mu}m. The layers exhibit minimum unintentional n-type doping of {proportional_to}1 x 10{sup 15} cm{sup -3}, room temperature mobilities of {proportional_to}1000 cm{sup 2}/Vs, and intentional n-type doping from {proportional_to}5 x 10{sup 15} cm{sup -3} to >1 x 10{sup 19} cm{sup -3}. Intrawafer thickness and doping uniformities of 4% and 7% (standard deviation/mean) have been obtained, respectively, on 35 mm diameter substrates. Recently, 3% thickness uniformity has been demonstrated on a 50 mm substrate. Within a run, wafer-to-wafer thickness deviation is {proportional_to}4-14%. Doping variation is currently larger, ranging as much as a factor of two from the highest to the lowest doped wafer. Continuing efforts to improve the susceptor temperature uniformity and reduce unintentional hydrocarbon generation to improve layer uniformity and reproducibility, are presented. (orig.) 18 refs.

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...

Characterization of 2D-C/C composite for application of very high temperature reactor

International Nuclear Information System (INIS)

Shibata, Taiju; Sumita, Junya; Kunimoto, Eiji; Sawa, Kazuhiro; Makita, Taiyo; Takagi, Takashi; Kim, W.J.; Jung, C.H.; Park, J.Y.

2010-01-01

For in-core components of VHTR (Very High Temperature Reactor), carbon fiber reinforced carbon matrix composite (C/C composite) is one of the major candidate materials. In this study, fracture behaviors of two dimensional (2D-) C/C composites were examined by SENB specimens with four-point bending test. The surface of specimens was observed by a CCD camera during the bending test, and observed by a stereomicroscope before and after the bending test. The following results were obtained through mode-I fracture test. (1) Three types of the composites were evaluated by tentatively using the stress intensity factor equation for metallic materials. The equivalent stress intensity factor of 2D-C/C composite is in the range of 5.9 - 10.0MPa m 1/2 . It was expected that the fracture mechanism for the composite materials could be assessed by this test method. (2) The crack opening displacement-load behavior of C/C composite might depend not only on the propagation of crack but also on delaminating between layers. (author)

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."

105-C Reactor interim safe storage project technology integration plan

International Nuclear Information System (INIS)

Pulsford, S.K.

1997-01-01

The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

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

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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.

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

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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.

Study of the obtainment of Mo_2C by gas-solid reaction in a fixed and rotary bed reactor

International Nuclear Information System (INIS)

Araujo, C.P.B. de; Souza, C.P. de; Souto, M.V.M.; Barbosa, C.M.; Frota, A.V.V.M.

2016-01-01

Carbides' synthesis via gas-solid reaction overcomes many of the difficulties found in other processes, requiring lower temperatures and reaction times than traditional metallurgic routes, for example. In carbides' synthesis in fixed bed reactors (FB) the solid precursor is permeated by the reducing/carburizing gas stream forming a packed bed without mobility. The use of a rotary kiln reactor (RK) adds a mixing character to this process, changing its fluid-particle dynamics. In this work ammonium molybdate was subjected to carbo-reduction reaction (CH4 / H2) in both reactors under the same gas flow (15L / h) and temperature (660 ° C) for 180 minutes. Complete conversion was observed Mo2C (dp = 18.9nm modal particles sizes' distribution) in the fixed bed reactor. In the RK reactor this conversion was only partial (∼ 40%) and Mo2C and MoO3 (34nm dp = bimodal) could be observed on the produced XRD pattern. Partial conversion was attributed to the need to use higher solids loading in the reactor CR (50% higher) to avoid solids to centrifuge. (author)

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.

Development prospects of keratoplasty in Moscow

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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.

Creep crack growth in a reactor pressure vessel steel at 360 deg C

Energy Technology Data Exchange (ETDEWEB)

Wu, Rui; Seitisleam, F; Sandstroem, R [Swedish Institute for Metals Research, Stockholm (Sweden)

1999-12-31

Plain creep (PC) and creep crack growth (CCG) tests at 360 deg C and post metallography were carried out on a low alloy reactor pressure vessel steel (ASTM A508 class 2) with different microstructures. Lives for the CCG tests were shorter than those for the PC tests and this is more pronounced for simulated heat affected zone microstructure than for the parent metal at longer lives. For the CCG tests, after initiation, the cracks grew constantly and intergranularly before they accelerated to approach rupture. The creep crack growth rate is well described by C*. The relations between reference stress, failure time and steady crack growth rate are presented for the CCG tests. It is demonstrated that the failure stress due to CCG is considerably lower than the yield stress at 360 deg C. Consequently, the CCG will control the static strength of a reactor vessel. (orig.) 17 refs.

Creep crack growth in a reactor pressure vessel steel at 360 deg C

Energy Technology Data Exchange (ETDEWEB)

Rui Wu; Seitisleam, F.; Sandstroem, R. [Swedish Institute for Metals Research, Stockholm (Sweden)

1998-12-31

Plain creep (PC) and creep crack growth (CCG) tests at 360 deg C and post metallography were carried out on a low alloy reactor pressure vessel steel (ASTM A508 class 2) with different microstructures. Lives for the CCG tests were shorter than those for the PC tests and this is more pronounced for simulated heat affected zone microstructure than for the parent metal at longer lives. For the CCG tests, after initiation, the cracks grew constantly and intergranularly before they accelerated to approach rupture. The creep crack growth rate is well described by C*. The relations between reference stress, failure time and steady crack growth rate are presented for the CCG tests. It is demonstrated that the failure stress due to CCG is considerably lower than the yield stress at 360 deg C. Consequently, the CCG will control the static strength of a reactor vessel. (orig.) 17 refs.

Use of radiation technologies in agriculture and medicine

International Nuclear Information System (INIS)

Petukhov, V.K.; Chekushin, A.I.

1994-01-01

The most important directions of radiation and radiation biological technologies in the agriculture and medicine are elucidated. Kazakstan have possibility for application radiation technologies. There is powerful irradiation plant on the base of WWR-K reactor such could use for medicine materials sterilization. Has been proposed gamma-radiation plant with following technical characteristics: sources activity - 100-120 Ku; effective energy of radiation - 0,6-0,7 MeV; gamma-radiation use coefficient - 35 %; irradiation dose rate - 30-40 R/c; nonuniform irradiation rate - 12 %. Processing tools have being situated to hermetically sealed cylindrical container (height - 2 m; diameter - 1,2 m) and then have being put down under water towards gamma-irradiators

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

Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C

Science.gov (United States)

Yang, Yong; Chen, Yiren; Huang, Yina; Allen, Todd; Rao, Appajosula

Reactor internal components are subjected to neutron irradiation in light water reactors, and with the aging of nuclear power plants around the world, irradiation-induced material degradations are of concern for reactor internals. Irradiation-induced defects resulting from displacement damage are critical for understanding degradation in structural materials. In the present work, microstructural changes due to irradiation in austenitic stainless steels and cast steels were characterized using transmission electron microscopy. The specimens were irradiated in the BOR-60 reactor, a fast breeder reactor, up to 40 dpa at 320°C. The dose rate was approximately 9.4x10-7 dpa/s. Void swelling and irradiation defects were analyzed for these specimens. A high density of faulted loops dominated the irradiated-altered microstructures. Along with previous TEM results, a dose dependence of the defect structure was established at 320°C.

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

Thermophilic (55 - 65°C) and extreme thermophilic (70 - 80°C) sulfate reduction in methanol and formate-fed UASB reactors

NARCIS (Netherlands)

Vallero, M.V.G.; Camarero, E.; Lettinga, G.; Lens, P.N.L.

2004-01-01

The feasibility of thermophilic (55-65 degreesC) and extreme thermophilic (70-80 degreesC) sulfate-reducing processes was investigated in three lab-scale upflow anaerobic sludge bed (UASB) reactors fed with either methanol or formate as the sole substrates and inoculated with mesophilic granular

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)

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.)

Surveillance and Maintenance Plan for the 105-C Reactor Safe Storage Enclosure

International Nuclear Information System (INIS)

Logan, T. E.

1998-01-01

This document provides a plan for implementing surveillance and maintenance activities to ensure that the 105-C Reactor Safe Storage Enclosure is maintained in a safe, environmentally secure, and cost-effective manner until subsequent closure during the final disposition phase of decommissioning

Phospholipase C-catalyzed sphingomyelin hydrolysis in a membrane reactor for ceramide production

DEFF Research Database (Denmark)

Zhang, Long; Liang, Shanshan; Hellgren, Lars

2008-01-01

A membrane reactor for the production of ceramide through sphingomyelin hydrolysis with phospholipase C from Clostridium perfringens was studied for the first time. Ceramide has raised a large interest as an active component in both pharmaceutical and cosmetic industry. The enzymatic hydrolysis...

[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.

Design issues on using FPGA-based I and C systems in nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Farias, Marcos S.; Carvalho, Paulo Victor R. de; Santos, Isaac Jose A.L. dos; Lacerda, Fabio de, E-mail: msantana@ien.gov.br, E-mail: paulov@ien.gov.br, E-mail: luquetti@ien.gov.br, E-mail: acerda@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Engenharia Nuclear

2015-07-01

The FPGA (field programmable gate array) is widely used in various fields of industry. FPGAs can be used to perform functions that are safety critical and require high reliability, like in automobiles, aircraft control and assistance and mission-critical applications in the aerospace industry. With these merits, FPGAs are receiving increased attention worldwide for application in nuclear plant instrumentation and control (I and C) systems, mainly for Reactor Protection System (RPS). Reasons for this include the fact that conventional analog electronics technologies are become obsolete. I and C systems of new Reactors have been designed to adopt the digital equipment such as PLC (Programmable Logic Controller) and DCS (Distributed Control System). But microprocessors-based systems may not be simply qualified because of its complex characteristics. For example, microprocessor cores execute one instruction at a time, and an operating system is needed to manage the execution of programs. In turn, FPGAs can run without an operating system and the design architecture is inherently parallel. In this paper we aim to assess these and other advantages, and the limitations, on FPGA-based solutions, considering the design guidelines and regulations on the use of FPGAs in Nuclear Plant I and C Systems. We will also examine some circuit design techniques in FPGA to help mitigate failures and provide redundancy. The objective is to show how FPGA-based systems can provide cost-effective options for I and C systems in modernization projects and to the RMB (Brazilian Multipurpose Reactor), ensuring safe and reliable operation, meeting licensing requirements, such as separation, redundancy and diversity. (author)

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.

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.

Design of first reactor protection system prototype for C A R E M reactor

International Nuclear Information System (INIS)

Azcona, A; Lorenzo, G.; Maciel, F.; Fittipaldi, A

2006-01-01

In this paper we present the design of a prototype of the C A R E M Reactor Protection System, which is implemented on a basis of the digital platform T E L E P E R M X S.The proposed architecture for the Reactor Protection System (R P S) has 4 redundant trains composed by a complete set of sensors, a data acquisition computer and a processing computer.The information from the 4 processing computers goes into to a two voting units with a two out of four (2004) logic and its outputs are combined by a final actuation logic with a voting scheme of one out of two (1002).The prototype is implemented with a unique train.The train inputs are simulated by an Automatic Testing Unit.The pre-established test case or procedure results are fed back into the A T U.The choice of the digital platform T E L E P E R M X S for the R P S implementation allows versatility in the design stage and permits the prototype expansion due to its modular characteristic and the software tools flexibility [es

Examination of Surface Deposits on Oldbury Reactor Core Graphite to Determine the Concentration and Distribution of 14C.

Directory of Open Access Journals (Sweden)

Liam Payne

Full Text Available Pile Grade A graphite was used as a moderator and reflector material in the first generation of UK Magnox nuclear power reactors. As all of these reactors are now shut down there is a need to examine the concentration and distribution of long lived radioisotopes, such as 14C, to aid in understanding their behaviour in a geological disposal facility. A selection of irradiated graphite samples from Oldbury reactor one were examined where it was observed that Raman spectroscopy can distinguish between underlying graphite and a surface deposit found on exposed channel wall surfaces. The concentration of 14C in this deposit was examined by sequentially oxidising the graphite samples in air at low temperatures (450°C and 600°C to remove the deposit and then the underlying graphite. The gases produced were captured in a series of bubbler solutions that were analysed using liquid scintillation counting. It was observed that the surface deposit was relatively enriched with 14C, with samples originating lower in the reactor exhibiting a higher concentration of 14C. Oxidation at 600°C showed that the remaining graphite material consisted of two fractions of 14C, a surface associated fraction and a graphite lattice associated fraction. The results presented correlate well with previous studies on irradiated graphite that suggest there are up to three fractions of 14C; a readily releasable fraction (corresponding to that removed by oxidation at 450°C in this study, a slowly releasable fraction (removed early at 600°C in this study, and an unreleasable fraction (removed later at 600°C in this study.

CANDU reactors with reactor grade plutonium/thorium carbide fuel

Energy Technology Data Exchange (ETDEWEB)

Sahin, Suemer [Atilim Univ., Ankara (Turkey). Faculty of Engineering; Khan, Mohammed Javed; Ahmed, Rizwan [Pakistan Institute of Engineering and Applied Sciences, Islamabad (Pakistan); Gazi Univ., Ankara (Turkey). Faculty of Technology

2011-08-15

Reactor grade (RG) plutonium, accumulated as nuclear waste of commercial reactors can be re-utilized in CANDU reactors. TRISO type fuel can withstand very high fuel burn ups. On the other hand, carbide fuel would have higher neutronic and thermal performance than oxide fuel. In the present work, RG-PuC/ThC TRISO fuels particles are imbedded body-centered cubic (BCC) in a graphite matrix with a volume fraction of 60%. The fuel compacts conform to the dimensions of sintered CANDU fuel compacts are inserted in 37 zircolay rods to build the fuel zone of a bundle. Investigations have been conducted on a conventional CANDU reactor based on GENTILLYII design with 380 fuel bundles in the core. Three mixed fuel composition have been selected for numerical calculation; (1) 10% RG-PuC + 90% ThC; (2) 30% RG-PuC + 70% ThC; (3) 50% RG-PuC + 50% ThC. Initial reactor criticality values for the modes (1), (2) and (3) are calculated as k{sub {infinity}}{sub ,0} = 1.4848, 1.5756 and 1.627, respectively. Corresponding operation lifetimes are {proportional_to} 2.7, 8.4, and 15 years and with burn ups of {proportional_to} 72 000, 222 000 and 366 000 MW.d/tonne, respectively. Higher initial plutonium charge leads to higher burn ups and longer operation periods. In the course of reactor operation, most of the plutonium will be incinerated. At the end of life, remnants of plutonium isotopes would survive; and few amounts of uranium, americium and curium isotopes would be produced. (orig.)

10 CFR 72.128 - Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling. 72.128... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

[The vitamin status of pregnant women in Moscow: effect of multivitamin-mineral supplements].

Science.gov (United States)

Beketova, N A; Sokolnikov, A A; Kodentsova, V M; Pereverzeva, O G; Vrzhesinskaya, O A; Kosheleva, O V; Gmoshinskaya, M V

2016-01-01

Examination of the vitamin status of 102 pregnant women (19-41 years old) from Moscow (gestational age 6-38 weeks) in winter and spring 2015 has been conducted. The lack of vitamin B2 (blood serum level of riboflavin vitamin B6 (vitamin A (vitamins C (>0.4 mg/dL) and B12 (>150 ng/L). The frequency of the combined deficiency of two vitamins was 29%, of three vitamins - 21%, four - 10%, five - 5%. Only 8% of women were sufficiently supplied with all 8 studied vitamins and β-carotene. A positive correlation (pvitamin E and gestation term occurred. β-Carotene blood serum level raised with increasing gestation term in women receiving multivitamin-mineral supplements (VMS) and directly correlated (pvitamin E serum level. In 63 women who were not taking VMS, blood serum level of vitamins A, D, C, B2, B6, B12, folic acid and β-carotene was lower, and the frequency of inadequate supply, on the contrary, was significantly higher, compared to 39 women receiving VMS. Blood serum concentration of vitamins C, A, D, B6 and folic acid in women who were not taking VMS was significantly reduced (pvitamin blood serum level was maintained at a constant level. The data obtained demonstrate advisability of VMS intake during pregnancy to maintain vitamin status of pregnant women at a satisfactory level and to reduce the risk of birth defects in infants.

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.

Hydrogeological and Groundwater Flow Model for C, K, L, and P Reactor Areas, Savannah River Site, Aiken, South Carolina

International Nuclear Information System (INIS)

Flach, G.P.

1999-01-01

A regional groundwater flow model encompassing approximately 100 mi 2 surrounding the C, K. L. and P reactor areas has been developed. The Reactor flow model is designed to meet the planning objectives outlined in the General Groundwater Strategy for Reactor Area Projects by providing a common framework for analyzing groundwater flow, contaminant migration and remedial alternatives within the Reactor Projects team of the Environmental Restoration Department

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.

Present status of SiCf/SiC composites as low-activation structural materials of fusion reactor in Japan

International Nuclear Information System (INIS)

Kohyama, A.; Katoh, Y.; Hasegawa, A.; Noda, T.

2001-01-01

The outline of research subjects on SiCf/SiC composites to apply to the structural components of fusion reactors are described and present status on material development of SiCf/SiC composites in Japan is reviewed. Irradiation experiments of the composites using fission reactors conducted by international collaborations to clarify their radiation response and to optimize the fabrication processes are introduced. (author)

I and C system at TRIGA - ICN reactor after more than 20 years of operation

International Nuclear Information System (INIS)

Ionila, M.; Preda, M.

2002-01-01

An I and C system that is involved in a nuclear safety function has to be itself safe in operation, strictly performing the survey of those parameters, which are linked to the safety function. The precision of such a system is sufficient for the safety function, but for a more accurate evaluation of the in-core experimental phenomena, the presence of a data acquisition and processing system is needed. The two systems must be together taken into account by the reactor operation. The data acquisition and processing system designated for the monitoring of the stationary or the slow-varying processes allow the safety function evaluation from the point of view of the statistics of the effective reactor operation time along a certain period of time. The evaluation of the unscheduled reactor shutdowns determined by those reactor systems having safety functions with the percentage contribution of each system is presented. The data were selected from the annual operation reports for the reactor and the reactor installations in the period 1981-1999

Hydrogeological and Groundwater Flow Model for C, K, L, and P Reactor Areas, Savannah River Site, Aiken, South Carolina

Energy Technology Data Exchange (ETDEWEB)

Flach, G.P.

1999-02-24

A regional groundwater flow model encompassing approximately 100 mi{sup 2} surrounding the C, K. L. and P reactor areas has been developed. The Reactor flow model is designed to meet the planning objectives outlined in the General Groundwater Strategy for Reactor Area Projects by providing a common framework for analyzing groundwater flow, contaminant migration and remedial alternatives within the Reactor Projects team of the Environmental Restoration Department.

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

C.E.C. - cod for calculus of the evolution fuel for thermal reactors

International Nuclear Information System (INIS)

Biciolla, L.; Marcu, G.; Mociornita, G.

1975-01-01

The study of ''burnup'' into thermal reactor involves two main aspects: the economic one and another regarding the reactor operation, its stability and control. In the CEC-code written in FORTRAN IV language was analysed the change of the isotopic composition of nuclear fuel from thermal reactor during its operation

A qualified safety I and C for application in reactors of all kinds

International Nuclear Information System (INIS)

Stimler, M.

2001-01-01

Advanced I and C systems for nuclear power plants have to meet increasing demands for safety and availability. Specific requirements coming from the nuclear qualification have to be fulfilled. To meet both subjects adequately, Siemens has developed the advanced digital I and C technology for safety applications TELEPERM XS. National and international codes and standards impose special requirements on the safety I and C of a nuclear power plant. These concern: fault tolerance; robustness; qualification. In order to be able to meet these requirements to the full without making operational automation tasks unnecessarily expensive by excessive conservatism, the TELEPERM XS I and C system platform was developed. It is largely based on standard Hardware devices selected for their quality characteristics and adapted by specific design measures. In the Software area a complete new development had to be undertaken in order to meet the stringent qualification requirements. In 1992 the GRS (Gesellschaft fuer Reaktorsicherheit - Association for Reactor Safety) confirmed the suitability and licensibility of the underlying TELEPERM XS concepts. Subsequently, the development and qualification of the system software and the engineering tools as well as the type testing of the hardware components was performed. Operationally proven hardware components were selected for utilization, among others from the system families SIMATIC and SINEC. The first integration tests were performed successfully in mid-1996. Field testing of the first application projects could be finalised in 1997. In many countries, the nuclear industry bases its licensing process for nuclear power plants on the US-NRC procedures. For this reason, and in order to ensure world-wide utilization of the TXS technology, it was decided in 1998 to submit a licensing application to the US-NRC. In May 2000, Siemens has received a Safety Evaluation Report (SER) from the US-NRC approving use of its TELEPERM XS (TXS) platform

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

Directory of Open Access Journals (Sweden)

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.

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

Full Text Available Subject: the influence of the socio-demographic factor on the development of the network of facilities of the social infrastructure of the city (on the example of Moscow is explored. The interrelation between socio-demographic development and the formation of the consumer demand for services and various types of facilities is revealed. The main socio-demographic concepts and measures determining a need to develop and site the facilities throughout the city are considered. Thus, the social, age and family structure of the resident population determine the typology and functional structure of facilities. The “daytime” population, its structure and concentration areas determine the volume and the new construction sites of residential buildings. The “temporary” population (including tourists, transit passengers, business travelers and other population categories, staying in the city for more than 24 hours specifies the need for the construction of hotels, hostels and other collective accommodation facilities. Economically active population creates demand for jobs, including those created on the basis of social infrastructure. Objectives: to explain the need for taking into account the modern and perspective trends in population development during the preparation of the territorial and urban planning documents; to consider the particularities of the socio-demographic characteristics included when forecasting the need to develop the social facilities, creating workplaces, taking into account the transition to the economy of services and information technologies, in designing a citywide system, including transport hubs. Materials and methods: the research was conducted on the basis of official statistics (Rosstat, Mosgorstat, of line departments and offices of the city of Moscow. Statistical, analytical, sociological methods of research, expert assessments, analogies, field survey, mathematical modeling are used. Results: modern and perspective

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.

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)

Increased SRP reactor power

International Nuclear Information System (INIS)

MacAfee, I.M.

1983-01-01

Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

Biohydrogen production from glucose in upflow biofilm reactors with plastic carriers under extreme thermophilic conditions (70(degree)C)

DEFF Research Database (Denmark)

Zheng, H.; Zeng, Raymond Jianxiong; Angelidaki, Irini

2008-01-01

Biohydrogen could efficiently be produced in glucose-fed biofilm reactors filled with plastic carriers and operated at 70°C. Batch experiments were, in addition, conducted to enrich and cultivate glucose-fed extremethermophilic hydrogen producing microorganisms from a biohydrogen CSTR reactor fed...

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

First experiences from system integration, installation and commissioning of TELEPERM XS for reactor I and C at the Unterweser NPP

International Nuclear Information System (INIS)

Schoerner, O.

1998-01-01

The modernization of Reactor I and C, consisting of reactor limitation system, reactor control system and rod control system, at Unterweser NPP is the pilot application of the state-of-the-art safety I and C system TELEPERM XS. The Unterweser system has been integrated and tested from December 1996 to May 1997 in the Siemens Erlangen test field and has been installed at site in July 1997. For the period from July 1997 to Jul 1998 the new TELEPERM XS based Reactor I and C system will be operated online-open-loop in parallel to the existing system, in order to get information about the long term stability of the system and conduct intensive personnel training. For one selected function ''Power distribution control'' the operator has the possibility to choose between the old controller and the new TELEPERM XS function. During the 1998 outage the TELEPERM XS system will be connected to the process and the old I and C system will be dismantled. This document describes the experiences gathered during system integration in the test field. (author)

ELECTRICAL RESISTANCE HEATING OF SOILS AT C-REACTOR AT THE SAVANNAH RIVER SITE

International Nuclear Information System (INIS)

Blundy, R; Michael Morgenstern, M; Joseph Amari, J; Annamarie MacMurray, A; Mark Farrar, M; Terry Killeen, T

2007-01-01

Chlorinated solvent contamination of soils and groundwater is an endemic problem at the Savannah River Site (SRS), and originated as by-products from the nuclear materials manufacturing process. Five nuclear reactors at the SRS produced special nuclear materials for the nation's defense program throughout the cold war era. An important step in the process was thorough degreasing of the fuel and target assemblies prior to irradiation. Discharges from this degreasing process resulted in significant groundwater contamination that would continue well into the future unless a soil remediation action was performed. The largest reactor contamination plume originated from C-Reactor and an interim action was selected in 2004 to remove the residual trichloroethylene (TCE) source material by electrical resistance heating (ERH) technology. This would be followed by monitoring to determine the rate of decrease in concentration in the contaminant plume. Because of the existence of numerous chlorinated solvent sources around SRS, it was elected to generate in-house expertise in the design and operation of ERH, together with the construction of a portable ERH/SVE system that could be deployed at multiple locations around the site. This paper describes the waste unit characteristics, the ERH system design and operation, together with extensive data accumulated from the first deployment adjacent to the C-Reactor building. The installation heated the vadose zone down to 62 feet bgs over a 60 day period during the summer of 2006 and raised soil temperatures to over 200 F. A total of 730 lbs of trichloroethylene (TCE) were removed over this period, and subsequent sampling indicated a removal efficiency of 99.4%

Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors

International Nuclear Information System (INIS)

Narkunas, Ernestas; Smaizys, Arturas; Poskas, Povilas; Kilda, Raimondas

2010-01-01

Two RBMK-1500 water-cooled graphite-moderated channel-type power reactors at the Ignalina Nuclear Power Plant (INPP) are under decommissioning now. The total mass of irradiated graphite in the cores of both units is more than 3600 tons. The main source of uncertainty in the numerical assessment of graphite activity is the uncertainty of the initial impurities content in graphite. Nitrogen is one of the most important impurities, having a large neutron capture cross-section. This impurity may become the dominant source of C-14 production. RBMK reactors graphite stacks operate in the cooling mixture of helium-nitrogen gases and this may additionally increase the quantity of the nitrogen impurity. In this paper the results of the numerical modelling of graphite activation for the INPP Unit I reactor are presented. In order to evaluate the C-14 activity dependence on the nitrogen impurity content, several cases with different nitrogen content were modelled taking into account initial nitrogen impurity quantities in the graphite matrix and possible nitrogen quantities entrapped in the graphite pores from cooling gases. (orig.)

Preliminary conceptual design for electrical and I and C system of a new research reactor

International Nuclear Information System (INIS)

Jung, Hoan Sung; Kim, Y. K.; Kim, M. J.; Kim, H. K.; Ryu, J. S.

2004-01-01

The core type and the process system design will be varied according to the reactor's application and capacity. A New research reactor is being designed by KAERI since 2002 and the process systems are not fixed yet. But control and instrument systems are similar to each other even though the application and the size are not same. So the C and I system that encompasses reactor protection system, reactor control system, and computer system was designed conceptually according to the requirements based on new digital technology and HANARO's proven design. The plant electrical system consists of off-site system that delivers bulk electrical power to the reactor site and on-site system that distributes and controls electrical power at the facility. The electrical system includes building service system that consist of lighting, communication, fire detection, grounding, cathodic protection, etc. also. This report describes the design requirements of on-site and off-site electric power system that set up from the codes and standards and the conceptual design based on the design requirements

Evaluation of Tehran research reactor (TRR) control rod worth using MCNP4C computer code

International Nuclear Information System (INIS)

Hosseini, Mohammad; Vosoughi, Naser; Hosseini, Seyed Abolfazl

2010-01-01

The main objective of reactor control system is to provide a safe reactor starting up, operation and shutting down. Calculation or measurement of precise values of control rod worth is of great importance in Tehran Research Reactor (TRR), considering the fact that they are the only controlling tools in the reactor. In present paper, simulation of TRR in First Operation Cycle (FOC) and in cold and clean core for the calculation of total and integral worth of control nods is reported. MCNP4C computer code has been used for all simulation process. Two method have been used for control rods worth calculation in this paper, namely the direct approach and perturbation method. It is shown that while the direct approach is appropriate for worth calculation of both the shim and the regulating control rods, the perturbation method is just suitable for tiny reactivity changes, i.e. for small initial part of regulating rods. Results of simulation are compared with the reported data in Safety Analysis Report (SAR) of Tehran research reactor and showed satisfactory agreement. (author)

Analysis on Configuration of I and C Systems for an Advanced HANARO Reactors

International Nuclear Information System (INIS)

Park, Gee Yong; Jung, H. S.; Ryu, J. S.; Park, C.

2006-01-01

In an advanced HANARO reactor (AHR), the instrumentation and control (I and C) systems are designed based on the digital system rather than the analog system installed in an existing HANARO instrumentation and control systems. While the safety and functionality of analog-based instrumentation and control system are experienced over a long period of operating time and also well-validated, the obsolescence and the lack of flexibility of this system have to move from the analog technology to the digital technology in the instrumentation and control systems to be used in nuclear power plants as well as nuclear research reactors. For establishing the adequate structure of instrumentation and control systems for an AHR, various instrumentation and control architectures are analyzed for their merits and demerits for use in I and C systems of an AHR and the most promising instrumentation and control architecture for an AHR are drawn from this analysis. The conceptual configuration of a digital-based safety shutdown system is proposed in this report

Nanocrystalline SiC and Ti₃SiC₂ Alloys for Reactor Materials: Annual Report

Energy Technology Data Exchange (ETDEWEB)

Henager, Charles H. [pnnl; Alvine, Kyle J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Roosendaal, Timothy J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Shin, Yongsoon [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nguyen, Ba Nghiep; Borlaug, Brennan A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jiang, Weilin [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Arreguin, Shelly A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-01-15

A new dual-phase nanocomposite of Ti₃SiC₂/SiC is being synthesized using preceramic polymers, ceramic powders, and carbon nanotubes (CNTs) designed to be suitable for advanced nuclear reactors and perhaps as fuel cladding. The material is being designed to have superior fracture toughness compared to SiC, adequate thermal conductivity, and higher density than SiC/SiC composites. This annual report summarizes the progress towards this goal and reports progress in understanding certain aspects of the material behavior but some shortcomings in achieving full density or in achieving adequate incorporation of CNTs. The measured thermal conductivity is adequate and falls into an expected range based on SiC and Ti₃SiC₂. Part of this study makes an initial assessment for Ti₃SiC₂ as a barrier to fission product transport. Ion implantation was used to introduce fission product surrogates (Ag and Cs) and a noble metal (Au) in Ti₃SiC₂, SiC, and a synthesized at PNNL. The experimental results indicate that the implanted Ag in SiC is immobile up to the highest temperature (1273 K) applied in this study; in contrast, significant out-diffusion of both Ag and Au in MAX phase Ti₃SiC₂ occurs during ion implantation at 873 K. Cs in Ti₃SiC₂ is found to diffuse during post-irradiation annealing at 973 K, and noticeable Cs release from the sample is observed. This study may suggest caution in using Ti₃SiC₂ as a fuel cladding material for advanced nuclear reactors operating at very high temperatures. Progress is reported in thermal conductivity modeling of SiC-based materials that is relevant to this research, as is progress in modeling the effects of CNTs on fracture strength of SiC-based materials.

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…

Evaluation of I and C architecture alternatives required for the jupiter Icy moons orbiter (JIMO) reactor

International Nuclear Information System (INIS)

Muhlheim, M. D.; Wood, R. T.; Bryan, W. L.; Wilson Jr, T. L.; Holcomb, D. E.; Korsah, K.; Jagadish, U.

2006-01-01

This paper discusses alternative architectural considerations for instrumentation and control (I and C) systems in high-reliability applications to support remote, autonomous, inaccessible nuclear reactors, such as a space nuclear power plant (SNPP) for mission electrical power and space exploration propulsion. This work supported the pre-conceptual design of the reactor control system for the Jupiter Icy Moons Orbiter (JIMO) mission. Long-term continuous operation without intermediate maintenance cycles forces consideration of alternatives to commonly used active, N-multiple redundancy techniques for high-availability systems. Long space missions, where mission duration can exceed the 50% reliability limit of constituent components, can make active, N-multiple redundant systems less reliable than simplex systems. To extend a control system lifetime beyond the 50% reliability limits requires incorporation of passive redundancy of functions. Time-dependent availability requirements must be factored into the use of combinations of active and passive redundancy techniques for different mission phases. Over the course of a 12 to 20-year mission, reactor control, power conversion, and thermal management system components may fail, and the I and C system must react and adjust to accommodate these failures and protect non-failed components to continue the mission. This requires architectural considerations to accommodate partial system failures and to adapt to multiple control schemes according to the state of non-failed components without going through a complete shutdown and restart cycle. Relevant SNPP I and C architecture examples provide insights into real-time fault tolerance and long-term reliability and availability beyond time periods normally associated with terrestrial power reactor I and C systems operating cycles. I and C architectures from aerospace systems provide examples of highly reliable and available control systems associated with short- and long

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.

Regional groundwater flow model for C, K. L. and P reactor areas, Savannah River Site, Aiken, SC

Energy Technology Data Exchange (ETDEWEB)

Flach, G.P.

2000-02-11

A regional groundwater flow model encompassing approximately 100 mi2 surrounding the C, K, L, and P reactor areas has been developed. The reactor flow model is designed to meet the planning objectives outlined in the General Groundwater Strategy for Reactor Area Projects by providing a common framework for analyzing groundwater flow, contaminant migration and remedial alternatives within the Reactor Projects team of the Environmental Restoration Department. The model provides a quantitative understanding of groundwater flow on a regional scale within the near surface aquifers and deeper semi-confined to confined aquifers. The model incorporates historical and current field characterization data up through Spring 1999. Model preprocessing is automated so that future updates and modifications can be performed quickly and efficiently. The CKLP regional reactor model can be used to guide characterization, perform scoping analyses of contaminant transport, and serve as a common base for subsequent finer-scale transport and remedial/feasibility models for each reactor area.

Regional groundwater flow model for C, K. L. and P reactor areas, Savannah River Site, Aiken, SC

International Nuclear Information System (INIS)

Flach, G.P.

2000-01-01

A regional groundwater flow model encompassing approximately 100 mi2 surrounding the C, K, L, and P reactor areas has been developed. The reactor flow model is designed to meet the planning objectives outlined in the General Groundwater Strategy for Reactor Area Projects by providing a common framework for analyzing groundwater flow, contaminant migration and remedial alternatives within the Reactor Projects team of the Environmental Restoration Department. The model provides a quantitative understanding of groundwater flow on a regional scale within the near surface aquifers and deeper semi-confined to confined aquifers. The model incorporates historical and current field characterization data up through Spring 1999. Model preprocessing is automated so that future updates and modifications can be performed quickly and efficiently. The CKLP regional reactor model can be used to guide characterization, perform scoping analyses of contaminant transport, and serve as a common base for subsequent finer-scale transport and remedial/feasibility models for each reactor area

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.

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.

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

Development of SiC Neutron Detector Assembly to Measure the Neutron Flux of the Reactor Core

Energy Technology Data Exchange (ETDEWEB)

Park, Se Hwan; Park, June Sic; Shin, Hee Sung; Kim, Ho Dong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Yong Kyun [Hanyang University, Seoul (Korea, Republic of)

2012-05-15

At present, the conventional detector to measure the neutron at harsh environment is a Self Powered Neutron Detector (SPND). Rhodium(Rh)-103 is in the SPND. When neutron is incident on the Rhodium, the neutron capture reaction occurs, and the Rh-103 is converted to Rh-104. The Rh-104 is decayed to Pd-104 by {beta}-decay, and electrons are generated as the decay products. Because of the half life of Rh-104, approximately 5 minutes are required for the SPND output to reach the equilibrium condition. Therefore the on-line monitoring of the nuclear reactor state is limited if the neutron flux in the reactor core is monitored with the SPND. Silicon carbide (SiC) has the possibility to be developed as neutron detector at harsh environment, because the SiC can be operative at high temperature and high neutron flux conditions. Previously, the basic operation properties of the SiC detector were studied. Also, the radiation response of the SiC detector was studied at high neutron and gamma dose rate. The measurement results for an ex-core neutron flux monitor or a neutron flux monitor of the spent fuel were published. The SiC detector was also developed as neutron detector to measure the fissile material with active interrogation method. However, the studies about the development of SiC detector are still limited. In the present work, the radiation damage effect of the SiC detector was studied. The detector structure was determined based on the study, and a neutron detector assembly was made with the SiC detectors. The neutron and gamma-ray response of the detector assembly is presented in this paper. The detector assembly was positioned in the HANARO research reactor core, the performance test was done. The preliminary results are also included in this paper

A study on the sealing performance of metallic C-rings in reactor pressure vessel

Energy Technology Data Exchange (ETDEWEB)

Jia, Xiaohong, E-mail: jiaxh@mail.tsinghua.edu.cn [State Key Laboratory of Tribology, Tsinghua University, Beijing 100084 (China); Chen, Huaming [State Key Laboratory of Tribology, Tsinghua University, Beijing 100084 (China); Li, Xinggen [Ningbo Tiansheng Sealing Packing Co., Ltd, Ningbo 315302 (China); Wang, Yuming [State Key Laboratory of Tribology, Tsinghua University, Beijing 100084 (China); Wang, Longke [Eaton Corporation, MN (United States)

2014-10-15

Highlights: • FE analysis on compression–resilience of metallic C-ring is performed and validated by experiments. • Model of RPV sealing system including the C-rings is developed. • Deformation data from factory hydraulic test of the RPV are used to verify the model. • C-rings’ behavior under designing condition is analyzed. • The model provides a reliable evaluation on the sealing performance of RPV. - Abstract: Double metallic C-rings are used in pressure vessel of pressurized water reactor (PWR) to seal the bolt-connected flanges. To evaluate the sealing performance, it is necessary to study both the C-rings’ intrinsic properties and their behavior in reactor pressure vessel (RPV) under various loading conditions. The compression–resilience property and linear load are the basic information to evaluate the performance of a well-designed C-ring's. An equivalent model of C-ring is constructed by means of ANSYS to analyze its intrinsic properties, and is also validated by experiments on scaled samples. This model is applied to develop a 2D-axisymmetric FE model of sealing system including RPV and C-rings with the consideration of nonlinear material, contacting problem and multiple coupled effects. The simulation results of RPV deformation under the hydraulic test condition agree well with the data of factory hydraulic test. With the verified model, an analysis under the designing condition is performed to study C-rings’ behavior in the RPV, and then provides a reliable evaluation on the sealing performance of RPV.

Examination of bedaquiline- and linezolid-resistant Mycobacterium tuberculosis isolates from the Moscow region.

Science.gov (United States)

Zimenkov, Danila V; Nosova, Elena Yu; Kulagina, Elena V; Antonova, Olga V; Arslanbaeva, Liaisan R; Isakova, Alexandra I; Krylova, Ludmila Yu; Peretokina, Irina V; Makarova, Marina V; Safonova, Svetlana G; Borisov, Sergey E; Gryadunov, Dmitry A

2017-07-01

To study the isolates with acquired resistance to bedaquiline and linezolid that were obtained from patients enrolled in a clinical study of a novel therapy regimen for drug-resistant TB in Moscow, Russia. Linezolid resistance was detected using MGIT 960 with a critical concentration of 1 mg/L. The MIC of bedaquiline was determined using the proportion method. To identify genetic determinants of resistance, sequencing of the mmpR ( Rv0678 ), atpE , atpC , pepQ , Rv1979c , rrl , rplC and rplD loci was performed. A total of 85 isolates from 27 patients with acquired resistance to linezolid and reduced susceptibility to bedaquiline (MIC ≥0.06 mg/L) were tested. Most mutations associated with a high MIC of bedaquiline were found in the mmpR gene. We identified for the first time two patients whose clinical isolates had substitutions D28N and A63V in AtpE, which had previously been found only in in vitro -selected strains. Several patients had isolates with elevated MICs of bedaquiline prior to treatment; four of them also bore mutations in mmpR , indicating the presence of some hidden factors in bedaquiline resistance acquisition. The C154R substitution in ribosomal protein L3 was the most frequent in the linezolid-resistant strains. Mutations in the 23S rRNA gene (g2294a and g2814t) associated with linezolid resistance were also found in two isolates. Heteroresistance was identified in ∼40% of samples, which reflects the complex nature of resistance acquisition. The introduction of novel drugs into treatment must be accompanied by continuous phenotypic susceptibility testing and the analysis of genetic determinants of resistance. © The Author 2017. Published by Oxford University Press on behalf of the British Society for Antimicrobial Chemotherapy. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

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

Supercritical Water Reactors

International Nuclear Information System (INIS)

Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

2014-01-01

The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

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. 

Temperature detectors on irradiated silicon base

International Nuclear Information System (INIS)

Karimov, M.; Dzhalelov, M.A.; Kurbanov, A.O.

2005-01-01

It is well known, that the most suitable for thermal resistors production is compensated silicon with impurities forming deep lying in forbidden zone, having big negative resistance temperature coefficients (RTC). In the capacity of initial materials for thermal resistors with negative RTC the n-type monocrystalline silicon with specific resistance ∼30 Ω·cm at 300 K is applied. Before the irradiation the phosphorus diffusion is realizing at temperature ∼1000 deg. C for 10 min. Irradiation is putting into practise by WWR-SM reactor fast neutrons within the range (7-10)·10 13 cm -2 . The produced resistors have nominal resistance range (8-20)·10 3 Ω·cm, coefficient of the thermal sensitivity B=4000-6000 deg. C., RTC α 300K =4-6.6 %/grad. It is shown, that offered method allows to obtain same type resistors characteristics on the base of neutron-irradiated material

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.

"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…

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

A simulation of a pebble bed reactor core by the MCNP-4C computer code

Directory of Open Access Journals (Sweden)

Bakhshayesh Moshkbar Khalil

2009-01-01

Full Text Available Lack of energy is a major crisis of our century; the irregular increase of fossil fuel costs has forced us to search for novel, cheaper, and safer sources of energy. Pebble bed reactors - an advanced new generation of reactors with specific advantages in safety and cost - might turn out to be the desired candidate for the role. The calculation of the critical height of a pebble bed reactor at room temperature, while using the MCNP-4C computer code, is the main goal of this paper. In order to reduce the MCNP computing time compared to the previously proposed schemes, we have devised a new simulation scheme. Different arrangements of kernels in fuel pebble simulations were investigated and the best arrangement to decrease the MCNP execution time (while keeping the accuracy of the results, chosen. The neutron flux distribution and control rods worth, as well as their shadowing effects, have also been considered in this paper. All calculations done for the HTR-10 reactor core are in good agreement with experimental results.

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.

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.

[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.

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.

Methanogenesis in Thermophilic Biogas Reactors

DEFF Research Database (Denmark)

Ahring, Birgitte Kiær

1995-01-01

Methanogenesis in thermophilic biogas reactors fed with different wastes is examined. The specific methanogenic activity with acetate or hydrogen as substrate reflected the organic loading of the specific reactor examined. Increasing the loading of thermophilic reactors stabilized the process as ....... Experiments using biogas reactors fed with cow manure showed that the same biogas yield found at 550 C could be obtained at 610 C after a long adaptation period. However, propionate degradation was inhibited by increasing the temperature.......Methanogenesis in thermophilic biogas reactors fed with different wastes is examined. The specific methanogenic activity with acetate or hydrogen as substrate reflected the organic loading of the specific reactor examined. Increasing the loading of thermophilic reactors stabilized the process...... as indicated by a lower concentration of volatile fatty acids in the effluent from the reactors. The specific methanogenic activity in a thermophilic pilot-plant biogas reactor fed with a mixture of cow and pig manure reflected the stability of the reactor. The numbers of methanogens counted by the most...

Materials surveillance program for C-E NSSS reactor vessels

International Nuclear Information System (INIS)

Koziol, J.J.

1977-01-01

Irradiation surveillance programs for light water NSSS reactor vessels provide the means by which the utility can assess the extent of neutron-induced changes in the reactor vessel materials. These programs are conducted to verify, by direct measurement, the conservatism in the predicted radiation-induced changes and hence the operational parameters (i.e., heat-up, cooldown, and pressurization rates). In addition, such programs provide assurance that the scheduled adjustments in the operational parameters are made with ample margin for safe operation of the plant. During the past 3 years, several documents have been promulgated establishing the criteria for determining both the initial properties of the reactor vessel materials as well as measurement of changes in these initial properties as a result of irradiation. These documents, ASTM E-185-73, ''Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels,'' and Appendix H to 10 CFR 50, ''Reactor Vessel Material Surveillance Program Requirements,'' are complementary to each other. They are the result of a change in the basic philosophy regarding the design and analysis of reactor vessels. In effect, the empirical ''transition temperature approach,'' which was used for design, was replaced by the ''analytical fracture mechanics approach.'' The implementation of this technique was described in Welding Research Council Bulletin 1975 and Appendix G to ASME Code Section III. Further definition of requirements appears in Appendix G to 10 CFR 50 published in July 1973. It is the intent of this paper to describe (1) a typical materials surveillance program for the reactor vessel of a Combustion Engineering NSSS, and (2) how the results of such programs, as well as experimental programs provide feed-back for improvement of materials to enhance their radiation resistance and thereby further improve the safety and reliability of future plants. (author)

Canada-India Reactor (CIR)

Energy Technology Data Exchange (ETDEWEB)

None

1960-12-15

Design information on the Canada-India Reactor is presented. Data are given on reactor physics, the core, fuel elements, core heat transfer, control, reactor vessel, fluid flow, reflector and shielding, containment, cost estimates, and research facilities. Drawings of vertical and horizontal sections of the reactor and fluid flow are included. (M.C.G.)

I and C safety research at the OECD Halden reactor project

International Nuclear Information System (INIS)

Gran, B.A.

2007-01-01

The overall objective of the Halden Reactor Project research on software systems dependability is to contribute to the successful introduction of digital I and C systems into NPPs. When celebrating the 50 years of the Halden Project in 2008, about 100 written reports have been delivered within this research. This research covers a number of topics covering safety, reliability, validation and verification, quality assurance, risk assessment, requirement engineering, error propagation, qualitative and quantitative assessment. In the paper some activities are described, pinpointing the importance of good joint projects with organisations in the member countries

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)

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

Conceptual design of nuclear fusion power reactor DREAM. Reactor structures and remote maintenance

International Nuclear Information System (INIS)

Nishio, Satoshi; Seki, Yasushi; Ueda, Shuzo; Kurihara, Ryoichi; Adachi, Junichi; Yamazaki, Seiichiro; Hashimoto, Toshiyuki.

1997-01-01

Nuclear fusion reactors are required to be able to compete another energy sources in economy, reliability, safety and environmental integrity for commercial use. In the DREAM (DRastically EAsy Maintenance) reactor, a very low activated material of SiC/SiC composite has been introduced for the structural material, a reactor configuration for very easy maintenance and the helium gas of a high temperature for the cooling system, and hence DREAM has been proven to be very attractively as the commercial power reactor due to the high availability and efficiency of the plant and minimization of radioactive wastes. (author)

Reactor as furnace and reactor as lamp

International Nuclear Information System (INIS)

Goldanskii, V.I.

1992-01-01

There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

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

Engineering Porous Polymer Hollow Fiber Microfluidic Reactors for Sustainable C-H Functionalization.

Science.gov (United States)

He, Yingxin; Rezaei, Fateme; Kapila, Shubhender; Rownaghi, Ali A

2017-05-17

Highly hydrophilic and solvent-stable porous polyamide-imide (PAI) hollow fibers were created by cross-linking of bare PAI hollow fibers with 3-aminopropyl trimethoxysilane (APS). The APS-grafted PAI hollow fibers were then functionalized with salicylic aldehyde for binding catalytically active Pd(II) ions through a covalent postmodification method. The catalytic activity of the composite hollow fiber microfluidic reactors (Pd(II) immobilized APS-grafted PAI hollow fibers) was tested via heterogeneous Heck coupling reaction of aryl halides under both batch and continuous-flow reactions in polar aprotic solvents at high temperature (120 °C) and low operating pressure. X-ray photoelectron spectroscopy (XPS) and inductively coupled plasma (ICP) analyses of the starting and recycled composite hollow fibers indicated that the fibers contain very similar loadings of Pd(II), implying no degree of catalyst leaching from the hollow fibers during reaction. The composite hollow fiber microfluidic reactors showed long-term stability and strong control over the leaching of Pd species.

Reactor noise analysis applications in NPP I and C systems

Energy Technology Data Exchange (ETDEWEB)

Gloeckler, O. [International Atomic Energy Agency, Wagramer Strosse 5, A-1400 Vienna, Austria Ontario Power Generation, 230 Westney Road South, Ajax, Ont. L1S 7R3 (Canada)

2006-07-01

Reactor noise analysis techniques are used in many NPPs on a routine basis as 'inspection tools' to get information on the dynamics of reactor processes and their instrumentation in a passive, non-intrusive way. The paper discusses some of the tasks and requirements an NPP has to take to implement and to use the full advantages of reactor noise analysis techniques. Typical signal noise analysis applications developed for the monitoring of the reactor shutdown system and control system instrumentation of the Candu units of Ontario Power Generation and Bruce Power are also presented. (authors)

Identification of tertiary butyl alcohol (TBA)-utilizing organisms in BioGAC reactors using 13C-DNA stable isotope probing.

Science.gov (United States)

Aslett, Denise; Haas, Joseph; Hyman, Michael

2011-09-01

Biodegradation of the gasoline oxygenates methyl tertiary-butyl ether (MTBE) and ethyl tertiary-butyl ether (ETBE) can cause tertiary butyl alcohol (TBA) to accumulate in gasoline-impacted environments. One remediation option for TBA-contaminated groundwater involves oxygenated granulated activated carbon (GAC) reactors that have been self-inoculated by indigenous TBA-degrading microorganisms in ground water extracted from contaminated aquifers. Identification of these organisms is important for understanding the range of TBA-metabolizing organisms in nature and for determining whether self-inoculation of similar reactors is likely to occur at other sites. In this study (13)C-DNA-stable isotope probing (SIP) was used to identify TBA-utilizing organisms in samples of self-inoculated BioGAC reactors operated at sites in New York and California. Based on 16S rRNA nucleotide sequences, all TBA-utilizing organisms identified were members of the Burkholderiales order of the β-proteobacteria. Organisms similar to Cupriavidus and Methylibium were observed in both reactor samples while organisms similar to Polaromonas and Rhodoferax were unique to the reactor sample from New York. Organisms similar to Hydrogenophaga and Paucibacter strains were only detected in the reactor sample from California. We also analyzed our samples for the presence of several genes previously implicated in TBA oxidation by pure cultures of bacteria. Genes Mpe_B0532, B0541, B0555, and B0561 were all detected in (13)C-metagenomic DNA from both reactors and deduced amino acid sequences suggested these genes all encode highly conserved enzymes. One gene (Mpe_B0555) encodes a putative phthalate dioxygenase-like enzyme that may be particularly appropriate for determining the potential for TBA oxidation in contaminated environmental samples.

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

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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».

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

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.

Application of macro-cellular SiC reactor to diesel engine-like injection and combustion conditions

Science.gov (United States)

Cypris, Weclas, M.; Greil, P.; Schlier, L. M.; Travitzky, N.; Zhang, W.

2012-05-01

One of novel combustion technologies for low emissions and highly efficient internal combustion engines is combustion in porous reactors (PM). The heat release process inside combustion reactor is homogeneous and flameless resulting in a nearly zero emissions level. Such combustion process, however is non-stationary, is performed under high pressure with requirement of mixture formation directly inside the combustion reactor (high pressure fuel injection). Reactor heat capacity resulting in lowering of combustion temperature as well as internal heat recuperation during the engine cycle changes the thermodynamic conditions of the process as compared to conventional engine. For the present investigations a macro-cellular lattice structure based on silicon carbide (non-foam structure) with 600 vertical cylindrical struts was fabricated and applied to engine-like combustion conditions (combustion chamber). The lattice design with a high porosity > 80% was shaped by indirect three-dimensional printing of a SiC powder mixed with a dextrin binder which also serves as a carbon precursor. In order to perform detailed investigations on low-and high-temperature oxidation processes in porous reactors under engine-like conditions, a special combustion chamber has been built and equipped with a Diesel common-rail injection system. This system simulates the thermodynamic conditions at the time instance of injection onset (corresponding to the nearly TDC of compression in a real engine). Overall analysis of oxidation processes (for variable initial pressure, temperature and air excess ratio) for free Diesel spray combustion and for combustion in porous reactor allows selection of three regions representing different characteristics of the oxidation process represented by a single-step and multi-step reactions Another characteristic feature of investigated processes is reaction delay time. There are five characteristic regions to be selected according to the delay time (t) duration

Temperature increases from 55 to 75 C in a two-phase biogas reactor result in fundamental alterations within the bacterial and archaeal community structure

Energy Technology Data Exchange (ETDEWEB)

Rademacher, Antje [Leibniz-Institut fuer Agrartechnik Potsdam-Bornim e.V. (ATB), Potsdam (Germany). Abt. Bioverfahrenstechnik; Technische Univ. Berlin (Germany). Inst. fuer Technischen Umweltschutz; Nolte, Christine; Schoenberg, Mandy; Klocke, Michael [Leibniz-Institut fuer Agrartechnik Potsdam-Bornim e.V. (ATB), Potsdam (Germany). Abt. Bioverfahrenstechnik

2012-10-15

Agricultural biogas plants were operated in most cases below their optimal performance. An increase in the fermentation temperature and a spatial separation of hydrolysis/acetogenesis and methanogenesis are known strategies in improving and stabilizing biogas production. In this study, the dynamic variability of the bacterial and archaeal community was monitored within a two-phase leach bed biogas reactor supplied with rye silage and straw during a stepwise temperature increase from 55 to 75 C within the leach bed reactor (LBR), using TRFLP analyses. To identify the terminal restriction fragments that were obtained, bacterial and archaeal 16S rRNA gene libraries were constructed. Above 65 C, the bacterial community structure changed from being Clostridiales-dominated toward being dominated by members of the Bacteroidales, Clostridiales, and Thermotogales orders. Simultaneously, several changes occurred, including a decrease in the total cell count, degradation rate, and biogas yield along with alterations in the intermediate production. A bioaugmentation with compost at 70 C led to slight improvements in the reactor performance; these did not persist at 75 C. However, the archaeal community within the downstream anaerobic filter reactor (AF), operated constantly at 55 C, altered by the temperature increase in the LBR. At an LBR temperature of 55 C, members of the Methanobacteriales order were prevalent in the AF, whereas at higher LBR temperatures Methanosarcinales prevailed. Altogether, the best performance of this two-phase reactor was achieved at an LBR temperature of below 65 C, which indicates that this temperature range has a favorable effect on the microbial community responsible for the production of biogas. (orig.)

Irradiations under magnetic field. Measurement of resistivity sample irradiations between 100 and 500 deg C in a swimming-pool reactor

International Nuclear Information System (INIS)

Pauleve, J.; Marchand, A.; Blaise, A.

1964-01-01

An oven is described which enables the irradiation of small samples in the maximum neutron flux of a swimming-pool reactor of 15 MW (Siloe), at temperatures of between 100 and 500 deg.C defined to ± 0,5 deg.C, The oven is very simple from the technological point of view, and has a diameter of only 27 mm, This permits resistivity measurements to be carried out under irradiation in the reactor, or as another example, it enables irradiations in a magnetic field of 5000 oersteds, created by an immersed solenoid. (authors) [fr

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

Nuclear reactor

International Nuclear Information System (INIS)

Garabedian, G.

1988-01-01

A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

Generation IV reactors: reactor concepts

International Nuclear Information System (INIS)

Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

2003-01-01

Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

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

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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...

[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.

Nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

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.

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

High-temperature and breeder reactors - economic nuclear reactors of the future

International Nuclear Information System (INIS)

Djalilzadeh, A.M.

1977-01-01

The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

Mortality related to air pollution with the moscow heat wave and wildfire of 2010.

Science.gov (United States)

Shaposhnikov, Dmitry; Revich, Boris; Bellander, Tom; Bedada, Getahun Bero; Bottai, Matteo; Kharkova, Tatyana; Kvasha, Ekaterina; Lezina, Elena; Lind, Tomas; Semutnikova, Eugenia; Pershagen, Göran

2014-05-01

Prolonged high temperatures and air pollution from wildfires often occur together, and the two may interact in their effects on mortality. However, there are few data on such possible interactions. We analyzed day-to-day variations in the number of deaths in Moscow, Russia, in relation to air pollution levels and temperature during the disastrous heat wave and wildfire of 2010. Corresponding data for the period 2006-2009 were used for comparison. Daily average levels of PM10 and ozone were obtained from several continuous measurement stations. The daily number of nonaccidental deaths from specific causes was extracted from official records. Analyses of interactions considered the main effect of temperature as well as the added effect of prolonged high temperatures and the interaction with PM10. The major heat wave lasted for 44 days, with 24-hour average temperatures ranging from 24°C to 31°C and PM10 levels exceeding 300 μg/m on several days. There were close to 11,000 excess deaths from nonaccidental causes during this period, mainly among those older than 65 years. Increased risks also occurred in younger age groups. The most pronounced effects were for deaths from cardiovascular, respiratory, genitourinary, and nervous system diseases. Continuously increasing risks following prolonged high temperatures were apparent during the first 2 weeks of the heat wave. Interactions between high temperatures and air pollution from wildfires in excess of an additive effect contributed to more than 2000 deaths. Interactions between high temperatures and wildfire air pollution should be considered in risk assessments regarding health consequences of climate change.

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

Effect of temperature increase from 55 to 65 degrees C on performance and microbial population dynamics of an anaerobic reactor treating cattle manure

DEFF Research Database (Denmark)

Ahring, Birgitte Kiær; Ibrahim, Ashraf; Mladenovska, Zuzana

2001-01-01

C, a decreased activity was found For glucosc-, acetate- , butyrate- and formate-utilizers and no significant activity was measured with propionate. Only the hydrogen-consuming methanogens showed an enhanced activity at 65 degreesC. Numbers of cultivable methanogens, estimated by the most probable number (MPN......The effect of a temperature increase from 55 to 65 degreesC on process performance and microbial population dynamics were investigated in thermophilic, lab-scale, continuously stirred tank reactors. The reactors had a working volume of 3 l and were fed with cattle manure at an organic loading rate....../d at 55 degreesC. Simultaneously, Ibe level of total volatile fatty acids, VFA, increased from being below 0.3g/l to 1.8-2.4g acetate/l. The specific methanogenic activities (SMA) of biomass from the reactors were measured with acetate, propionate, butyrate, hydrogen, formate and glucose. At 65 degrees...

Greater-than-Class C low-level radioactive waste characterization. Appendix A-3: Basis for greater-than-Class C low-level radioactive waste light water reactor projections

International Nuclear Information System (INIS)

Mancini, A.; Tuite, P.; Tuite, K.; Woodberry, S.

1994-09-01

This study characterizes low-level radioactive waste types that may exceed Class C limits at light water reactors, estimates the amounts of waste generated, and estimates radionuclide content and distribution within the waste. Waste types that may exceed Class C limits include metal components that become activated during operations, process wastes such as cartridge filters and decontamination resins, and activated metals from decommissioning activities. Operating parameters and current management practices at operating plants are reviewed and used to estimate the amounts of low-level waste exceeding Class C limits that is generated per fuel cycle, including amounts of routinely generated activated metal components and process waste. Radionuclide content is calculated for specific activated metals components. Empirical data from actual low-level radioactive waste are used to estimate radionuclide content for process wastes. Volumes and activities are also estimated for decommissioning activated metals that exceed Class C limits. To estimate activation levels of decommissioning waste, six typical light water reactors are modeled and analyzed. This study does not consider concentration averaging

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.

Maintenance and material aspects of DREAM reactor

International Nuclear Information System (INIS)

Ueda, S.; Nishio, S.; Yamada, R.; Seki, Y.; Kurihara, R.; Adachi, J.; Yamazaki, S.

2000-01-01

A concept of a commercial fusion power reactors (Fusion Power: 5.5 GW, electric output: 2.7 GW) having high environmental safety, high thermal efficiency and high availability has been studied in JAERI. The gross reactor configuration was designed to achieve good maintainability, high performance breeding blanket, high efficient power generation system and little radwastes. Design was based on the use of low activation structural material (SiC/SiC composites) and helium as a coolant. In this paper, maintenance and material aspects of DREAM reactor design is discussed. The concluding remarks are as follows. (1) The difficulty of development of maintenance tool is alleviated by sector replacement and the radiation dose environment less than 10 Gy/h in a reactor chamber. (2) Design requirement and present status of SiC/SiC composites was investigated. (3) The SiC/SiC composite development program is planned to satisfy the requirements of DREAM reactor

Simulations of Moscow megacity heat island with the COSMO-CLM model using two different urban canopy schemes and realistic building parameters, derived from OpenStreetMap data

Science.gov (United States)

Varentsov, Mikhail; Wouters, Hendrik; Trusilova, Kristina; Samsonov, Timofey; Konstantinov, Pavel

2017-04-01

In this study we present the application of the regional climate model COSMO-CLM to simulate urban heat island (UHI) phenomenon for Moscow megacity, which is the biggest agglomeration in Europe (with modern population of more than 17 million people). Significant differences of Moscow from the cities of Western Europe are related with much more continental climate with higher diurnal and annual temperature variations, and with specific building features such as its high density and almost total predominance of high-rise and low-rise blocks of flats on the private low-rise houses. Because of these building and climate features, the UHI of Moscow megacity is stronger than UHIs of many other cities of the similar size, with a mean intensity is about 2 °C and maximum intensity reaching up to 13 °C (Lokoschenko, 2014). Such a pronounced UHI together with the existence of an extensive observation network (more than 50 weather and air quality monitoring stations and few microwave temperature profilers) within the city and its surrounding make Moscow an especially interesting place for urban climate researches and good testbed for urban canopy models. In our numerical experiments, regional climate model firstly was adapted for investigated region with aim to improve quality of its simulations of rural areas. Then, to take into account urban canopy effects on thermal regime of the urbanized areas, we used two different versions of COSMO-CLM model. First is coupled with TEB (Town Energy Balance) single layer urban canopy model (Trusilova, 2013), and second is extended with bulk urban canopy scheme TERRA_URB using the Semi-empircal URban-canopY dependency parametriation SURY (Wouters et. al, 2016). Numerical experiments with these two versions of the model were run with spatial resolution about 1 km for several summer and winter months. To provide specific parameters, required for urban parameterizations, such as urban fraction, building height and street canyon aspect ratio

Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

International Nuclear Information System (INIS)

Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

2014-01-01

Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as 99 Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as 99 Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO 2 SO 4 ) with 994.2 g of 235 U (enrichment at 20%) providing an excess reactivity at operating temperature (40 o C) of 3.8 mk for a molality determined as 1.46 mol kg -1 for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 o C. Peak temperature and power were determined as 83 o C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the temperature and void coefficients are

Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

Energy Technology Data Exchange (ETDEWEB)

Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Canadian Forces (Canada)

2014-07-01

Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as {sup 99}Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as {sup 99}Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO{sub 2}SO{sub 4}) with 994.2 g of {sup 235}U (enrichment at 20%) providing an excess reactivity at operating temperature (40 {sup o}C) of 3.8 mk for a molality determined as 1.46 mol kg{sup -1} for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 {sup o}C. Peak temperature and power were determined as 83 {sup o}C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the

Reactor for exothermic reactions

Science.gov (United States)

Smith, L.A. Jr.; Hearn, D.; Jones, E.M. Jr.

1993-03-02

A liquid phase process is described for oligomerization of C[sub 4] and C[sub 5] isoolefins or the etherification thereof with C[sub 1] to C[sub 6] alcohols wherein the reactants are contacted in a reactor with a fixed bed acid cation exchange resin catalyst at an LHSV of 5 to 20, pressure of 0 to 400 psig and temperature of 120 to 300 F. Wherein the improvement is the operation of the reactor at a pressure to maintain the reaction mixture at its boiling point whereby at least a portion but less than all of the reaction mixture is vaporized. By operating at the boiling point and allowing a portion of the reaction mixture to vaporize, the exothermic heat of reaction is dissipated by the formation of more boil up and the temperature in the reactor is controlled.

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.

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

Reactor facility

International Nuclear Information System (INIS)

Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

1997-01-01

The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

Use of MCNP for characterization of reactor vessel internals waste from decommissioned nuclear reactors

International Nuclear Information System (INIS)

Love, E.F.; Pauley, K.A.; Reid, B.D.

1995-09-01

This study describes the use of the Monte Carlo Neutron-Photon (MCNP) code for determining activation levels of irradiated reactor vessel internals hardware. The purpose of the analysis is to produce data for the Department of Energy's Greater-Than-Class C Low-Level Radioactive Waste Program. An MCNP model was developed to analyze the Yankee Rowe reactor facility. The model incorporates reactor geometry, material compositions, and operating history data acquired from Yankee Atomic Electric Company. In addition to the base activation analysis, parametric studies were performed to determine the sensitivity of activation to specific parameters. A component sampling plan was also developed to validate the model results, although the plan was not implemented. The calculations for the Yankee Rowe reactor predict that only the core baffle and the core support plates will be activated to levels above the Class C limits. The parametric calculations show, however, that the large uncertainties in the material compositions could cause errors in the estimates that could also increase the estimated activation level of the core barrel to above the Class C limits. Extrapolation of the results to other reactor facilities indicates that in addition to the baffle and support plates, core barrels may also be activated to above Class C limits; however the classification will depend on the specific operating conditions of the reactor and the specific material compositions of the metal, as well as the use of allowable concentration averaging practices in packaging and classifying the waste

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…

Comparison of two-stage thermophilic (68 degrees C/55 degrees C) anaerobic digestion with one-stage thermophilic (55 degrees C) digestion of cattle manure.

Science.gov (United States)

Nielsen, H B; Mladenovska, Z; Westermann, P; Ahring, B K

2004-05-05

A two-stage 68 degrees C/55 degrees C anaerobic degradation process for treatment of cattle manure was studied. In batch experiments, an increase of the specific methane yield, ranging from 24% to 56%, was obtained when cattle manure and its fractions (fibers and liquid) were pretreated at 68 degrees C for periods of 36, 108, and 168 h, and subsequently digested at 55 degrees C. In a lab-scale experiment, the performance of a two-stage reactor system, consisting of a digester operating at 68 degrees C with a hydraulic retention time (HRT) of 3 days, connected to a 55 degrees C reactor with 12-day HRT, was compared with a conventional single-stage reactor running at 55 degrees C with 15-days HRT. When an organic loading of 3 g volatile solids (VS) per liter per day was applied, the two-stage setup had a 6% to 8% higher specific methane yield and a 9% more effective VS-removal than the conventional single-stage reactor. The 68 degrees C reactor generated 7% to 9% of the total amount of methane of the two-stage system and maintained a volatile fatty acids (VFA) concentration of 4.0 to 4.4 g acetate per liter. Population size and activity of aceticlastic methanogens, syntrophic bacteria, and hydrolytic/fermentative bacteria were significantly lower in the 68 degrees C reactor than in the 55 degrees C reactors. The density levels of methanogens utilizing H2/CO2 or formate were, however, in the same range for all reactors, although the degradation of these substrates was significantly lower in the 68 degrees C reactor than in the 55 degrees C reactors. Temporal temperature gradient electrophoresis profiles (TTGE) of the 68 degrees C reactor demonstrated a stable bacterial community along with a less divergent community of archaeal species. Copyright 2004 Wiley Periodicals, Inc.

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. 

Mirror fusion reactor design

International Nuclear Information System (INIS)

Neef, W.S. Jr.; Carlson, G.A.

1979-01-01

Recent conceptual reactor designs based on mirror confinement are described. Four components of mirror reactors for which materials considerations and structural mechanics analysis must play an important role in successful design are discussed. The reactor components are: (a) first-wall and thermal conversion blanket, (b) superconducting magnets and their force restraining structure, (c) neutral beam injectors, and (d) plasma direct energy converters

Study of the obtainment of Mo{sub 2}C by gas-solid reaction in a fixed and rotary bed reactor; Estudo da obtencao de Mo{sub 2}C por reacao gas-solido em reator de leito fixo e rotativo

Energy Technology Data Exchange (ETDEWEB)

Araujo, C.P.B. de; Souza, C.P. de; Souto, M.V.M.; Barbosa, C.M.; Frota, A.V.V.M., E-mail: cpbaraujo@gmail.com [Universidade Federal do Rio Grande do Norte (UFRN), Natal, RN (Brazil)

2016-07-01

Carbides' synthesis via gas-solid reaction overcomes many of the difficulties found in other processes, requiring lower temperatures and reaction times than traditional metallurgic routes, for example. In carbides' synthesis in fixed bed reactors (FB) the solid precursor is permeated by the reducing/carburizing gas stream forming a packed bed without mobility. The use of a rotary kiln reactor (RK) adds a mixing character to this process, changing its fluid-particle dynamics. In this work ammonium molybdate was subjected to carbo-reduction reaction (CH4 / H2) in both reactors under the same gas flow (15L / h) and temperature (660 ° C) for 180 minutes. Complete conversion was observed Mo2C (dp = 18.9nm modal particles sizes' distribution) in the fixed bed reactor. In the RK reactor this conversion was only partial (∼ 40%) and Mo2C and MoO3 (34nm dp = bimodal) could be observed on the produced XRD pattern. Partial conversion was attributed to the need to use higher solids loading in the reactor CR (50% higher) to avoid solids to centrifuge. (author)

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)

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.)

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.)

A COMPARISON OF (PuU)C AND (PuU)O$sub 2$ FUELED FAST BREEDER REACTORS

Energy Technology Data Exchange (ETDEWEB)

Kazi, A. Halim; Rosen, Stanley

1963-11-15

BS>A conceptual evaluation is presented of a (PuU)C 500Mw(e) reactor which uses a moderate power generation of 40 kw/ft and a maximum fuel temperature of 2900 deg F, well below the 4500 deg F melting point of Pu/sub 0.2/U/sub 0.8/C. The principal design characteristics and fuel cycle costs are tabulated together with those of a (PuU)O/sub 2/ design of equal power. The comparison shows that the carbide core has significant economic and safety advantages over the oxide core. (D.L.C.)

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.

Physical security at research reactors

International Nuclear Information System (INIS)

Clark, R.A.

1977-01-01

Of the 84 non-power research facilities licensed under 10 CFR Part 50, 73 are active (two test reactors, 68 research reactors and three critical facilities) and are required by 10 CFR Part 73.40 to provide physical protection against theft of SNM and against industrial sabotage. Each licensee has developed a security plan required by 10 CFR Part 50.34(c) to demonstrate the means of compliance with the applicable requirements of 10 CFR Part 73. In 1974, the Commission provided interim guidance for the organization and content of security plans for (a) test reactors, (b) medium power research and training reactors, and (c) low power research and training reactors. Eleven TRIGA reactors, with power levels greater than 250 kW and all other research and training reactors with power levels greater than 100 kW and less than or equal to 5,000 kW are designated as medium power research and training reactors. Thirteen TRIGA reactors with authorized power levels less than 250 kW are considered to be low power research and training reactors. Additional guidance for complying with the requirements of 73.50 and 73.60, if applicable, is provided in the Commission's Regulatory Guides. The Commission's Office of Inspection and Enforcement inspects each licensed facility to assure that an approved security plan is properly implemented with appropriate procedures and physical protection systems

Comparative assessment of instrumentation and control (I and C) system architectures for research reactors

International Nuclear Information System (INIS)

Khalil, Rah Man; Heo, Gyun Young; Son, Han Seong; Kim, Young Ki; Park, Jae Kwan

2012-01-01

Application of digital I and C has increased in nuclear industry since last two decades but lack of experience, innovative and naive nature of technology and insufficient failure information raised questions on its use. The issues has been highlighted due to the use of digital I and C which were not relevant to analog. These are the potential weakness of digital systems for Common Cause Failure, threat to system security and reliability due to inter channel communication, need for highly integrated control room and difficulty to assess the digital I and C reliability. In the existing scenario, HANARO and JRTR have hybrid I and C systems (digital plus analog) whereas OPAL is fully digitalized. In order to authenticate the choice of fully digital I and C architecture for research reactor, it is required to perform assessment from risk point of view, cyber security as well other issues. The architecture assessment method and restrictions are discussed in the next part of article

Joining of SiC/SiCf ceramic matrix composites for fusion reactor blanket applications

International Nuclear Information System (INIS)

Colombo, P.; Riccardi, B.; Donato, A.; Scarinci, G.

2000-01-01

Using a preceramic polymer, joints between SiC/SiC f ceramic matrix composites were obtained. The polymer, upon pyrolysis at high temperature, transforms into a ceramic material and develops an adhesive bonding with the composite. The surface morphology of 2D and 3D SiC/SiC f composites did not allow satisfactory results to be obtained by a simple application of the method initially developed for monolithic SiC bodies, which employed the use of a pure silicone resin. Thus, active or inert fillers were mixed with the preceramic polymer, in order to reduce its volumetric shrinkage which occurs during pyrolysis. In particular, the joints realized using the silicone resin with Al-Si powder as reactive additive displayed remarkable shear strength (31.6 MPa maximum). Large standard deviation for the shear strength has nevertheless been measured. The proposed joining method is promising for the realization of fusion reactor blanket structures, even if presently the measured strength values are not fully satisfactory

Comparative assessment of instrumentation and control (I and C) system architectures for research reactors

Energy Technology Data Exchange (ETDEWEB)

Khalil, Rah Man; Heo, Gyun Young [Kyung Hee Univ., Seoul (Korea, Republic of); Son, Han Seong [Joongbu Univ., Chungnam (Korea, Republic of); Kim, Young Ki; Park, Jae Kwan [KAERI, Daejeon (Korea, Republic of)

2012-10-15

Application of digital I and C has increased in nuclear industry since last two decades but lack of experience, innovative and naive nature of technology and insufficient failure information raised questions on its use. The issues has been highlighted due to the use of digital I and C which were not relevant to analog. These are the potential weakness of digital systems for Common Cause Failure, threat to system security and reliability due to inter channel communication, need for highly integrated control room and difficulty to assess the digital I and C reliability. In the existing scenario, HANARO and JRTR have hybrid I and C systems (digital plus analog) whereas OPAL is fully digitalized. In order to authenticate the choice of fully digital I and C architecture for research reactor, it is required to perform assessment from risk point of view, cyber security as well other issues. The architecture assessment method and restrictions are discussed in the next part of article.

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

Expected characteristics of future reactors for human beings

International Nuclear Information System (INIS)

Taketani, Kiyoaki

1992-01-01

Based on four reactor safety components (namely: a) God-given safety, b) Equipment safety, c) Quick-response safety, d) Containing safety), categorical assessment is made of various nuclear reactor concepts ranging from present existing reactors to future reactors based on innovative reactor design. In pursuit of nuclear reactor safety, ultimate characteristics of the ideal nuclear reactor are expected to coincide with those of an inherently safe reactor. A definition of 'inherently safe' has already been proposed by a committee in Japan. As a realistic and existable reactor, which is as close to the ideal reactor, a future reactor which is almost the same as a global reactor, is proposed. This global reactor must be constructable anywhere on earth and must permit easy operation and maintenance by anyone. It is also discussed to identify what behavior is expected of the global reactor under various conditions. At the same time, this future reactor which includes the global reactor, should solve a) the nuclear fuel resource issue, b) efficient utilization of fission energy and c) environmental issues as the greenhouse effect. (author). 7 refs., 2 figs

Temperature etalon of WWER-440 reactor

International Nuclear Information System (INIS)

Stanc, S.; Slanina, M.

2001-01-01

The presentation deals with the description, parameters and advantages of use of the temperature etalon. The system ensures temperature measurement of reactor outlet and inlet temperatures with high accuracy. Accuracy of temperature measurement is 0.18 deg C, accuracy of temperature difference measurement is 0.14 deg C, both with probability 0.95. Using the temperature etalon it is possible to increase accuracy of the standard temperature reactor measurements and to check their accuracy in the course of power reactor statuses in every measurement cycle. Temperature reactor etalon was installed in 12 WWER-440 units in Slovakia, Bohemia and Bulgaria. (Authors)

Resolution of the Task A-11 reactor-vessel materials-toughness safety issue. Appendices C-K

International Nuclear Information System (INIS)

1982-10-01

The central problem in the unresolved safety issue A-11, Reactor Vessel Materials Toughness, was to provide guidance in performing analyses required by 10 CFR Part 50, Appendix G, Section V.C. for reactor pressure vessels (RPVs) which fail to meet the toughness requirement during service life as a result of neutron radiation embrittlement. Although the methods of linear-elastic fracture mechanics (LEFM) were adequate for low-temperature RPV problems, they were inapplicable under operating conditions because vessel steels, even those which exhibit less than 50 ft-lb of C/sub v/ energy, were relatively tough at temperatures where the impact energy reached its upper shelf values. A technical team of recognized experts was organized to assist the NRC staff in addressing the problem. Using the foundation of the tearing modulus concept, which had been developed under earlier NRC sponsorship, relationships were obtained which provided approximate solutions to the problem of RPV fracture with assumed beltline region flaws. The first paper of this report is a summary of the problem, the solutions, and the results of verification analyses. The details are provided in a series of appendices in Volumes I and II

RHTF 2, a 1200 MWe high temperature reactor

International Nuclear Information System (INIS)

Brisbois, Jacques

1978-01-01

After having adapted to French conditions the 1160 MWe G.A.C. reactor, Commissariat a l'Energie Atomique and French Industry have decided to design an High Temperature Reactor 1200 MWe based on the G.A.C. technology and taking into account the point of view of Electricite de France and the experience of C.E.A. and industry on the gas cooled reactor technology. The main objective of this work is to produce a reactor design having a low technical risk, good operability, with an emphasis on the safety aspects easing the licensing problems

Biohydrogen production from pig slurry in a CSTR reactor system with mixed cultures under hyper-thermophilic temperature (70 oC)

International Nuclear Information System (INIS)

Kotsopoulos, Thomas A.; Fotidis, Ioannis A.; Tsolakis, Nikolaos; Martzopoulos, Gerassimos G.

2009-01-01

A continuous stirred tank reactor (CSTR) (750 cm 3 working volume) was operated with pig slurry under hyper-thermophilic (70 o C) temperature for hydrogen production. The hydraulic retention time (HRT) was 24 h and the organic loading rate was 24.9 g d -1 of volatile solid (VS). The inoculum used in the hyper-thermophilic reactor was sludge obtained from a mesophilic methanogenic reactor. The continuous feeding with active biomass (inoculum) from the mesophilic methanogenic reactor was necessary in order to achieve hydrogen production. The hyper-thermophilic reactor started to produce hydrogen after a short adapted period of 4 days. During the steady state period the mean hydrogen yield was 3.65 cm 3 g -1 of volatile solid added. The high operation temperature of the reactor enhanced the hydrolytic activity in pig slurry and increased the volatile fatty acids (VFA) production. The short HRT (24 h) and the hyper-thermophilic temperature applied in the reactor were enough to prevent methanogenesis. No pre-treatment methods or other control methods for preventing methanogenesis were necessary. Hyper-thermophilic hydrogen production was demonstrated for the first time in a CSTR system, fed with pig slurry, using mixed culture. The results indicate that this system is a promising one for biohydrogen production from pig slurry.

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.

Long-term adaptation of methanol-fed thermophilic (55°C) sulfate-reducing reactors to NaCl

NARCIS (Netherlands)

Vallero, M.V.G.; Lettinga, G.; Lens, P.N.L.

2003-01-01

A laboratory-scale upflow anaerobic sludge bed (UASB) reactor was operated during 273 days at increasing NaCl concentrations (0.5-12.5 g NaCl l(-1)) to assess whether the stepwise addition of the salt NaCl results in the acclimation of that sludge. The 6.5-1 thermophilic (55 degreesC), sulfidogenic

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.

The modular high-temperature gas-cooled reactor - a new production reactor

International Nuclear Information System (INIS)

Nulton, J.D.

1990-01-01

One of the reactor concepts being considered for application as a new production reactor (NPR) is a 350-MW(thermal) modular high-temperature gas-cooled reactor (MHTGR). The proposed MHTGR-NPR is based on the design of the commercial MHTGR and is being developed by a team that includes General Atomics and Combustion Engineering. The proposed design includes four modules combined into a production block that includes a shared containment, a spent-fuel storage facility, and other support facilities. The MHTGR has a helium-cooled, graphite-moderated, graphite-reflected annular core formed from prismatic graphite fuel blocks. The MHTGR fuel consists of highly enriched uranium oxycarbide (UCO) microsphere fuel particles that are coated with successive layers of pyrolytic carbon (PyC) and silicon carbide (SiC). Tritium-producing targets consist of enriched 6 Li aluminate microsphere target particles that are coated with successive layers of PyC and SiC similar to the fuel microspheres. Normal reactivity control is implemented by articulated control rods that can be inserted into channels in the inner and outer reflector blocks. Shutdown heat removal is accomplished by a single shutdown heat exchanger and electric motor-driven circulator located in the bottom of the reactor vessel. Current plans are to stack spent fuel elements in dry, helium-filled, water-cooled wells and store them for ∼1 yr before reprocessing. All phases of MHTGR fuel reprocessing have been demonstrated

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...

Regulatory use the classification security systems of I and C in VVER type reactors

International Nuclear Information System (INIS)

Ilizastegui Perez, F.

1998-01-01

Presently work the author proposes a classification to the system I and C to the VVER 440 type reactor in categories the regulatory control with a view to establishing the degree to the attention that the regulator should pay to these systems, leaving the importance that have the same ones for the security the installation, during the execution the works that are carried out with this equipment in the stages construction, setting in service and exploitation

Irradiation creep of various ferritic alloys irradiated at {approximately}400{degrees}C in the PFR and FFTF reactors

Energy Technology Data Exchange (ETDEWEB)

Toloczko, M.B.; Garner, F.A. [Pacific Northwest National Lab., Richland, WA (United States); Eiholzer, C.R. [Westinghouse Hanford Company, Richland, WA (United States)

1997-04-01

Three ferritic alloys were irradiated in two fast reactors to doses of 50 dpa or more at temperatures near 400{degrees}C. One martensitic alloy, HT9, was irradiated in both the FFTF and PFR reactors. PFR is the Prototype Fast Reactor in Dourneay, Scotland, and FFTF is the Fast Flux Test Facility in Richland, WA. D57 is a developmental alloy that was irradiated in PFR only, and MA957 is a Y{sub 2}O{sub 3} dispersion-hardened ferritic alloy that was irradiated only in FFTF. These alloys exhibited little or no void swelling at {approximately}400{degrees}C. Depending on the alloy starting condition, these steels develop a variety of non-creep strains early in the irradiation that are associated with phase changes. Each of these alloys creeps at a rate that is significantly lower than that of austenitic steels irradiated in the same experiments. The creep compliance for ferritic alloys in general appears to be {approximately}0.5 x 10{sup {minus}6} MPa{sup {minus}1} dpa{sup {minus}1}, independent of both composition and starting state. The addition of Y{sub 2}O{sub 3} as a dispersoid does not appear to change the creep behavior.

Evaluación del comportamiento hidráulico en un reactor anaerobio de doble cámara (RADCA)

OpenAIRE

Nancy Rincón; Andres Galindo; Jhonny Pérez

2011-01-01

En la remoción de carga orgánica en un sistema de tratamiento de aguas residuales intervienen los procesos bioquímico y aspectos hidrodinámicos como las características de flujo, régimen de mezcla, tiempos de residencia, geometría del reactor, por otro lado las condiciones de flujo no ideal tales como cortos circuitos, zonas muertas y recirculación interna afectan su desempeño. En esta investigación se evaluó el comportamiento hidráulico de un reactor anaerobio de doble cámara (RADCA) de 5...

Nuclear reactor

International Nuclear Information System (INIS)

Schulze, I.; Gutscher, E.

1980-01-01

The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

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.

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.

Fast reactors

International Nuclear Information System (INIS)

Vasile, A.

2001-01-01

Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

Undergraduate reactor control experiment

International Nuclear Information System (INIS)

Edwards, R.M.; Power, M.A.; Bryan, M.

1992-01-01

A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

Thermodynamic parameters and transport coefficients of the U-C-F gas mixture in the steady flow gaseous core fission reactor

International Nuclear Information System (INIS)

Berg, M.S. van den.

1995-01-01

Thermodynamic parameters and transport coefficients have been calculated for a multicomponent reacting U-C-F gas mixture in the steady flow gaseous core fission reactor. Element abundances are consistent with thermodynamic equilibrium between the gas mixture and a cooled solid graphite wall at 2500 K. Results are presented for various pressures, a fluorine potential of 5.6 and temperatures between 2500 and 7000 K. As a result of dissociation processes of uranium and carbon fluoride compounds, ''effective'' values of thermodynamic parameters and transport coefficients show anomalous behaviour with respect to so-called ''frozen'' values. The chemical reaction energy of the U-C-F gas mixture has been calculated as the driving-force behind the process of fuel redistribution to attain criticality conditions inside a functioning reactor. (author)

ROP design for Enhanced CANDU 6 reactor

Energy Technology Data Exchange (ETDEWEB)

Hu, J.; Scherbakova, D; Kastanya, D.; Ovanes, M. [Candu Energy Inc., Mississauga, Ontario (Canada)

2011-07-01

The Enhanced CANDU 6 (EC6) nuclear power plant is a mid-sized pressurized heavy water reactor design, based on the highly successful CANDU 6 (C6) family of power plants, upgraded to meet today's Canadian and international safety requirements and to satisfy Generation III expectations. The EC6 reactor is equipped with two independent Regional Overpower Protection (ROP) systems to prevent overpowers in the reactor fuel. The ROP system design, retaining the traditional C6 methodology, is determined to cover the End-of-Life (EOL) reactor core condition since the reactor operating/thermal margin gradually decreases as plant equipment ages. Several design changes have been incorporated into the reference C6 plant to mitigate the ageing effect on the ROP trip margin. This paper outlines the basis for the EC6 ROP physics design and presents the ROP related improvements made in the EC6 design to ensure that full power operation is not limited by the ROP throughout the entire life of the reactor. (author)

Development of M3C code for Monte Carlo reactor physics criticality calculations

International Nuclear Information System (INIS)

Kumar, Anek; Kannan, Umasankari; Krishanani, P.D.

2015-06-01

The development of Monte Carlo code (M3C) for reactor design entails use of continuous energy nuclear data and Monte Carlo simulations for each of the neutron interaction processes. BARC has started a concentrated effort for developing a new general geometry continuous energy Monte Carlo code for reactor physics calculation indigenously. The code development required a comprehensive understanding of the basic continuous energy cross section sets. The important features of this code are treatment of heterogeneous lattices by general geometry, use of point cross sections along with unionized energy grid approach, thermal scattering model for low energy treatment, capability of handling the microscopic fuel particles dispersed randomly. The capability of handling the randomly dispersed microscopic fuel particles which is very useful for the modeling of High-Temperature Gas-Cooled reactor fuels which are composed of thousands of microscopic fuel particle (TRISO fuel particle), randomly dispersed in a graphite matrix. The Monte Carlo code for criticality calculation is a pioneering effort and has been used to study several types of lattices including cluster geometries. The code has been verified for its accuracy against more than 60 sample problems covering a wide range from simple (like spherical) to complex geometry (like PHWR lattice). Benchmark results show that the code performs quite well for the criticality calculation of the system. In this report, the current status of the code, features of the code, some of the benchmark results for the testing of the code and input preparation etc. are discussed. (author)

Removal Site Evaluation Report to the C-Reactor Seepage Basins (904-066, -067 and -068G)

Energy Technology Data Exchange (ETDEWEB)

Palmer, E.R. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-07-01

Removal Site Evaluation Reports are prepared in accordance with Section 300.410 of the National Contingency Plan (NCP) and Section X of the Federal Facility Agreement (FFA). The C-Reactor Seepage Basins (904-066G,-067G,-068G) are listed in Appendix C, Resource Conservation and Recovery Act (RCRA)/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Units List, of the FFA. The purpose of this investigation is to report information concerning conditions at this unit sufficient to assess the threat (if any) posed to human health and the environment and to determine the need for additional CERCLA action. The scope of the investigation included a review of past survey and investigation data, the files, and a visit to the unit.Through this investigation unacceptable conditions of radioactive contaminant uptake in on-site vegetation were identified. This may have resulted in probable contaminant migration and become introduced into the local ecological food chain. As a result, the SRS will initiate a time critical removal action in accordance with Section 300.415 of the NCP and FFA Section XIV to remove, treat (if required), and dispose of contaminated vegetation from the C-Reactor Seepage Basins. Erosion in the affected areas will be managed by an approved erosion control plan. further remediation of this unit will be conducted in accordance with the FFA.

Removal Site Evaluation Report to the C-Reactor Seepage Basins (904-066, -067 and -068G)

International Nuclear Information System (INIS)

Palmer, E.R.

1997-07-01

Removal Site Evaluation Reports are prepared in accordance with Section 300.410 of the National Contingency Plan (NCP) and Section X of the Federal Facility Agreement (FFA). The C-Reactor Seepage Basins (904-066G,-067G,-068G) are listed in Appendix C, Resource Conservation and Recovery Act (RCRA)/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Units List, of the FFA. The purpose of this investigation is to report information concerning conditions at this unit sufficient to assess the threat (if any) posed to human health and the environment and to determine the need for additional CERCLA action. The scope of the investigation included a review of past survey and investigation data, the files, and a visit to the unit.Through this investigation unacceptable conditions of radioactive contaminant uptake in on-site vegetation were identified. This may have resulted in probable contaminant migration and become introduced into the local ecological food chain. As a result, the SRS will initiate a time critical removal action in accordance with Section 300.415 of the NCP and FFA Section XIV to remove, treat (if required), and dispose of contaminated vegetation from the C-Reactor Seepage Basins. Erosion in the affected areas will be managed by an approved erosion control plan. further remediation of this unit will be conducted in accordance with the FFA

Software development methodology for computer based I&C systems of prototype fast breeder reactor

International Nuclear Information System (INIS)

Manimaran, M.; Shanmugam, A.; Parimalam, P.; Murali, N.; Satya Murty, S.A.V.

2015-01-01

Highlights: • Software development methodology adopted for computer based I&C systems of PFBR is detailed. • Constraints imposed as part of software requirements and coding phase are elaborated. • Compliance to safety and security requirements are described. • Usage of CASE (Computer Aided Software Engineering) tools during software design, analysis and testing phase are explained. - Abstract: Prototype Fast Breeder Reactor (PFBR) is sodium cooled reactor which is in the advanced stage of construction in Kalpakkam, India. Versa Module Europa bus based Real Time Computer (RTC) systems are deployed for Instrumentation & Control of PFBR. RTC systems have to perform safety functions within the stipulated time which calls for highly dependable software. Hence, well defined software development methodology is adopted for RTC systems starting from the requirement capture phase till the final validation of the software product. V-model is used for software development. IEC 60880 standard and AERB SG D-25 guideline are followed at each phase of software development. Requirements documents and design documents are prepared as per IEEE standards. Defensive programming strategies are followed for software development using C language. Verification and validation (V&V) of documents and software are carried out at each phase by independent V&V committee. Computer aided software engineering tools are used for software modelling, checking for MISRA C compliance and to carry out static and dynamic analysis. Various software metrics such as cyclomatic complexity, nesting depth and comment to code are checked. Test cases are generated using equivalence class partitioning, boundary value analysis and cause and effect graphing techniques. System integration testing is carried out wherein functional and performance requirements of the system are monitored

Software development methodology for computer based I&C systems of prototype fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

Manimaran, M., E-mail: maran@igcar.gov.in; Shanmugam, A.; Parimalam, P.; Murali, N.; Satya Murty, S.A.V.

2015-10-15

Highlights: • Software development methodology adopted for computer based I&C systems of PFBR is detailed. • Constraints imposed as part of software requirements and coding phase are elaborated. • Compliance to safety and security requirements are described. • Usage of CASE (Computer Aided Software Engineering) tools during software design, analysis and testing phase are explained. - Abstract: Prototype Fast Breeder Reactor (PFBR) is sodium cooled reactor which is in the advanced stage of construction in Kalpakkam, India. Versa Module Europa bus based Real Time Computer (RTC) systems are deployed for Instrumentation & Control of PFBR. RTC systems have to perform safety functions within the stipulated time which calls for highly dependable software. Hence, well defined software development methodology is adopted for RTC systems starting from the requirement capture phase till the final validation of the software product. V-model is used for software development. IEC 60880 standard and AERB SG D-25 guideline are followed at each phase of software development. Requirements documents and design documents are prepared as per IEEE standards. Defensive programming strategies are followed for software development using C language. Verification and validation (V&V) of documents and software are carried out at each phase by independent V&V committee. Computer aided software engineering tools are used for software modelling, checking for MISRA C compliance and to carry out static and dynamic analysis. Various software metrics such as cyclomatic complexity, nesting depth and comment to code are checked. Test cases are generated using equivalence class partitioning, boundary value analysis and cause and effect graphing techniques. System integration testing is carried out wherein functional and performance requirements of the system are monitored.

Manufacture of components for Canadian reactor programs

International Nuclear Information System (INIS)

Perry, L.P.

Design features, especially those relating to calandrias, are pointed out for many CANDU-type reactors and the Taiwan research reactor. The special requirements shouldered by the Canadian suppliers of heavy reactor components are analyzed. (E.C.B.)

Engineering reactors for catalytic reactions

Indian Academy of Sciences (India)

126, No. 2, March 2014, pp. 341–351. c Indian Academy of Sciences. ... enhancement was realized by catalyst design, appropriate choice of reactor, better injection and .... Gas–liquid and liquid–solid transport processes in catalytic reactors.5.

Lead- or Lead-bismuth-cooled fast reactors

International Nuclear Information System (INIS)

Bouchter, J.C.; Courouau, J.L.; Dufour, P.; Guidez, J.; Latge, C.; Martinelli, L.; Renault, C.; Rimpault, G.

2014-01-01

Lead-cooled fast reactors are one of the 6 concepts retained for the 4. generation of nuclear reactors. So far no lead-cooled reactors have existed in the world except lead-bismuth-cooled reactors in soviet submarines. Some problems linked to the use of the lead-bismuth eutectic appeared but were satisfactorily solved by a more rigorous monitoring of the chemistry of the lead-bismuth coolant. Lead presents various advantages as a coolant: no reactivity with water and the air,a high boiling temperature and low contamination when irradiated. The main asset of the lead-bismuth alloy is the drop of the fusion temperature from 327 C degrees to 125 C degrees. The main drawback of using lead (or lead-bismuth) is its high corrosiveness with metals like iron, chromium and nickel. The high corrosiveness of the coolant implies low flow velocities which means a bigger core and consequently a bigger reactor containment. Different research programs in the world (in Europe, Russia and the USA) are reviewed in the article but it appears that the development of this type of reactor requires technological breakthroughs concerning materials and the resistance to corrosion. Furthermore the concept of lead-cooled reactors seems to be associated to a range of low output power because of the compromise between the size of the reactor and its resistance to earthquakes. (A.C.)

Method of reactor operation

International Nuclear Information System (INIS)

Maeda, Katsuji.

1982-01-01

Purpose: To prevent stress corrosion cracks in stainless steels caused from hydrogen peroxide in reactor operation in which the density of hydrogen peroxide in the reactor water is controlled upon reactor start-up. Method: A heat exchanger equipped with a heat source for applying external heat is disposed into the recycling system for reactor coolants. Upon reactor start-up, the coolants are heated by the heat exchanger till arriving at a temperature at which the dissolving rate is faster than the forming rate of hydrogen peroxide in the coolants, and nuclear heating is started after reaching the above temperature. The temperature of the reactor water is increased in such a manner and, when it arrives at 140 0 C, extraction of control elements is started and the heat source for the heat exchanger is interrupted simultaneously. In this way spikes in the density of hydrogen peroxide are suppressed upon reactor start-up to thereby decrease the stress corrosion cracks in stainless steels. (Horiuchi, T.)

Pebble bed reactors simulation using MCNP: The Chinese HTR-10 reactor

Directory of Open Access Journals (Sweden)

SA Hosseini

2013-09-01

Full Text Available   Given the role of Gas-Graphite reactors as the fourth generation reactors and their recently renewed importance, in 2002 the IAEA proposed a set of Benchmarking problems. In this work, we propose a model both efficient in time and resources and exact to simulate the HTR-10 reactor using MCNP-4C code. During the present work, all of the pressing factors in PBM reactor design such as the inter-pebble leakage, fuel particle distribution and fuel pebble packing fraction effects have been taken into account to obtain an exact and easy to run model. Finally, the comparison between the results of the present work and other calculations made at INEEL proves the exactness of the proposed model.

Potential market and characteristics of low-temperature reactors

International Nuclear Information System (INIS)

Lerouge, B.

1975-01-01

The low-temperature (100 to 200 deg C) heat market for industrial applications and district heating is very important. Two main studies have been developed: a swimming pool reactor delivering water at 110 deg C and a prestressed concrete vessel reactor delivering water at 200 deg C [fr

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

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)

Simultaneous C and N removal from saline salmon effluents in filter reactors comprising anoxic-anaerobic-aerobic processes: effect of recycle ratio.

Science.gov (United States)

Giustinianovich, Elisa A; Aspé, Estrella R; Huiliñir, César E; Roeckel, Marlene D

2014-01-01

Salmon processing generates saline effluents with high protein load. To treat these effluents, three compact tubular filter reactors were installed and an integrated anoxic/anaerobic/aerobic process was developed with recycling flow from the reactor's exit to the inlet stream in order to save organic matter (OM) for denitrification. The reactors were aerated in the upper section with recycle ratios (RR) of 0, 2, and 10, respectively, at 30°C. A tubular reactor behave as a plug flow reactor when RR = 0, and as a mixed flow reactor when recycle increases, thus, different RR values were used to evaluate how it affects the product distribution and the global performance. Diluted salmon process effluent was prepared as substrate. Using loads of 1.0 kg COD m(-3)d(-1) and 0.15 kg total Kjeldahl nitrogen (TKN) m(-3)d(-1) at HRT of 2 d, 100% removal efficiencies for nitrite and nitrate were achieved in the anoxic-denitrifying section without effect of the dissolved oxygen in the recycled flow on denitrification. Removals >98% for total organic carbon (TOC) was achieved in the three reactors. The RR had no effect on the TOC removal; nevertheless a higher efficiency in total nitrogen removal in the reactor with the highest recycle ratio was observed: 94.3% for RR = 10 and 46.6% for RR = 2. Results showed that the proposed layout with an alternative distribution in a compact reactor can efficiently treat high organic carbon and nitrogen concentrations from a saline fish effluent with OM savings in denitrification.

Effect of NaCl on thermophilic (55°C) methanol degradation in sulfate reducing granular sludge reactors

NARCIS (Netherlands)

Vallero, M.V.G.; Hulshoff Pol, L.W.; Lettinga, G.; Lens, P.N.L.

2003-01-01

The effect of NaCl on thermophilic (55degreesC) methanol conversion in the presence of excess of sulfate (COD/SO42-=0.5) was investigated in two 6.5L lab-scale upflow anaerobic sludge bed reactors inoculated with granular sludge previously not adapted to NaCl
The effect of NaCl on thermophilic

Reactor core design optimization of the 200 MWt Pb-Bi cooled fast reactor for hydrogen production

International Nuclear Information System (INIS)

Bahrum, Epung Saepul; Su'ud, Zaki; Waris, Abdul; Fitriyani, Dian; Wahjoedi, Bambang Ari

2008-01-01

In this study reactor core geometrical optimization of 200 MWt Pb-Bi cooled long life fast reactor for hydrogen production has been conducted. The reactor life time is 20 years and the fuel type is UN-PuN. Geometrical core configurations considered in this study are balance, pancake and tall cylindrical cores. For the hydrogen production unit we adopt steam membrane reforming hydrogen gas production. The optimum operating temperature for the catalytic reaction is 540degC. Fast reactor design optimization calculation was run by using FI-ITB-CHI software package. The design criteria were restricted by the multiplication factor that should be less than 1.002, the average outlet coolant temperature 550degC and the maximum coolant outlet temperature less than 700degC. By taking into account of the hydrogen production as well as corrosion resulting from Pb-Bi, the balance cylindrical geometrical core design with diameter and height of the active core of 157 cm each, the inlet coolant temperature of 350degC and the coolant flow rate of 7000 kg/s were preferred as the best design parameters. (author)

Reactor operation method

International Nuclear Information System (INIS)

Osumi, Katsumi; Miki, Minoru.

1979-01-01

Purpose: To prevent stress corrosion cracks by decreasing the dissolved oxygen and hydrogen peroxide concentrations in the coolants within a reactor container upon transient operation such as at the start-up or shutdown of bwr type reactors. Method: After a condensate has been evacuated, deaeration operation is conducted while opening a main steam drain line, as well as a main steam separation valve and a by-pass valve in a turbine by-pass line connecting the main steam line and the condenser without by way of a turbine, and the reactor is started-up by the extraction of control rods after the concentration of dissolved oxygen in the cooling water within a pressure vessel has been decreased below a predetermined value. Nuclear heating is started after the reactor water has been increased to about 150 0 C by pump heating after the end of the deaeration operation for preventing the concentration of hydrogen peroxide and oxygen in the reactor water from temporarily increasing immediately after the start-up. The corrosive atmosphere in the reactor vessel can thus be moderated. (Horiuchi, T.)

Evaluación del comportamiento hidráulico en un reactor anaerobio de doble cámara (RADCA

Directory of Open Access Journals (Sweden)

Nancy Rincón

2011-01-01

tales como cortos circuitos, zonas muertas y recirculación interna afectan su desempeño. En esta investigación se evaluó el comportamiento hidráulico de un reactor anaerobio de doble cámara (RADCA de 534,5 L (cámara 1=305 L y cámara 2= 229,5 L como innovación tecnológica de los reactores UASB. El RADCA fue alimentado con agua residual municipal (ARM de la ciudad de Maracaibo, Venezuela; cada una de las cámaras fueron inoculadas con lodo granular (20% v/v proveniente de una cervecería local. La evaluación hidráulica se realizó en la fase líquida y en operación utilizando Li+ (LiCl como trazador aplicado de forma instantánea en el afluente a tiempo de retención hidráulico teórico (TRHt de 6 horas; 3,4 h en la cámara 1 y 2,6 para la cámara 2. El RADCA describió un flujo pistón en ambas cámaras y una eficiencia hidráulica cercana a la unidad (1 indicando una presencia casi nula de zonas muertas. La eficiencia de remoción de la DQO total (DQOT del RADCA se mantuvo en el rango de 59,77% a 74,64% con un promedio de 68,26%. Para las cámaras 1 y 2 la eficiencia promedio fue 60,4 y 20,94% con una producción de biogás (L/h de 2,768 y 0,541 respectivamente.

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

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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.

Fast neutron reactor core research at the C.E.A

International Nuclear Information System (INIS)

Chaudat, J.-P.

1978-05-01

This report covers all physical studies of fast neutron reactors carried out by the C.E.A., to povide basic data (multi-group cross sections) and computer methods which may be used to calculate nuclear power plant neutron properties with the precision required by the project. The approach adopted to establish the basic data used in all core calculations is described in greated detail: choice of a reference procedure for basic mode calculations (CARNAVAL set), choice of particular experimental programs to reduce uncertainties in connection with the formula set, adjustement of cross sections on integral parameters measured on critical experiments. The development of the formula set is closely connected with the project requirements; hence the set is modified with respect to the core characteristics of the power plant studied. Following an explanation of how the CARNAVAL III and IV formula sets -used for PHENIX and SUPER-PHENIX respectively- were derived, current studies for heterogeneous cores are described [fr

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)

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

Directory of Open Access Journals (Sweden)

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.

Microstructural defect evolution in neutron – Irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing

Energy Technology Data Exchange (ETDEWEB)

Tsay, K.V.; Maksimkin, O.P.; Turubarova, L.G.; Rofman, O.V. [Institute of Nuclear Physics NNC RK, Almaty (Kazakhstan); Garner, F.A., E-mail: frank.garner@dslextreme.com [Radiation Effects Consulting, Richland, WA (United States)

2013-08-15

Transmission electron microscopy and microhardness measurements were used to examine changes in microstructure and associated strengthening induced in austenitic stainless steel 12Cr18Ni9Ti irradiated to ∼0.001 and ∼5 dpa in the WWR-K reactor before and after being subjected to post-irradiation isochronal annealing. The relatively low values of irradiation temperature and dpa rate (∼80 °C and ∼1.2 × 10{sup −8} dpa/s) experienced by this steel allowed characterization of defect microstructures over a wide range of defect ensembles, all at constant composition, produced first by irradiation and then by annealing at temperatures between 450 and 1050 °C. It was shown that the dispersed barrier hardening model with commonly accepted physical properties successfully predicted the observed hardening. It was also observed that when TiC precipitates form at higher annealing temperatures, the alloy does not change in hardness, reflecting a balance between precipitate-hardening and matrix-softening due to removal of solute-strengthening elements titanium and carbon. Such matrix-softening is not often considered in other studies, especially where the contribution of precipitates to hardening is a second-order effect.

Microstructural defect evolution in neutron – Irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing

International Nuclear Information System (INIS)

Tsay, K.V.; Maksimkin, O.P.; Turubarova, L.G.; Rofman, O.V.; Garner, F.A.

2013-01-01

Transmission electron microscopy and microhardness measurements were used to examine changes in microstructure and associated strengthening induced in austenitic stainless steel 12Cr18Ni9Ti irradiated to ∼0.001 and ∼5 dpa in the WWR-K reactor before and after being subjected to post-irradiation isochronal annealing. The relatively low values of irradiation temperature and dpa rate (∼80 °C and ∼1.2 × 10 −8 dpa/s) experienced by this steel allowed characterization of defect microstructures over a wide range of defect ensembles, all at constant composition, produced first by irradiation and then by annealing at temperatures between 450 and 1050 °C. It was shown that the dispersed barrier hardening model with commonly accepted physical properties successfully predicted the observed hardening. It was also observed that when TiC precipitates form at higher annealing temperatures, the alloy does not change in hardness, reflecting a balance between precipitate-hardening and matrix-softening due to removal of solute-strengthening elements titanium and carbon. Such matrix-softening is not often considered in other studies, especially where the contribution of precipitates to hardening is a second-order effect

Station Blackout Analysis of HTGR-Type Experimental Power Reactor

Science.gov (United States)

Syarip; Zuhdi, Aliq; Falah, Sabilul

2018-01-01

The National Nuclear Energy Agency of Indonesia has decided to build an experimental power reactor of high-temperature gas-cooled reactor (HTGR) type located at Puspiptek Complex. The purpose of this project is to demonstrate a small modular nuclear power plant that can be operated safely. One of the reactor safety characteristics is the reliability of the reactor to the station blackout (SBO) event. The event was observed due to relatively high disturbance frequency of electricity network in Indonesia. The PCTRAN-HTR functional simulator code was used to observe fuel and coolant temperature, and coolant pressure during the SBO event. The reactor simulated at 10 MW for 7200 s then the SBO occurred for 1-3 minutes. The analysis result shows that the reactor power decreases automatically as the temperature increase during SBO accident without operator’s active action. The fuel temperature increased by 36.57 °C every minute during SBO and the power decreased by 0.069 MW every °C fuel temperature rise at the condition of anticipated transient without reactor scram. Whilst, the maximum coolant (helium) temperature and pressure are 1004 °C and 9.2 MPa respectively. The maximum fuel temperature is 1282 °C, this value still far below the fuel temperature limiting condition i.e. 1600 °C, its mean that the HTGR has a very good inherent safety system.

Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

1996-12-01

This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

Environmental consequences of alternatives to L Reactor restart

International Nuclear Information System (INIS)

1983-01-01

Alternatives to renewed L-Reactor operation for increased production of nuclear materials are: restart of R Reactor, construction and operation of a New Production Reactor (NPR), increased throughput of SRP reactors C, K, and P and N Reactor at Hanford, restart of K Reactors at Hanford, and no action - standby ready state for L Reactor. This report compares the environmental consequences from the proposed L-Reactor restart and these alternatives. The environmental consequences considered are radiological releases, radiocesium remobilization, nonradiological releases, ecological impacts and transportation

New instrumentation for the IPR-R1 reactor of CDTN

International Nuclear Information System (INIS)

Carvalho, P.V.R. de.

1992-01-01

The Nuclear Engineering Institute reactor instrumentation area has developed systems and equipment for reactor operation and safety. In such way, the new I and C for IEN Argonauta reactor and the nuclear instrumentation for IPEN critical facility were built. This paper describes our real work, the new I and C systems for IPR-R1, a Triga type reactor, located at CDTN (Belo Horizonte - MG). (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)

Effects of C/N ratio on nitrous oxide production from nitrification in a laboratory-scale biological aerated filter reactor.

Science.gov (United States)

He, Qiang; Zhu, Yinying; Fan, Leilei; Ai, Hainan; Huangfu, Xiaoliu; Chen, Mei

2017-03-01

Emission of nitrous oxide (N 2 O) during biological wastewater treatment is of growing concern. This paper reports findings of the effects of carbon/nitrogen (C/N) ratio on N 2 O production rates in a laboratory-scale biological aerated filter (BAF) reactor, focusing on the biofilm during nitrification. Polymerase chain reaction-denaturing gradient gel electrophoresis (PCR-DGGE) and microelectrode technology were utilized to evaluate the mechanisms associated with N 2 O production during wastewater treatment using BAF. Results indicated that the ability of N 2 O emission in biofilm at C/N ratio of 2 was much stronger than at C/N ratios of 5 and 8. PCR-DGGE analysis showed that the microbial community structures differed completely after the acclimatization at tested C/N ratios (i.e., 2, 5, and 8). Measurements of critical parameters including dissolved oxygen, oxidation reduction potential, NH 4 + -N, NO 3 - -N, and NO 2 - -N also demonstrated that the internal micro-environment of the biofilm benefit N 2 O production. DNA analysis showed that Proteobacteria comprised the majority of the bacteria, which might mainly result in N 2 O emission. Based on these results, C/N ratio is one of the parameters that play an important role in the N 2 O emission from the BAF reactors during nitrification.

Power monitoring in space nuclear reactors using silicon carbide radiation detectors

Science.gov (United States)

Ruddy, Frank H.; Patel, Jagdish U.; Williams, John G.

2005-01-01

Space reactor power monitors based on silicon carbide (SiC) semiconductor neutron detectors are proposed. Detection of fast leakage neutrons using SiC detectors in ex-core locations could be used to determine reactor power: Neutron fluxes, gamma-ray dose rates and ambient temperatures have been calculated as a function of distance from the reactor core, and the feasibility of power monitoring with SiC detectors has been evaluated at several ex-core locations. Arrays of SiC diodes can be configured to provide the required count rates to monitor reactor power from startup to full power Due to their resistance to temperature and the effects of neutron and gamma-ray exposure, SiC detectors can be expected to provide power monitoring information for the fill mission of a space reactor.

Research reactor instrumentation and control technology. Report of a technical committee meeting

International Nuclear Information System (INIS)

1997-10-01

The majority of research reactors operating today were put into operation 20 years ago, and some of them underwent modifications, upgrading and refurbishing since their construction to meet the requirements for higher neutron fluxes. However, a few of these ageing research reactors are still operating with their original instrumentation and control systems (I and C) which are important for reactor safety to guard against abnormal occurrences and reactor control involving startup, shutdown and power regulation. Worn and obsolete I and C systems cause operational problems as well as difficulties in obtaining replacement parts. In addition, satisfying the stringent safety conditions laid out by the nuclear regulatory bodies requires the modernization of research reactors I and C systems and integration of additional instrumentation units to the reactor. In order to clarify these issues and to provide some guidance to reactor operators on state-of-art technology and future trends for the I and C systems for research reactors, a Technical Committee Meeting on Technology and Trends for Research Reactor Instrumentation and Controls was held in Ljubljana, Slovenia, from 4 to 8 December 1995. This publication summarizes the discussions and recommendations resulting from that meeting. This is expected to benefit the research reactor operators planning I and C improvements. Refs, figs, tabs

HE CADASTRAL VA LUE OF REAL ESTATE — AN INDICATOR OF THE EFFICIENCY OF CITY DEVELOPMENT PROGRAMS (ON THE EXAMPLE OF MOSCOW

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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

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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

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

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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

Gas leak tightness of SiC/SiC composites at elevated temperature

Energy Technology Data Exchange (ETDEWEB)

Hayasaka, Daisuke, E-mail: hayasaka@oasis.muroran-it.ac.jp [OASIS, Muroran Institute of Technology, Muroran, Hokkaido (Japan); Graduate School of Engineering, Muroran Institute of Technology, Muroran, Hokkaido (Japan); Park, Joon-Soo. [OASIS, Muroran Institute of Technology, Muroran, Hokkaido (Japan); Kishimoto, Hirotatsu [OASIS, Muroran Institute of Technology, Muroran, Hokkaido (Japan); Graduate School of Engineering, Muroran Institute of Technology, Muroran, Hokkaido (Japan); Kohyama, Akira [OASIS, Muroran Institute of Technology, Muroran, Hokkaido (Japan)

2016-11-01

Highlights: • NITE-SiC/SiC has extremely densified microstructure compared with other SiC/SiC composite like CVI. • Excellent helium and hydrogen gas-leak tightness of SiC/SiC composites by DEMO-NITE method from prototype industrialization production line was presented. • The excellence against stainless steel and Zircaloy at elevated temperature, together with generic excellent properties of SiC will be inevitable for innovative blanket and divertors for DEMO- and power- fusion reactors. - Abstract: SiC/SiC composite materials are attractive candidates for high heat flux components and blanket of fusion reactor, mainly due to their high temperature properties, radiation damage tolerance and low induced radioactivity. One of the challenges for SiC/SiC application in fusion reactors is to satisfy sufficient gas leak tightness of hydrogen and helium isotopes. Although many efforts have been carried-out, SiC/SiC composites by conventional processes have not been successful to satisfy the requirements, except SiC/SiC composites by NITE-methods. Toward the early realization of SiC/SiC components into fusion reactor systems process development of NITE-process has been continued. Followed to the brief introduction of recently developed DEMO-NITE process, baseline properties and hydrogen and helium gas leak tightness is presented. SiC/SiC claddings with 10 mm in diameter and 1 mm in wall thickness are tested by gas leak tightness system developed. The leak tightness measurements are done room temperature to 400 °C. Excellent gas leak tightness equivalent or superior to Zircaloy claddings for light water fission reactors is confirmed. The excellent gas leak tightness suggests nearly perfect suppression of large gas leak path in DEMO-NITE SiC/SiC.

Molten salt reactors

International Nuclear Information System (INIS)

Bouchter, J.C.; Dufour, P.; Guidez, J.; Simon, N.; Renault, C.

2014-01-01

Molten salt reactors are one of the 6 concepts retained for the 4. generation of nuclear reactors. The principle of this reactor is very innovative: the nuclear fuel is dissolved in the coolant which allows the online reprocessing of the fuel and the online recovery of the fission products. A small prototype: the Molten Salt Reactor Experiment (MSRE - 8 MWt) was operating a few years in the sixties in the USA. The passage towards a fast reactor by the suppression of the graphite moderator leads to the concept of Molten Salt Fast Reactor (MSFR) which is presently studied through different European projects such as MOST, ALISIA and EVOL. Worldwide the main topics of research are: the adequate materials resisting to the high level of corrosiveness of the molten salts, fuel salt reprocessing, the 3-side coupling between neutron transport, thermohydraulics and thermo-chemistry, the management of the changing chemical composition of the salt, the enrichment of lithium with Li 7 in the case of the use of lithium fluoride salt and the use of MSFR using U 233 fuel (thorium cycle). The last part of the article presents a preliminary safety analysis of the MSFR. (A.C.)

"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.

State of development of high temperature gas-cooled reactors in foreign countries

International Nuclear Information System (INIS)

Sudo, Yukio

1990-01-01

Emphasis has been placed in the development of high temperature gas-cooled reactors on high thermal efficiency as power reactors and the reactor from which nuclear heat can be utilized. In U.K., as the international project 'Dragon Project', the experimental Dragon reactor for research use with 20 MWt output and exit coolant temperature 750 deg C was constructed, and operated till 1976. Coated fuel particles were developed. In West Germany, the experimental power reactor AVR with 46 MWt and 15 MWe output was operated till 1988. The prototype power reactor THTR-300 with 300 MWe output and 750 deg C exit temperature is in commercial operation. In USA, the experimental power reactor Peach Bottom reactor with 40 MWe output and 728 deg C exit temperature was operated till 1974. The prototype Fort Saint Vrain power reactor with 330 MWe output and 782 deg C exit temperature was operated till 1989. In USSR, the modular VGM with 200 MWh output is at the planning stage. Also in China, high temperature gas-cooled reactors are at the design stage. Switzerland has taken part in various international projects. (K.I.)

Instrumentation and control improvements at Experimental Breeder Reactor II

International Nuclear Information System (INIS)

Christensen, L.J.; Planchon, H.P.

1993-01-01

The purpose of this paper is to describe instrumentation and control (I ampersand C) system improvements at Experimental Breeder Reactor 11 (EBR-11). The improvements are focused on three objectives; to keep the reactor and balance of plant (BOP) I ampersand C systems at a high level of reliability, to provide diagnostic systems that can provide accurate information needed for analysis of fuel performance, and to provide systems that will be prototypic of I ampersand C systems of the next generation of liquid metal reactor (LMR) plants

Studies of a modular advanced stellarator reactor ASRA6C

International Nuclear Information System (INIS)

Boehme, G.; Jentzsch, K.; Komarek, P.; Maurer, W.; El-Guebaly, L.A.; Emmert, G.A.; Kulcinski, G.L.; Larsen, E.M.; Sanatarius, J.F.; Schawan, M.E.; Scharer, J.E.; Sviatoslavski, I.N.; Vogelsang, W.F.; Walstrom, P.L.; Wittenberg, L.J.; Grieger, G.; Harmeyer, E.; Herrnegger, F.; Kisslinger, J.; Rau, F.; Wobig, H.

1987-05-01

This study is directed towards the clarification of critical issues of advanced modular stellerator reactors exploiting the inherent potential of steady state operation, and is not a point design study of a reactor. Critical technology issues arise from the three-dimensional magnetic field structure. The first wall, blanket and shield are more complex than those of axi-symmetric systems, but this is eased at moderate to large aspect ratio typical of stellerators. Several blanket options have been studied and a thin blanket (21 cm) was the first choice for the design. Superconducting modular coils were investigated with respect to the conductor and mechanical supports. From the analysis of forces and stresses caused by the electromagnetic loads the coils are considered to be feasible, although shear stresses might pose a critical issue. Demountable intermagnetic support elements were designed for use at separation areas between the cryostat modules. A scheme for remote reactor maintenance was also developed. The plasma physics issues of different configurations were studied using extrapolations of transort behaviour and equilibrium from theory and present experiments. These studies indicate that the confinement and equilibrium behaviour is adequate for ignited operation at an average value of 5% beta. Impurities may pose a critical issue. Several impurity control operations were investigated; a pumped limiter configuration utilizing the 'ergodic layer' at the plasma edge was chosen for edge plasma and impurity control. A general conclusion of the study is that the modular stellerator configuration offers interesting prospects regarding the development towards steady-state reactors. (orig.)

Studies of a modular advanced stellarator reactor ASRA6C

International Nuclear Information System (INIS)

Boehme, G.; El-Guebaly, L.A.; Emmert, G.A.; Grieger, G.; Harmeyer, E.; Herrnegger, F.; Huebener, J.; Jentzsch, K.; Kisslinger, J.; Komarek, P.; Kulcinski, G.L.; Larsen, E.M.; Maurer, W.; Rau, F.; Santarius, J.F.; Sawan, M.E.; Scharer, J.E.; Sviatoslavsky, I.N.; Vogelsang, W.F.; Walstrom, P.L.; Wittenberg, L.J.; Wobig, H.

1987-06-01

This study is directed towards the clarification of critical issues of advanced modular stellerator reactors exploiting the inherent potential of steady state operation, and is not a point design study of a reactor. Critical technology issues arise from the three-dimensional magnetic field structure. The first wall, blanket and shield are more complex than those of axi-symmetric systems, but this is eased at moderate to large aspect ratio typical of stellarators. Several blanket options have been studied and a thin blanket (21 cm) was the first choice for the design. Superconducting modular coils were investigated with respect to the conductor and mechanical supports. From the analysis of forces and stresses caused by the electromagnetic loads the coils are considered to be feasible, although shear stresses might pose a critical issue. Demountable intermagnetic support elements were designed for use at separation areas between the cryostat modules. A scheme for remote reactor maintenance was also developed. The plasma physics issues of different configurations were studied using extrapolations of transport behaviour and equilibrium from theory and present experiments. These studies indicate that the confinement and equilibrium behaviour is adequate for ignited operation at an average value of 5% beta. Impurities may pose a critical issue. Several impurity control operations were investigated; a pumped limiter configuration utilizing the 'ergodic layer' at the plasma edge was chosen for edge plasma and impurity control. A general conclusion of the study is that the modular stellerator configuration offers interesting prospects regarding the development towards steady-state reactors. (orig.) [de

Advances in light water reactor technologies

CERN Document Server

Saito, Takehiko; Ishiwatari, Yuki; Oka, Yoshiaki

2010-01-01

""Advances in Light Water Reactor Technologies"" focuses on the design and analysis of advanced nuclear power reactors. This volume provides readers with thorough descriptions of the general characteristics of various advanced light water reactors currently being developed worldwide. Safety, design, development and maintenance of these reactors is the main focus, with key technologies like full MOX core design, next-generation digital I&C systems and seismic design and evaluation described at length. This book is ideal for researchers and engineers working in nuclear power that are interested

[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...

Fuel recycling and 4. generation reactors

International Nuclear Information System (INIS)

Devezeaux de Lavergne, J.G.; Gauche, F.; Mathonniere, G.

2012-01-01

The 4. generation reactors meet the demand for sustainability of nuclear power through the saving of the natural resources, the minimization of the volume of wastes, a high safety standard and a high reliability. In the framework of the GIF (Generation 4. International Forum) France has decided to study the sodium-cooled fast reactor. Fast reactors have the capacity to recycle plutonium efficiently and to burn actinides. The long history of reprocessing-recycling of spent fuels in France is an asset. A prototype reactor named ASTRID could be entered into operation in 2020. This article presents the research program on the sodium-cooled fast reactor, gives the status of the ASTRID project and present the scenario of the progressive implementation of 4. generation reactors in the French reactor fleet. (A.C.)

Integrity of the first wall in fusion reactors

International Nuclear Information System (INIS)

Kurihara, Ryoichi

2004-07-01

Future fusion power reactors DREAM and A-SSTR2, which have been conceptually designed in the Japan Atomic Energy Research Institute, use the SiC/SiC composite material as the first wall of the blanket because of its characteristics of high heat-resistance and low radiation material. DEMO reactor, which was conceptually designed in 2001, uses the low activation ferritic steel as the first-wall material of the blanket. The problems in the thermal structural design of the plasma facing component such as the blanket first wall and the divertor plate which receives very high heat flux were examined in the design of the fusion power reactors. Compact high fusion power reactor must give high heat flux and high-speed neutron flux from the plasma to the first wall and the divertor plate. In this environmental situation, the micro cracks should be generated in material of the first wall. Structural integrity of the first wall would be very low during the operation of the reactor, if those micro-cracks grow in a crack having significant size by the fatigue or the creep. The crack penetration in the first wall can be a factor which threatens the safety of the fusion power reactor. This paper summarizes the problems on the structural integrity in the first wall made of the SiC/SiC composite material or the ferritic steel. (author)

Calcium oxide/carbon dioxide reactivity in a packed bed reactor of a chemical heat pump for high-temperature gas reactors

International Nuclear Information System (INIS)

Kato, Yukitaka; Yamada, Mitsuteru; Kanie, Toshihiro; Yoshizawa, Yoshio

2001-01-01

The thermal performance of a chemical heat pump that uses a calcium oxide/carbon dioxide reaction system was discussed as a heat storage system for utilizing heat output from high temperature gas reactors (HTGR). Calcium oxide/carbon dioxide reactivity for the heat pump was measured using a packed bed reactor containing 1.0 kg of reactant. The reactor was capable of storing heat at 900 deg. C by decarbonation of calcium carbonate and generating up to 997 deg. C by carbonation of calcium oxide. The amount of stored heat in the reactor was 800-900 kJ kg -1 . The output temperature of the reactor could be controlled by regulating the carbonation pressure. The thermal storage performance of the reactor was superior to that of conventional sensible heat storage systems. A heat pump using this CaO/CO 2 reactor is expected to contribute to thermal load leveling and to realize highly efficient utilization of HTGR output due to the high heat storage density and high-quality temperature output of the heat pump

Lower activation materials and magnetic fusion reactors

International Nuclear Information System (INIS)

Conn, R.W.; Bloom, E.E.; Davis, J.W.; Gold, R.E.; Little, R.; Schultz, K.R.; Smith, D.L.; Wiffen, F.W.

1984-01-01

Radioactivity in fusion reactors can be effectively controlled by materials selection. The detailed relationship between the use of a material for construction of a magnetic fusion reactor and the material's characteristics important to waste disposal, safety, and system maintainability has been studied. The quantitative levels of radioactivation are presented for many materials and alloys, including the role of impurities, and for various design alternatives. A major outcome has been the development of quantitative definitions to characterize materials based on their radioactivation properties. Another key result is a four-level classification scheme to categorize fusion reactors based on quantitative criteria for waste management, system maintenance, and safety. A recommended minimum goal for fusion reactor development is a reference reactor that (a) meets the requirements for Class C shallow land burial of waste materials, (b) permits limited hands-on maintenance outside the magnet's shield within 2 days of a shutdown, and (c) meets all requirements for engineered safety. The achievement of a fusion reactor with at least the characteristics of the reference reactor is a realistic goal. Therefore, in making design choices or in developing particular materials or alloys for fusion reactor applications, consideration must be given to both the activation characteristics of a material and its engineering practicality for a given application

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

Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors

Directory of Open Access Journals (Sweden)

H. Ushida

2016-12-01

Full Text Available Under tritium production method using a high-temperature gas-cooled reactor loaded Li compound, Li compound has to be coated by ceramic materials in order to suppress the spreading of tritium to the whole reactor. Pyrolytic carbon (PyC is a candidate of the coating material because of its high resistance for gas permeation. In this study, hydrogen permeation experiments using a PyC-coated isotropic graphite tube were conducted and hydrogen diffusivity, solubility and permeability were evaluated. Tritium permeation behavior through PyC-coated Li compound particles was simulated by using obtained data. Hydrogen permeation flux through PyC in a steady state is proportional to the hydrogen pressure and is larger than that through Al2O3 which is also candidate coating material. However, total tritium leak within the supposed reactor operation period through the PyC-coated Li compound particles is lower than that through the Al2O3-coated ones because the hydrogen absorption capacity in PyC is considerably larger than that in Al2O3.

Rise-to-power test in High Temperature Engineering Test Reactor. Test progress and summary of test results up to 30 MW of reactor thermal power

International Nuclear Information System (INIS)

Nakagawa, Shigeaki; Fujimoto, Nozomu; Shimakawa, Satoshi

2002-08-01

The High Temperature Engineering Test Reactor (HTTR) is a graphite moderated and gas cooled reactor with the thermal power of 30 MW and the reactor outlet coolant temperature of 850degC/950degC. Rise-to-power test in the HTTR was performed from April 23rd to June 6th in 2000 as phase 1 test up to 10 MW in the rated operation mode, from January 29th to March 1st in 2001 as phase 2 test up to 20 MW in the rated operation mode and from April 14th to June 8th in 2001 as phase 3 test up to 20 MW in the high temperature test the mechanism of the reactor outlet coolant temperature becomes 850degC at 30 MW in the rated operation mode and 950degC in the high temperature test operation mode. Phase 4 rise-to-power test to achieve the thermal reactor power of 30 MW started on October 23rd in 2001. On December 7th in 2001 it was confirmed that the thermal reactor power and the reactor outlet coolant temperature reached to 30 MW and 850degC respectively in the single loaded operation mode in which only the primary pressurized water cooler is operating. Phase 4 test was performed until March 6th in 2002. JAERI (Japan Atomic Energy Research Institute) obtained the certificate of the pre-operation test from MEXT (Ministry of Education Culture Sports Science and Technology) after all the pre-operation tests by MEXT were passed successfully with the reactor transient test at an abnormal event as a final pre-operation test. From the test results of the rise-up-power test up to 30 MW in the rated operation mode, performance of the reactor and cooling system were confirmed, and it was also confirmed that an operation of reactor facility can be performed safely. Some problems to be solved were found through the tests. By solving them, the reactor operation with the reactor outlet coolant temperature of 950degC will be achievable. (author)

Calculation of the power distribution in the fuel rods of the low power research reactor using the MCNP4C code

International Nuclear Information System (INIS)

Dawahra, S.; Khattab, K.

2011-01-01

Highlights: → The MCNP4C code was used to calculate the power distribution in 3-D geometry in the MNSR reactor. → The maximum power of the individual rod was found in the fuel ring number 2 and was found to be 105 W. → The minimum power was found in the fuel ring number 9 and was 79.9 W. → The total power in the total fuel rods was 30.9 kW. - Abstract: The Monte Carlo method, using the MCNP4C code, was used in this paper to calculate the power distribution in 3-D geometry in the fuel rods of the Syrian Miniature Neutron Source Reactor (MNSR). To normalize the MCNP4C result to the steady state nominal thermal power, the appropriate scaling factor was defined to calculate the power distribution precisely. The maximum power of the individual rod was found in the fuel ring number 2 and was found to be 105 W. The minimum power was found in the fuel ring number 9 and was 79.9 W. The total power in the total fuel rods was 30.9 kW. This result agrees very well with nominal power reported in the reactor safety analysis report which equals 30 kW. Finally, the peak power factors, which are defined as the ratios between the maximum to the average and the maximum to the minimum powers were calculated to be 1.18 and 1.31 respectively.

Gas-cooled breeder reactor safety

Energy Technology Data Exchange (ETDEWEB)

Chermanne, J.; Burgsmueller, P. [Societe Belge pour l' Industrie Nucleaire, Brussels

1981-01-15

The European Association for the Gas-cooled Breeder Reactor (G B R A), set-up in 1969 prepared between 1972 and 1974 a 1200 MWe Gas-cooled Breeder Reactor (G B R) commercial reference design G B R 4. It was then found necessary that a sound and neutral appraisal of the G B R licenseability be carried out. The Commission of the European Communities (C E C) accepted to sponsor this exercise. At the beginning of 1974, the C E C convened a group of experts to examine on a Community level, the safety documents prepared by the G B R A. A working party was set-up for that purpose. The experts examined a ''Preliminary Safety Working Document'' on which written questions and comments were presented. A ''Supplement'' containing the answers to all the questions plus a detailed fault tree and reliability analysis was then prepared. After a final study of this document and a last series of discussions with G B R A representatives, the experts concluded that on the basis of the evidence presented to the Working Party, no fundamental reasons were identified which would prevent a Gas-cooled Breeder Reactor of the kind proposed by the G B R A achieving a satisfactory safety status. Further work carried out on ultimate accident have confirmed this conclusion. One can therefore claim that the overall safety risk associated with G B R s compares favourably with that of any other reactor system.