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Sample records for bucharest wwr-s reactor

  1. Decommissioning of the nuclear research reactor WWR-S at Magurele-Bucharest, Romania

    International Nuclear Information System (INIS)

    The WWR-S Nuclear Research Reactor of Horia Hulubei National Institute of Physics and Nuclear Engineering at Magurele-Bucharest will be decommissioned. The strategy selected was the immediate dismantling. 2010 was the first year of the project. Duration of the decommissioning project will be 11 years. Three phases of decommissioning will be necessary for finalizing the entire project. In the first 4 years the planning is to repatriate to Russian Federation all the low enriched uranium nuclear fuel of type EK-10 irradiated assemblies, while in the framework of US Department of Energy - National Nuclear Security Administration Program concerning the Russian Research Reactor Fuel Return - RRRFR, all the highly enriched uranium spent fuel assemblies of type C-36 were repatriated from Magurele site to Russian Federation in June 2009. Also, in the first three years of the project, the Radioactive Waste Treatment Plant located at the same site as the WWR-S research reactor, will be up-graded to ensure the proper processing of the materials resulted from decommissioning activities. For executing the Dismantling and Decontamination activities there were selected, as best option, the participation the members team of operators and engineers from research reactor. End state of the decommissioning project will be reutilization of the buildings for sitting a new electron linear accelerator with maximum 10 MeV energy used in material sciences studies and applications. Commercial equipment obtained during deployment the IAEA Technical Cooperation Project (2004-2008), technical cooperation project with US Argonne National Laboratory (2003-2007), EU PHARE project (2008-2009), US RRRFR program (2004-2009) and national projects will be used in decommissioning project. Good practices in planning, organization, funding and logistics will be described in the paper. (authors)

  2. Preliminary decommissioning plan for research reactor WWR-S, Bucharest, Magurele

    International Nuclear Information System (INIS)

    Preliminary plan for WWR-S Bucharest reactor decommissioning was developed in the frame of Technical Assistance Project ROM/9/017, sustained by IAEA Vienna. This plan takes into account the IAEA recommendations and is built on the decommissioning methodology usually adopted in European Union. The plan is based on the research activity of our laboratory, the works performed together with international experts and the expertise knowledge acquired during the visits abroad and fellowships. Also, the plan contains the results of the PHARE Project PH 04.1/1994 referring to safety, health physics, management of wastes and spent fuel. We developed: - a calculation system for radioactive inventory; - methods for determination of impurities in structural materials of the reactor; - methods for radiological characterization of the technological areas of the reactor; - mapping methods for environmental characterization on the waste routes; - method for evaluation of the in-deep contamination for concrete used in the reactor. A cost analysis code was implemented in order to perform an estimation of the funds necessary for development of the project. Activities related with the decommissioning plan of this reactor have been developed in a cooperation with VKTA Rossendorf, Germany covering the following topics: - health physics and environmental surveillance; - spent fuel management; - wastes arising from decommissioning; - intercomparison of calculation methods. (author)

  3. Decommissioning of research nuclear reactor WWR-S Bucharest. Analysis, justification and selection of decommissioning strategy

    International Nuclear Information System (INIS)

    The decommissioning of Research Nuclear Reactor WWR-S Bucharest involves the removal of the radioactive and hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. The National Institute of Physics and Nuclear Engineering has overall responsibilities in decommissioning including actions of contractors, submit a decommissioning plan to the regulatory body for approval and no decommissioning activities shall begin without the appropriate approval of the regulatory body. A very important aspect of decommissioning is analysis, justification and selection of decommissioning strategy. There are three strategies: Immediate Dismantling, Safe Enclosure, and Entombment. These strategies have been analyzed taking into account: - Future use of site and facilities; - Infrastructure of the specific site and facilities; - Waste storage and disposal options; - Financial aspects; - Geographical Location; - National, Local and International Legislation; - Facility characterization; Identification of decommissioning objectives; - Description of alternatives: scope, features, specific end points, release criteria, risks and safety issues, effectiveness, feasibility, nature and amount of waste of generated and disposal plans, material recycling/reusing opportunities, cost, schedule, comparative analysis; - Rationale for selecting the preferred alternative. (authors)

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

    International Nuclear Information System (INIS)

    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

  5. Stage of decommissioning of the WWR-S research nuclear reactor at Magurele-Bucharest

    International Nuclear Information System (INIS)

    Full text: A decommissioning project is performed on the nuclear facility research reactor WWR-S Magurele-Bucharest to remove the radioactive and hazardous materials to avoid any risk to human health and the environment. The project involves four phases, namely: assessment, development, activity implementation and closeout. There are two major parts of 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 alternatives will be considered, the best alternative chosen, final goal identified, risk assessments evaluated, and issues of regulations supporting assessment, land use considerations, financial problems, disposal availability, public involvement, and technology developments will be appropriately solved. After a decommissioning alternative is chosen, detailed engineering will begin following appropriate regulatory guidance. The plan requires 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 the following: scheduling, preparation for decommissioning operations, coordination, documentation, characterization, report, feasibility studies, Decommissioning Plan, project report day to day, radiological survey, airborne sampling records, termination survey of the site. Key concerns in operations are worker protection, health and safety program, review of planing work, work area assessment, work area controls, personal protection and monitoring, environmental protection: air quality, surface water, ground water, shipments, effluent sampling and monitoring, environmental monitoring, site release

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

    International Nuclear Information System (INIS)

    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

  7. Safety report on WWR-S reactor

    International Nuclear Information System (INIS)

    The present Safety Report of the WWR-S reactor summarizes findings obtained during the trial and partially also permanent operation of the reactor after two stages of its reconstruction implemented between 1974 and 1976. Most data are presented necessary for assessing probable risks of possible accident conditions whose consequences pose health hazards to individuals of the population, radiation personnel and the facilities themselves. Attention is devoted to the description of the locality, to components and systems, heat removal from the core, design aspects, the quality of new and old parts of the technological circuits, the systems of protection and control, the emergency core cooling system, the problems of radiation safety, and to the safety analyses of the abnormal states envisaged. The Report was compiled with regard to IAEA and CMEA recommendations concerning safe operation of research reactors and to the recommendations and binding decisions of the Czechoslovak Atomic Energy Commission. (author)

  8. First stage of the WWR-S reactor reconstruction

    International Nuclear Information System (INIS)

    The technical development of the WWR-S reactor from its start-up in 1957 up to the present time is briefly described. The targets of the first stage of the facility reconstruction are formulated. This stage was accomplished in 1974. Attention is devoted to the description of refuelling and to some design details of the reactor core, of the control and protection system and finally to the experience with and the results of the reactor physical start-up. The volume of work carried out and described creates the pre-conditions for the successful materialization of the second stage of the reconstruction aimed at increasing of the reactor thermal output to 10 MW. (author)

  9. The Waste Management Plan integration into Decommissioning Plan of the WWR-S research reactor from Romania

    International Nuclear Information System (INIS)

    The paper presents the progress of the Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor WWR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for WWR-S decommissioning was also developed. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the IAEA assistance. Environmental concerns are part of the radioactive waste management strategy. (authors)

  10. Safe decommissioning of WWR-S Romania research reactor

    International Nuclear Information System (INIS)

    WWR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotope production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was a 2-stage plan (in IAEA definition). In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH/04.1/1994 dedicated to the 'Study of Soviet Design Research Reactors' had consolidated the development of the project emphasizing technical option of safe management for radioactive wastes and WWR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to establishing of strategy for safe management of decommissioning. Technical analysis of WWR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita - Bihor) proved the possibility of classical method utilization for nuclear facility dismantling, treatment-conditioning-disposal of the arising wastes in safe conditions. The 2-stage IAEA decommissioning plan has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by R and D program including neutron calculation and experiments, radiological characterization (for facility and its influenced area), seismic analysis and environmental balance during the operation and after reactor shut down. A special chapter is dedicated to regulatory issues concerning development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for decommissioning of research

  11. WWR-S IFIN - HH research reactor decommissioning

    International Nuclear Information System (INIS)

    The paper presents the issues referring to the decommissioning of WWR-S research reactor, built in 1957 and shut down at the end of 1997. There are given: - General data; - Reactor characteristics; - Radioactive inventory in spent fuel (calculated at the and of 1999); - Radioactive inventory due to the neutron activation; - Results of contamination measurements for reactor components as well as technological areas; - The commissioning strategy development under international projects. There is also presented the list of components which will not be dismantled according to the established strategy. The radioactive waste arose in decommissioning are categorized as: - Wastes from dismantling of the primary circuit; - Historical wastes from research as well as reactor operation; Wastes from dismantling of control-command system; Wastes from dismantling of hot cells. Except for radwastes from reactor internals which are due to neutron activation, all the wastes are resulting from radioactive contamination. Other issues discussed are related to the treatment, conditioning and radwaste storage.The cost evaluation, planning of decommissioning as well as the funding arrangements are also given in this contribution. The documentation which can be used in the process is divided in two parts, one already worked out and the other which is to be developed. The management of the project and the relationships with civil society as beneficiary of the decommissioning of obsolete risky facilities are considered important. Romanian Government supported R-D works referring to this objective by: Funding from state - Budget of research for defining the decommissioning strategy, for developing the computational methods as well as for radiological characterization of facilities, waste routes and influence area; - Great support for international cooperation (IAEA Vienna, PHARE, bilateral agreements), by TAP ROM/9/017, ROM/9/017/EXTENDED, PH04.1/1994. A special place in the development of

  12. The structure of decommissioning plan for WWR-S research reactor

    International Nuclear Information System (INIS)

    The WWR-S IPNE reactor, situated in the village Magurele near Bucharest, has been put in operation at the 27th of July, 1957 and it was continuously operated without major events, up to present moments. During this period there were not made any modifications concerning the core and main circuits. The reactor operates with the original equipment and control instrumentation supplied by Soviets. The reactor is designed and built at the scientific and technological level of 50's. During the life-cycle of a nuclear facility, decommissioning is a definite phase which begins with the final closure of the facility and ends with the release of the site for unrestricted use. Regardless of why a facility is permanently shut down, the three commonly accepted stages in the decommissioning process are: - Stage 1, or storage under surveillance; - Stage 2, or restricted site use; - Stage 3, or unrestricted site use. In view of the present situation the recommendation of the IAEA Experts on strategy is: decommissioning to Stage 2 as a preferable and viable option. When reliable cost estimates and more complete radiological characterization are available, the strategy shall be reviewed because early decommissioning to the Stage 3 must not be entirely excluded. There is no obvious reasons to defer Stage 3 other than costs and waste management capability. (authors)

  13. Study of the WWR-S-NIPNE-HH reactor main components state, after 40 years working, using non-destructive methods

    International Nuclear Information System (INIS)

    In the framework of periodical inspections and verifications of the nuclear research reactor WWR-S were established to be perform some tests and investigations destined to ensure that there are available concordances with the security requirements and that the security state of the reactor didn't decrease given the initial state. Their aim is to obtain information regarding the technical state and the ability of the components, systems and installations to work properly in conditions of high security level in accordance with the Safety Analysis Report of Nuclear Research Reactor WWR-S from NIPNE-HH, Bucharest (1997), and at the level guaranteed from the initial state. By initial state we mean the state of first commissioning. (author)

  14. Technical glasses: electrical properties and behaviour in nuclear reactor WWR-S

    International Nuclear Information System (INIS)

    Samples of SIMAX, SIAL, PN, UNIHOST, KS-80 and KS-90 were irradiated in a WWR-S reactor and their electric conductivity was studied. A decrease in conductivity was found following the irradiation with thermal neutron fluence of 2.0x1023 n.m-2, which is characteristic of the individual types of glass. In the reactor channel heat generation was compared for glass containing boron (SIMAX, SUPREMAX) and boron-free glass (UNIHOST). Boron-free glass showed an increase within the limits of the temperature measurement error while both borosilicate types of glass showed a local increase of temperature of 39 K and 33 K, respectively, at temperatures of 350 to 390 degC. (author)

  15. Time behaviour evaluation of WWR-S IFIN-HH reactor spent fuel characteristics using the SCALE4.3 computational system

    International Nuclear Information System (INIS)

    The time evolution of the radioactive inventory, gamma and neutron sources, and thermal power of the WWR-S IFIN-HH reactor spent fuel is calculated in this work via SCALE4.3 computational system. The evaluation of these spent fuel characteristics needed for the storage variant analysis is based on a method previously established in IFIN-HH, Bucharest consisting in burnup calculations by means of ORIGEN-S code which applies specific problem dependent libraries defined for classes of fuel elements and processed with SAS2H, SCALE calculation module. The reliability of the calculations performed was tested by comparison against similar calculation, for same representative fuel elements, performed by ORIGEN-JR and HELIOS codes in VKTA Rossendorf. Four reference time of 5, 10, 25, and 50 years after the date 31st December, 1999 were taken into account. Detailed results for all 222 fuel assemblies of both types i.e., EK-10 and S36, irradiated in the reactor are presented and discussed into the paper. The WWR-S IFIN-HH Spent Fuel Archive System 'S.F.A.S' ACCESS Database that was achieved is also discussed. (authors)

  16. Dose rate time evolution for the activities of WWR-S IFIN - HH reactor internal structures

    International Nuclear Information System (INIS)

    This paper reports the results of a work, carried out under IAEA Vienna contract, aiming at getting information concerning the working conditions of the personnel involved in decommissioning and the decommissioning variant to be chosen. According to the decommissioning strategy for the WWR-S IFIN - HH reactor, the most of the reactor tank will remain on place except for some internal components which have to be extracted and disposed. Time behaviour of the dose rates for the reactor internal components is evaluated by means of the code MERCURE-3. The gamma activity was computed by means of ORIGEN code by using a neutron flux obtained from a 2-D calculation carried out with the TWOTRAN program. The reactor irradiation history as well as the 100 days, 6, 10, 25 and 50 years spans after reactor shutdown were taken into account. For the internal components situated near the horizontal channels and thermal column a reference system located at the component position was used in calculation. For large components like reactor vessels, iron and concrete shieldings, corrections were introduced to account for the influence of horizontal channels and thermal column. On the other hand for these latter components a sophisticated algorithm, correcting for photon sources was created. In order to obtain a configuration as real as possible detailed computation models were conceived using the point kernel method. Time dependences of the dose rates resulting from the computation of components' areas namely for surface area + 20 cm, + 100 cm, + 200 cm, + 800 cm, + 1000 cm are presented. The dose rates corresponding for the whole reactor vessel assembly show a rapid decrease in the first six years followed by a steep exponential decrease, while after six years a simple exponential decay remains due mainly to the predominant radioactive isotope 63 Ni. Measurement values for components from other WWR-S decommissioned reactors appear to be an order of magnitude lower than the values

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

    International Nuclear Information System (INIS)

    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 cm2; the

  18. Reconstruction of the WWR-S reactor. I. Switch-over to IRTM fuel

    International Nuclear Information System (INIS)

    The findings are briefly reviewed gained in the first stage of the WWR-S reactor reconstruction aimed at achieving a thermal output of 1O MW. The principle of the reconstruction consists in the use of a new type of fuel, IRT-M, in place of EK-10 used so far. The new fuel assembly consists of four fuel elements in the shape of rectangular cross-section concentric tubes having a wall thickness of 2 mm, the kernel consists of a uranium-aluminium alloy with 80% U 235 enrichment. With this type of fuel, the reactor core has high reactivity excess in spite of a relatively small number of fuel assemblies used (26 pcs) and may operate at high thermal load, which permits obtaining high neutron flux, i.e., 1014 n/cm2s for thermal neutrons. The number of regulating rods has been increased from 9 to 12, the reactor control and protection system has been entirely reconstructed and other necessary adaptations of the core have been made. During physical start-up criticality was verified of various core configurations, such as a configuration featuring a light-water moderator and a central beryllium neutron absorber, a compact configuration with a light-water moderator and an operating configuration with a light-water reflector and 4 loop channels in the peripheral region. In all these cases critical mass and reactivity excess was determined. So far, the reactor achieves an output of 2 MW; in stage two of the reconstruction, heat removal from the reactor including the emergency core cooling system is to be solved. (Z.M.)

  19. Personnel training program for WWR-S Nuclear Research Reactor - on the radiological characterization and cleanup activities

    International Nuclear Information System (INIS)

    The aim of this program is the development of competence by training, acquiring, extending and maintaining competence, using fundamental or refreshment training courses. Progress and suited approach are established based on the list with tasks and subjects to be assimilated. According to 'graded approach to training' method the training process will be assessed from initial training-to-training evaluation at the working place. The program responsible of and participants will provide a detailed report that will describe the progress, achieved competence area and the future training necessities. Report form will be given to the participants at the beginning of the training, which will be completed during the program. It will be taken in account that the Nuclear Reactor WWR-S is in the conservation phase for the Nuclear Reactor and the exploitation of the Nuclear Spent Fuel Ponds (Away from Reactor-AFR) - both phases are authorized by the Regulatory Body (CNCAN), as transition phase from the operating-shut-down-conservation phase and the decommissioning preparing: clean-up, maintaining and improvement of the nuclear safety, technical documentation elaboration, maintenance activities. (authors)

  20. Decommissioning of research nuclear reactor WWER-S Magurele-Bucharest

    International Nuclear Information System (INIS)

    A decommissioning project is performed on a nuclear facility, the WWR-S research reactor at Magurele-Bucharest to remove the radioactive and hazardous materials in order to avoid any risks to human health and the environment. The project involves four phases, namely: assessment, development, activities implementation 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 the 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 is identified, risk assessments are evaluated, regulations supporting assessment will be identified, land use will be considered as well as the financial sources, disposal availability, public involvement, and the technology developments. After the decommissioning alternative is chosen, detailed engineering issues will be approached under appropriate regulatory guidance. The plan will include characterisation information, review of decommissioning alternatives, justification for the selected alternative, provision for regulatory compliance, evaluations of personnel exposure, radioactive waste volume, and cost. Other activities are: scheduling, preparation for decommissioning operations, coordination, documentation, characterization, report, feasibility studies, decommissioning plan, daily project report, radiological survey, airborne sampling records, termination survey of the site. The key operations are: worker protection, health and safety program, review of planing work, work area assessment, work area controls, personal protection and monitoring, environmental protection: air quality, surface water, ground water, shipments, effluent sampling and monitoring, environmental monitoring, site release

  1. Decommissioning of research reactors

    International Nuclear Information System (INIS)

    Research reactors of WWR-S type were built in countries under Soviet influence in '60, last century and consequently reached their service life. Decommissioning implies removal of all radioactive components, processing, conditioning and final disposal in full safety of all sources on site of radiological pollution. The WWR-S reactor at Bucuresti-Magurele was put into function in 1957 and operated until 1997 when it was stopped and put into conservation in view of decommissioning. Presented are three decommissioning variants: 1. Reactor shut-down for a long period (30-50 years) what would entail a substantial decrease of contamination with lower costs in dismantling, mechanical, chemical and physical processing followed by final disposal of the radioactive wastes. The drawback of this solution is the life prolongation of a non-productive nuclear unit requiring funds for personnel, control, maintenance, etc; 2. Decommissioning in a single stage what implies large funds for a immediate investment; 3. Extending the operation on a series of stages rather phased in time to allow a more convenient flow of funds and also to gather technical solutions, better than the present ones. This latter option seems to be optimal for the case of the WWR-S Research at Bucharest-Magurele Reactor. Equipment and technologies should be developed in order to ensure the technical background of the first operations of decommissioning: equipment for scarification, dismantling, dismemberment in a highly radioactive environment; cutting-to-pieces and disassembling technologies; decontamination modern technologies. Concomitantly, nuclear safety and quality assurance regulations and programmes, specific to decommissioning projects should be implemented, as well as a modern, coherent and reliable system of data acquisition, recording and storing. Also the impact of decommissioning must be thoroughly evaluated. The national team of specialists will be assisted by IAEA experts to ensure the

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

    International Nuclear Information System (INIS)

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

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

    International Nuclear Information System (INIS)

    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

  4. Outlook on radioisotope production at TRIGA SSR 14 MW reactor

    International Nuclear Information System (INIS)

    INR Pitesti, endowed with a research nuclear reactor of TRIGA SSR 14 MW type, has developed activities of radioisotope production, being at present licensed for production and selling Ir-192 sources for industrial gamma radiography and Co-60 sources (2,000 Ci) for medical uses (cobalto therapy). A collaboration was initiated with the CPR Department of IFIN-HH Bucharest, particularly after the WWR-S reactor shutdown on December 21, 1997. In the frame of this program the INR Pitesti offers services of raw material irradiations followed by the radioisotope production performed subsequently at the Radioisotope Production Department (CPR) of IFIN-HH Bucharest which also deals with selling the product on internal market . The experimental facilities with the two TRIGA reactors (TRIGA SSR 14 MW and TRIGA ACPR) of INR Pitesti are described. The maximum neutron flux is 2.9 · 1014 n/cm2s. The irradiation channels are of two neutron spectra types. Also the neutron flux is characterized by radial and axial distribution which are taken into account when a given raw material is to be irradiated, to avoid perturbing non-homogeneities in the raw material activation. Five irradiation devices are presented. Preparations are currently under way for production of fission radioisotopes Mo-99, I-131 and Xe-133 and activation radioisotope I-125 for medical application

  5. Dose calculation for accident situations at WWR-S type spent nuclear fuel repository

    International Nuclear Information System (INIS)

    Full text: The Spent Nuclear Fuel Repository at IFIN-HH Bucharest (SNFR IFIN-HH) consists in four pools, repository hall, radiological monitoring system, ventilation system and auxiliary systems. At the moment the remaining activity in the repository is about 3500 Ci. Despite of the small activity, for emergency preparedness purposes, several accident scenarios, with a non zero probability of occurrence during the repository lifetime, have been postulated. Evaluations of radiological consequences to personnel, general public and environment, for each accident scenario have been performed. The radioactive inventory was evaluated with ORIGEN code from SCALE computer code system and radiological consequences were evaluated with COSYMA computer code. Assumptions for the source term determination, meteorological conditions and release, are presented. The calculated values of doses and risk are also presented. The impact of these accident scenarios on population and environment is also discussed. (authors)

  6. 1977 Bucharest, Romania Images

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — 1,500 reported killed, 10,500 injured, and extensive damage in the Bucharest area. Bulgaria reported 20 killed and 165 injured. Moscow reported some damage in the...

  7. Groundwater Monitoring and Control Before Decommissioning of the Research Reactor VVR-S from Magurele-Bucharest

    International Nuclear Information System (INIS)

    The research reactor type VVR-S (tank type, water is cooler, moderator and reflector, thermal power- 2 MW, thermal energy- 9. 52 GW d) was put into service in July 1957 and, in December 1997 was shout down. In 2002, Romanian Government decided to put the research reactor in the permanent shut-down in order to start the decommissioning. This nuclear facility was used in nuclear research and radioisotope production for 40 years, without events, incidents or accidents. Within the same site, in the immediate vicinity of the research reactor, there are many other nuclear facilities: Radioactive Waste Treatment Plant, Tandem Van der Graaf heavy ions accelerator, Cyclotron, Industrial Irradiator, Radioisotope Production Center. The objectives of this work were dedicated on the water underground analyses described in the following context: - presentation of the approaches in planning the number of drillings, vertical soil profiles (characteristics, analyses, direction of the flow of underground water, uncertainties in measurements); - presentation of the instrumentation used in analyses of water, soil and vegetation samples - analyses and final conclusions on results of the measurements; - comparison of the results of measurements on underground water from drillings with the measurements results on samples from the town and the system of drinking water - supplied from the second level of underground water. According to the analysis, in general, no values higher than the Minimum Detectable Activity were detected in water samples (MDA) for Pb212, Bi214, Pb214, Ac228, but situated under values foreseen in drinking water. Distribution of Uranium As results of the Uranium determination, values higher than 0,004 mg/l (4 ppb) were detected, values that represent the average contents in the underground water. The higher values, 2-3 times higher than background, were detected in the water from the drillings F15, F12, F5, F13, drillings located between RWTP (Radioactive Waste

  8. Reactor neutron activation analysis on reference materials from intercomparison runs

    International Nuclear Information System (INIS)

    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)

  9. Bucharest urban seismology

    International Nuclear Information System (INIS)

    An important project was carried out in Bucharest area by the National Institute of Research-Development for Earth Physics and Collaborative Research Center 461 (CRC 461) Geophysical Institute from the University of Karlsruhe (Germany) in the period October 2003 - August 2004. The project consists of an array of 33 stations, uniformly arranged in the city of Bucharest and in the outskirts (Magurele, Voluntari, Otopeni, Buftea, etc). The station functioned 24 h/day for a period of 10 months. The number of functioning stations had a little variation in time, some of them had to be moved because some sites became improper in time. The sensors used by the stations were of the type: STS - 2, LE - 3D, 4OT, 3ESP and KS2000. The performance of continuous recording was possible by using on each station a hard disk drive of 120 Gb, which gives independence of 3 month. For preventing some accidental electric power stops a rechargeable battery on each station was used . A service was performed for each station every month to avoid accidental stops, which consisted usually of mechanical bumps. All the recorded data by the stations was saved on DVSs, the final number being around 140. This project helped gathering a large number of seismological data for the city of Bucharest and outskirts from seismic events of magnitude of 4, 3, 2 and ambient noise. (authors)

  10. Pressurized Heavy Water Reactor Fuel: Integrity, Performance and Advanced Concepts. Proceedings of the Technical Meetings held in Bucharest, 24-27 September 2012, and in Mumbai, 8-11 May 2013

    International Nuclear Information System (INIS)

    Seven Member States have operating pressurized heavy water reactors (PHWRs), and some of them are also planning new reactors of this type. The current type of PHWR uses natural uranium as the fuel and has an average burnup of 7000 MWd/t (megawatt days per metric tonne). To make these reactors economically competitive with other reactor types, the discharge burnup of PHWR fuel will need to be increased without affecting the integrity of the fuel pin and bundle. A significant increase in the discharge burnup of fuel is possible with the use of advanced fuel cycles in PHWRs. The advanced fuels can be slightly enriched uranium, reprocessed uranium from light water reactors, mixed oxide or thorium based fuels. At the same time, substantial savings in natural uranium resources can also be achieved through the possible extension of the discharge burnup of advanced fuels used in PHWRs without changing reactor hardware. Following the recommendation of the Technical Working Group on Fuel Performance and Technology, two technical meetings were held: Technical Meeting on Fuel Integrity during Normal Operation and Accident Conditions in PHWRs, 24–27 September 2012, Bucharest, Romania; and Technical Meeting on Advanced Fuel Cycles in PHWRs, 8–11 April 2013, Mumbai, India. Their objective was to update information on the performance of PHWR fuels, the status and trends in the use of advanced fuels in PHWRs and the technical readiness for the deployment of such fuel cycles in these types of reactor. This publication contains the proceedings of the two technical meetings, including a record of the discussions held during the various technical sessions

  11. SANS Facility at the Pitesti 14 MW TRIGA Reactor

    International Nuclear Information System (INIS)

    At the present time, an important not yet fully exploited potentiality is represented by the SANS instruments existent at lower power reactors and reactors in developing countries even if they are, generally, endowed with a simpler equipment and are characterized by the lack of infrastructure to maintain and repair high technology accessories. The application of SANS at lower power reactors and in developing countries nevertheless is possible in well selected topics where only a restricted Q range is required, when scattering power is expected to be sufficiently high or when the sample size can be increased at the expense of resolution. Examples of this type of applications are: 1) Phase separation and precipitates in material science, 2) Ultrafine grained materials (nanocrystals, ceramics), 3) Porous materials such as concretes and filter materials, 4) Conformation and entanglements of polymer-chains, 5) Aggregates of micelles in microemulsions, gels and colloids, 6) Radiation damage in steels and alloys. The need for the installation of a new SANS facility at the TRIGA Reactor of the Institute of Nuclear Research in Pitesti, Romania becomes actual especially after the shutting down of the WWR-S Reactor from Bucharest. A monochromatic neutron beam with 1.5 A ≤ λ ≤ 5 A is produced by a mechanical velocity selector with helical slots. The distance between sample and detectors plane is 5.2 m. The sample width may be fixed between 10 mm and 20 mm. The minimum value of the scattering vector is Qmin = 0.005 A-1 while the maximal value is Qmax = 0.5 A-1. The relative error is ΔQ/Qmin = 0.5. The cooperation partnership between advanced research centers and the smaller ones from developing countries could be fruitful. The formers act as mentors in solving specific problems. Such a partnership was established between INR Pitesti, Romania and JINR Dubna, Russia. The first step in this cooperation consists in the manufacturing at Dubna of a battery of gas filled

  12. Programme Note: Street Children in Bucharest.

    Science.gov (United States)

    Alexandrescu, Gabriela

    1996-01-01

    Interviewed Bucharest street children, most between 11 and 15 years of age. Found that most left families, not institutions. Half were from intact families characterized by many children, an incarcerated parent, physical violence, sexual abuse, or alcoholism. Most worked either begging or in casual labor, and engaged in substance abuse.…

  13. Caries experience in schoolchildren in Bucharest, Romania

    DEFF Research Database (Denmark)

    Funieru, Cristian; Twetman, Svante; Funieru, Elena;

    2014-01-01

    OBJECTIVE: This cross-sectional study aimed to investigate the prevalence and experience of dental caries among children from public middle schools in Bucharest in relation to socioeconomic status and access to school-based dental care. METHODS: Clinical data were collected from 1,595 schoolchild...

  14. Outlines of seismic microzoning of Bucharest, Romania

    International Nuclear Information System (INIS)

    During the last century Bucharest suffered heavy damage and casualties inflicted by the 1940 (Mw=7.7) and 1977 (Mw=7.4) Vrancea earthquakes. The statistics based on the historical records show that, in Vrancea, about 3 destructive subcrustal earthquakes (Mw≥7.0) occur each century. In these circumstances, the seismic microzonation of the city is an important information to be taken into account by the decision-makers in order to establish the appropriate level of preparedness to the earthquake threat. This paper discusses the state of the art of seismic microzonation studies in Bucharest. The main features concerning the seismicity in the Vrancea region, the city site conditions, the characterization of the building stock, and the codes of practice that regulate the antiseismic design are presented. (author)

  15. BUCHAREST HOTEL MARKET IN THE EUROPEAN CONTEXT

    Directory of Open Access Journals (Sweden)

    Silvia Patricia DODU

    2014-12-01

    Full Text Available The European hospitality industry currently sees an increase in all specific indicators, a fact that shows, on one hand, the ability of this sector to overcome the economic turbulences of recent years, but also the real perspectives for future growth. Today’s hotel industry can no longer rely on the traditional growth methods, and needs to prepare for the major confrontation with the next-generation technological developments that generate modern marketing channels but, by default, incur significantly higher costs for simply „being” on the market. The Bucharest hotel market is no exception; in the recent past, it has witnessed a slight upwards trend generated by the increase of demand in the business tourism area, while also facing the challenge of integration of modern technologies in the hotel business.

  16. Polarisation of Social Inequalities in Disadvantaged Neighbourhoods of Bucharest Metropolis

    OpenAIRE

    ALINA T. CHICOŞ; ALINA E. HUZUI; ROBERT C. STOICULESCU

    2013-01-01

    This paper gives an insight into the statistical interpretation of socio-spatial changes of Bucharest urban landscape in connection to the transformations of the urban planning visions across the last decades. Special emphasis is placed on the emergence of disadvantaged neighbourhoods which are defined by a clear homogenisation of certain social classes on a precarious housing infrastructure. This came as a result of a historical hierarchy of the urban social space. Moreover, Bucharest was sh...

  17. Environmental radioactivity in the surroundings of IFIN-HH, Bucharest, Magurele

    International Nuclear Information System (INIS)

    Different nuclear activities were developed at the Magurele site beginning fifties. The start-up of the research reactor type WWR-S in 1957 increased the radioactive contaminating potential in the zone. An environmental monitoring system was developed according to the new legislation of the country. Special attention was given to the Reactor, away-from-reactor (AFR) storage of spent fuel and Radioactive Waste Treatment Facility surroundings. Presently, the institute applies an environmental concept. The necessary radiological site characterization implies an increasing number of surveyed points and new measuring techniques. The radiological data acquisition is performed by 'in-laboratory' α, β and γ absolute determinations. A high resolution gamma spectrometer NOMAD PLUS was used in the study. The portable system SMART-200 is provided with the detectors for α, β, and γ radiations (ranges: 20 to 70 keV, 40 keV to 1 MeV). The materials used for preparation of standards were: - leaves gathered from reactor yard, dried at 90 deg. C and milled; - soil taken from 1 m depth in village Mosteni-Teleorman, dried at 90 deg. C and milled; - water, distillated. For the determination of gamma-spectrometer calibration factors used for in-situ measurements a circular geometry (1 m radius) was chosen. The reference sources were the following: 152 Eu with activity of 370.0 kBq; 60 Co with activity of 306.9 kBq, 137 Cs with activity of 255.7 kBq, 241 Am with activity of 338.1 kBq and 51 Cr with activity of 261.9 kBq. The standards for soil and vegetation using as reference sources eusol1, euveg1 and euveg2 having the densities 1.45, 061, 0.40 g/cm3 and the activities 733.40, 584.41, 542.14 Bq, respectively, were measured with an error of ± 5%. The results for soil and vegetation measurements in IFIN-HH surroundings were obtained by processing γ spectra using GAMMA VISION code. The content (in Bq) for the radioisotopes identified in samples was determined by means of the

  18. Aircraft noise footprint for Bucharest – Sophia flights

    Directory of Open Access Journals (Sweden)

    Luis MELIVEO

    2012-12-01

    Full Text Available Studies of impact noise have traditionally focused on landing and takeoff procedures in the airports vicinity. Beside these studies, en-route noise is considered an issue when we talk about noise in natural reservation or other populated sensitive areas and when it comes to designing a new aircraft engine. In these cases, the studies are focusing on the impact at ground level of the en route noise produced by aircraft at all the flights stages. This paper presents the results of the measurement performed for an A320 aircraft when flying en-route and the impact map for a flight from Bucharest – Sofia – Bucharest (OTP-SOF-OTP.

  19. Near surface shear wave velocity in Bucharest, Romania

    OpenAIRE

    M. von Steht; B. Jaskolla; Ritter, J.R.R.

    2010-01-01

    Bucharest, the capital of Romania with nearly 2 1/2 million inhabitants, is endangered by the strong earthquakes in the Vrancea seismic zone. To obtain information on the near surface shear-wave velocity Vs structure and to improve the available microzonations we conducted seismic refraction measurements in two parks of the city. There the shallow Vs structure is determined along five profiles, and the compressional-wave velocity (Vp) s...

  20. ANALYSIS OF THE BUCHAREST STOCK EXCHANGE INDICES STRUCTURE

    OpenAIRE

    Mihaela SUDACEVSCHI

    2013-01-01

    A stock market index is used for measure the stock market activity or the value of a section of the stock market. Bucharest Stock Exchange (BSE) currently has 7 indices, with different structures, whose evolution reflects the real situation of the most liquid companies listed on the BSE or the price movement of all the companies listed on the BSE regulated market, in fact the situation of the Romanian economy. For investors, stock indices evolution is very important, since highlights the stoc...

  1. THE BRANDING POTENTIAL OF BUCHAREST. STRATEGY AND SUCCESS FACTORS

    OpenAIRE

    Ruxandra Irina POPESCU

    2009-01-01

    Bucharest is still looking for its identity. Reported in the national brand – that is still in an incipient phase, it can play two roles: whether as ingredient for the country brand, the capital becoming an element included on the list of values promoted at national level, or as a landmark, for defining and subsequently for improving the country brand. The unexploited potential must be capitalized in the future by using urban branding and marketing steps adapted to the local specificity.

  2. RESEARCH ON CONSUMER BEHAVIOUR ON BUCHAREST MEAT MARKET

    OpenAIRE

    Agatha POPESCU

    2013-01-01

    The paper aimed to analyze consumer behavior for meat on Bucharest market, using a sample of 100 individuals, representatives as age, sex and profession, who were interviewed within a structured questionaire based survey on their preference to buy and consume meat. The answers were processed using the semantic differential and Likert Scale. The obtained results pointed out that white meat is the top preference, because it is healthier and its price is more acceptable compared to red meat. How...

  3. Romanian Hotel Groups Listed at Bucharest Stock Exchange a Survey

    OpenAIRE

    Cornelia Pop; Cristina Curutiu; Partenie Dumbrava

    2008-01-01

    Hotel industry is an important component of travel and tourism (T&T) sector. However, less studies are dedicated to hotel industry than to the T&T sector as a hole. Even less studies are available on hotel companies or groups listed on stock exchanges around the world. The present study will focus on Romanian hotel groups listed at Bucharest Stock Exchange, compared with the situation in Europe.

  4. Deterministic approach for a C level microzonation of Bucharest

    Science.gov (United States)

    Moldoveanu, C. L.; Cioflan, C.; Radulian, M.; Apostol, B.; Panza, G. F.

    2003-04-01

    Bucharest experienced heavy destruction and large number of victims during the extreme 1940 (Mw=7.7) and 1977 (Mw=7.4) Vrancea intermediate-depth earthquakes (located in the 60-200 km depth interval, at the sharp bend of the Southeast Carpathians). The statistics indicate a recurrence interval of 25 years for Mw>6.0 and 50 years for Mw>7.0 in the region. The assessment and mitigation of the earthquake risk are therefore particularly important in the Romanian capital since more than 2 million inhabitants, major investments and vital life systems are concentrated there. The seismic ground motion evaluation implies the analysis of a large database of records provided by dense arrays of seismographs. This allows to define generally valid ground parameters to be used in seismic microzonation estimations. The strong motion registrations in Bucharest area are rather few and available only since 1977. Therefore the ability to compute numerically realistic seismograms represents in our opinion the key element for performing "present day" microzonation studies. Using a complex hybrid waveform modeling method that accounts for the source, wave propagation path and local site geology, we investigate which features of the seismic process are predictable in case of Vrancea dominant shocks, and how do they reproduce the strong local effects observed in Bucharest for the 1977 event. Our deterministic results show that the synthetic local hazard distribution supplies a realistic estimation of the seismic input. This method allows the merging of the different specific information collected until now in reasonably well constrained scenarios for a level C realistic microzonation of Bucharest area to be used to mitigate the effects of future strong events originating in Vrancea region.

  5. SWOT ANALYSIS OF PUBLIC TRANSPORT SYSTEM IN BUCHAREST

    OpenAIRE

    Bugheanu Alexandru

    2015-01-01

    European Capital-Bucharest is in a continuous development from all points of view, and the demand for more effective modes of transportation is constantly increasing. The population of the city has increased significantly in recent years, the number of passenger cars registered here exceeds 20% of the total of those registered at the country level, and the transport system has to face all the challenges. The aim of the present research is to conduct an analysis on the public transport network...

  6. Teenage perspectives on urban environments: case studies from contemporary Bucharest

    OpenAIRE

    Florea, Ioana

    2010-01-01

    The urban environment is a product of everyday social practices and interactions but, at the same time, it conditions social practices and interactions. The article explores the position of the youth in this reciprocal process, drawing on a study involving more than 100 children and teenagers (pupils from Grades 4-11) from 2 elementary schools and 2 high schools in Bucharest. The research followed several lines of investigation: their knowledge of and sensitivity to pollution and nature; the ...

  7. The Bucharest of tomorrow as imagined in the last century

    Directory of Open Access Journals (Sweden)

    Mihai Ene

    2014-12-01

    Full Text Available The inhabitants of Bucharest, but not only them, have always had a nostalgia of a capital comparable to the great European metropolis. Their imaginary related to this issue is, more often than not, bookish, but there have also been competent voices (architects, builders, engineers, or politicians who knew how to lucidly identify the needs and possibilities of the town on the banks of the Dâmboviţa river, to propose viable solutions able to correct the shortcomings of the present and, more rarely, to analyze ways and means by which their city can become a truly modern one. In the majority of cases, the envisioned renewal comes down to building imposing institutional buildings, improving the banks of the river, the development of the transportation network and harnessing the potential of the northern lakes. Few authors have proven to be able to tackle the usual issues of urban plans in a coherent manner (the public space/private space relationship, building height regulations, communication networks and fewer still, mainly professionals, have succeeded in sketching, even concisely, the list of priorities and the steps to be followed for the builders of the future. Not all those who have entered this debate have called for a modernization in the Western sense, some claiming that the loss of the picturesque qualities of the old capital will result in a depersonalization of Bucharest and its transformation into a failed copy of the Western capitals. Although incomplete, superficial or even naive, all these fragments of the imaginary of Bucharest are a testimony of love of the residents for their city and can bring a contribution to a better understanding of today’s realities of the capital of Romania.

  8. Statistical investigation on the IT market in Bucharest

    Directory of Open Access Journals (Sweden)

    Constantin MITRUT

    2006-01-01

    Full Text Available This paper represents the results of a pilot survey conducted on a set of it specialists concerning their behavior on the IT market as buyers. Demand estimation is one of the main purpose of the research. Initial hypothesis were that people in Romania are using Internet and IT systems as a tool to develop social and cultural relations, to be informed more and more compared to classic ways of access to culture and information. The research purpose was also to determine the main cross classification variables as the main influence factors on IT market in Bucharest.

  9. Research on Consumer Behaviour in Bucharest Poultry Meat Market

    OpenAIRE

    Ion Pirvutoiu; Agatha Popescu

    2013-01-01

    The paper goal was to study consumer behaviour for poultry meat. In this purpose 100 individuals participated to a questionnaire based survey  in a supermarket of  Bucharest. Specific methods of marketing research in such a case assured the statistical processing of the respondents’ answers. The results pointed out an increased consumption of poultry meat,  a preference for fresh chicken meat which is daily bought  or 2-3 times a week in a varied amount ranging between 1-1.5 kg depending on c...

  10. Estimating the probability of stock market crashes for Bucharest Stock Exchange using stable distributions

    Directory of Open Access Journals (Sweden)

    Daniel Traian PELE

    2012-07-01

    Full Text Available In this study we analyse the evolution of BET Bucharest Stock Exchange through an AR-GARCH model and we estimate the likelihood of extreme events using stable distributions.Using the time series of the Bucharest Stock Exchange main index BET we argue that stable distributions can significantly improve the prediction of an extreme event.

  11. Characterization of environmental radioactivity in the influence zone of IFIN-HH Bucharest, Magurele

    International Nuclear Information System (INIS)

    As a consequence of 40 years of nuclear related activities on the Bucharest Magurele site, the environment surrounding the area of the institute was significantly influenced. The main facilities acting as sources of radioactive pollution are inter alia the VVR-S research reactor, the U-120 cyclotron, the radioisotope production centre, the radioactive waste treatment plant, and spent fuel storage facility. In the framework of the IAEA Co-ordinated Research Project entitled 'Site characterization techniques used in environmental restoration activities', under research contract No.8735, methods for the characterization of radioactive contamination in the institute influence zone have been developed. The attention focused on the routes involved in radioactive waste and spent fuel management. Based on the environmental monitoring programme developed for the nuclear units on the site, the monitoring network was improved in area Reactor - Spent Fuel Storage - RWTP - railway station for shipping the drums to the national repository Baita-Bihor, an area with elevated radiological risks. Additionally, the work has been extended to the temporary radioactive waste storage at the former Magurele military fort, which is now partially decommissioned. The paper presents techniques, methods and instrumentation used for the radiological characterization of the site Magurele and its influence area, during the period of 1995 - 1999, as well as the respective quality assurance (QA) procedures. The results of this radiological survey presented here will be used to define the environmental restoration programme of the zone. In addition the system for the information of the public developed in this project is discussed. (author)

  12. Polarisation of Social Inequalities in Disadvantaged Neighbourhoods of Bucharest Metropolis

    Directory of Open Access Journals (Sweden)

    ALINA T. CHICOŞ

    2013-01-01

    Full Text Available This paper gives an insight into the statistical interpretation of socio-spatial changes of Bucharest urban landscape in connection to the transformations of the urban planning visions across the last decades. Special emphasis is placed on the emergence of disadvantaged neighbourhoods which are defined by a clear homogenisation of certain social classes on a precarious housing infrastructure. This came as a result of a historical hierarchy of the urban social space. Moreover, Bucharest was shaped in relation to different socio-economic and socio-cultural policies that determined the creation of a polarisation between north and south or between centre and periphery which were subject to numerous socio-urban inversions during the communist and post-communist eras. Hence, life in a large metropolis is vulnerable to inequalities appearing within the urban pattern that intensifies, in some cases, towards residential segregation. The historical-geographical analysis of vectors behind clusters of sensitive areas in the 20th and 21st centuries strengthens the importance of social cohesion measures in the future urban policies and territorial planning.

  13. Psychological Vulnerability and Earthquake Risk Perception in Bucharest/Romania

    Science.gov (United States)

    Romeo Cretu, Zeno; Armas, Iuliana; Stanciugelu, Irina

    2010-05-01

    The importance of studying the relationship with the natural hazard events from a psycho-social perspective is fundamental by the experience with past disasters as much as by the research in the field that proved that the people's psychologic structures may constitute a starting point for risk reduction. People's psycho-behavioural patterns contain conscious or unconscious references to the environmental risk, thus creating certain adjustment strategies and mechanisms, with a certain degree of psychological vulnerability. In modern man's case, the high level of awareness in front of natural dangers, doubled by the perception of the environment's unsafety, experienced as a lack of control, brings to attention nowadays the problematic of the analysis of natural risk perception, as a main factor in the adjustment of human communities' capacity of adapting to the natural environment's dynamics. The major objective of this present work is, based on the development of an efficient evaluation methodology, to identify specific relational patterns to seismic risk in Bucharest, function the characteristics of the urban environment, the social, economical and psychological vulnerability, with results that can be applied for disaster management. For explaining human reactions and the way in which they perceive and evaluate the psychological resources, on a daily basis, but also in risk situations (earthquakes), a multi-modal questionnaire was conceived through qualitative methods (a focus group, along with experts from the Public and Administrative Sciences National School, Risk Communication Center). The questionnaire was structured on a 49 items sequence, in which were included different type of questions (with single or multiple answers, open questions etc), and also questions using different scaling methods. The items caught cognitive elements (expectations, anticipations and negative or positive judgments regarding risk element), affective (feelings) and behavioral

  14. Strategic Directions for the Bucharest Strategy and City Brand

    Directory of Open Access Journals (Sweden)

    Ana-Claudia Ţapardel

    2012-11-01

    Full Text Available On the international stage, public administration has become an essential factor, capable of providing a nation with the competitive advantage. Improving standards in local administration in our country has included not only a vigorous and sustained process of reform, but also a drive to modernise and perfect management within the public sector. These aspects are essential, since decisions made by partners and investors are to an ever larger extent influenced by the quality, efficiency and credibility of public administration. Following these considerations, and based upon an empirical research conducted with the aid of a survey and a comparative analysis between the manner in which the branding and development strategies were developed in Vancouver and Bucharest, the present paper aims to identify the main strategic directions and branding elements necessary in elaborating a strategy and in accumulating a dossier of best practices, in order to implement successfully the strategic planning process and the branding strategy in the local communities of Romania.

  15. GONE FISHIN’ EFFECTS ON THE BUCHAREST STOCK EXCHANGE

    Directory of Open Access Journals (Sweden)

    RAMONA DUMITRIU

    2013-10-01

    Full Text Available This paper investigates the presence of Gone Fishin’ Effects on the Romanian Capital Market from January 2000 to July 2013. In this analysis we employ daily values of five main indexes of Bucharest Stock Exchange. We use GARCH models to reveal this seasonality not only on indexes returns but also on the capital market volatility. In order to identify the differences between quiet and turbulent periods of time we split our sample of data into two sub-samples. The first, from January 2000 to December 2006, corresponds to a relative quiet period, while the second, from January 2007 to August 2013, corresponds to a turbulent period. Our results indicate the decline of Gone Fishin’ Effects on returns from the first to the second sub-sample.

  16. Entrepreneurial behavior among employees. Pilot study: Employees from Bucharest

    Directory of Open Access Journals (Sweden)

    Ionuţ Constantin

    2015-12-01

    Full Text Available Many objective or subjective factors influence the decision to open a business. The most important factors are: the existence of an adequate opportunity or a market, perception that starting a business could be difficult because of bureaucracy, financial barriers or the need to acquire new skills, a lack of money, etc. Also, entrepreneurial behavior is generally influenced by socio-economic status of the family of origin [1]. Thus, children from wealthy families have the “competitive advantage” to receive an education appropriate for managing a business and of course have the necessary financial resources and its start [2]. However, abilities of every individual can “correct’’ these benefits are completely eliminated/reduced exogenous barriers [3]. In this article I will present the results of a pilot study conducted in 2014 at Bucharest employees to observe their entrepreneurial behavior.

  17. Research on Consumer Behaviour in Bucharest Poultry Meat Market

    Directory of Open Access Journals (Sweden)

    Ion Pirvutoiu

    2013-05-01

    Full Text Available The paper goal was to study consumer behaviour for poultry meat. In this purpose 100 individuals participated to a questionnaire based survey  in a supermarket of  Bucharest. Specific methods of marketing research in such a case assured the statistical processing of the respondents’ answers. The results pointed out an increased consumption of poultry meat,  a preference for fresh chicken meat which is daily bought  or 2-3 times a week in a varied amount ranging between 1-1.5 kg depending on consumer’s income for covering the family need. The main factors influencing consumer buying decision are the sensorial meat characteristics, meat quality, origin, price, prepaking grade. As a conclusion producers have to pay more attention to these aspects in their future strategy for producing and commercialising poultry meat.

  18. Near surface shear wave velocity in Bucharest, Romania

    Directory of Open Access Journals (Sweden)

    M. von Steht

    2008-12-01

    Full Text Available Bucharest, the capital of Romania with nearly 2 1/2 million inhabitants, is endangered by the strong earthquakes in the Vrancea seismic zone. To obtain information on the near surface shear-wave velocity Vs structure and to improve the available microzonations we conducted seismic refraction measurements in two parks of the city. There the shallow Vs structure is determined along five profiles, and the compressional-wave velocity (Vp structure is obtained along one profile. Although the amount of data collected is limited, they offer a reasonable idea about the seismic velocity distribution in these two locations. This knowledge is useful for a city like Bucharest where seismic velocity information so far is sparse and poorly documented. Using sledge-hammer blows on a steel plate and a 24-channel recording unit, we observe clear shear-wave arrivals in a very noisy environment up to a distance of 300 m from the source. The Vp model along profile 1 can be correlated with the known near surface sedimentary layers. Vp increases from 320 m/s near the surface to 1280 m/s above 55–65 m depth. The Vs models along all five profiles are characterized by low Vs (<350 m/s in the upper 60 m depth and a maximum Vs of about 1000 m/s below this depth. In the upper 30 m the average Vs30 varies from 210 m/s to 290 m/s. The Vp-Vs relations lead to a high Poisson's ratio of 0.45–0.49 in the upper ~60 m depth, which is an indication for water-saturated clayey sediments. Such ground conditions may severely influence the ground motion during strong Vrancea earthquakes.

  19. Near surface shear wave velocity in Bucharest, Romania

    Science.gov (United States)

    von Steht, M.; Jaskolla, B.; Ritter, J. R. R.

    2008-12-01

    Bucharest, the capital of Romania with nearly 2 1/2 million inhabitants, is endangered by the strong earthquakes in the Vrancea seismic zone. To obtain information on the near surface shear-wave velocity Vs structure and to improve the available microzonations we conducted seismic refraction measurements in two parks of the city. There the shallow Vs structure is determined along five profiles, and the compressional-wave velocity (Vp) structure is obtained along one profile. Although the amount of data collected is limited, they offer a reasonable idea about the seismic velocity distribution in these two locations. This knowledge is useful for a city like Bucharest where seismic velocity information so far is sparse and poorly documented. Using sledge-hammer blows on a steel plate and a 24-channel recording unit, we observe clear shear-wave arrivals in a very noisy environment up to a distance of 300 m from the source. The Vp model along profile 1 can be correlated with the known near surface sedimentary layers. Vp increases from 320 m/s near the surface to 1280 m/s above 55 65 m depth. The Vs models along all five profiles are characterized by low Vs (<350 m/s) in the upper 60 m depth and a maximum Vs of about 1000 m/s below this depth. In the upper 30 m the average Vs30 varies from 210 m/s to 290 m/s. The Vp-Vs relations lead to a high Poisson's ratio of 0.45 0.49 in the upper ~60 m depth, which is an indication for water-saturated clayey sediments. Such ground conditions may severely influence the ground motion during strong Vrancea earthquakes.

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

    International Nuclear Information System (INIS)

    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 2.4.106 at a flight path distance of 3.6 m. The number of neutrons scattered from a sample (5 cm3 in volume) and incident on the detector system, as estimated for the suggested arrangement, is ∝1.6.103 n/sec. Such high counting rate allows to measure a diffraction spectrum within less than an hour. (orig.) With 12 figs

  1. New Geophysical and Geotechnical Data on Quaternary Layers in the Metropolitan Area of Bucharest

    Science.gov (United States)

    Florin Balan, Stefan; Ritter, Joachim; Bala, Andrei; Rohn, Joachim

    2010-05-01

    Bucharest, the capital of Romania, with approximately 2.5 million inhabitants, is considered after Istanbul the second-most earthquake-endangered metropolis in Europe. It is identified as a natural disaster hotspot by a global study of the World Bank and the Columbia University (Dilley et al., 2005). Four major earthquakes with moment-magnitudes between 6.9 and 7.7 hit Bucharest in the last 70 years. The most recent destructive earthquake of 4th March 1977, with a moment magnitude of 7.4, caused about 1.500 casualties in the capital alone. All disastrous earthquakes are generated within a small epicentral area - the Vrancea region - about 150 km northeast of Bucharest. Thick unconsolidated sedimentary layers in the area of Bucharest amplify the arriving seismic shear-waves causing severe destruction. Thus, disaster prevention and mitigation of earthquake effects is an issue of highest priority for Bucharest and its population. An international research project was initiated and recently finished - NATO SfP Project 981882: Site-effect analyses for the earthquake-endangered metropolis Bucharest, Romania. This project had the target to fill gaps in knowledge concerning seismic and geotechnical parameters in the shallow (h Physics, Bucharest, Romania and the Universität Karlsruhe (TH), Germany. The main objective was earthquake risk mitigation and better seismic safety of Bucharest City. Ten 50 m deep boreholes were successfully drilled and studied in detail. The values of the mean weighted seismic velocities computed in the present study are within a narrow range as others obtained by seismic in situ measurements. vs30 values below 360 m/s indicate intermediate soil as near-surface material which tends to amplify earthquakes waves. This means that the near-surface layer and its elastic properties are crucial for understanding the seismic hazard imposed to Bucharest City. The elastic and dynamic parameters from geotechnical measurements at samples from the first 6

  2. Bucharest PhD Training School : Modern Aspects of Quantum Field Theory and Applications

    CERN Document Server

    2015-01-01

    Bucharest 2015 – Modern Aspects of Quantum Field Theory is part of the CERN – SEENET-MTP PhD Training Program, which consists of a number of seminars in theoretical high energy Physics. This is the second seminar organized by this Program. Here are some photos from this event held in Bucharest between 8-14 November 2015. The previous seminar was organized in Belgrade, under the name Belgrade 2015 - Supergravity.

  3. The Impact of Management Structures’ Composition on Performance of Companies listed on the Bucharest Stock Exchange

    OpenAIRE

    Georgeta VINTILA; Raluca-Georgiana MOSCU

    2015-01-01

    This paper presents several econometric models that explain how the performance of companies listed on the Bucharest Stock Exchange is influenced by corporate governance practices of listed companies comply how the principles and recommendations of the Corporate Governance Code of the Bucharest Stock Exchange. They raised issues related to the composition and size of the Board of Directors. The research proposes a brief description of the characteristics governing bodies of companies listed o...

  4. Vrancea early warning system for Bucharest and industrial objectives

    International Nuclear Information System (INIS)

    Romania is an earthquake prone area and it is of crucial importance to obtain quantitative information needed for seismic risk mitigation and related public policies and seismic safety measures. The most damaging earthquakes in Romania concentrate in the Vrancea region, located at the sharp bend of the Eastern Carpathians Arc, in a well confined focal volume at intermediate depths between 60 km and 200 km. Vrancea earthquakes are documented for at least a millennium (since 985 a.c.) and represent very peculiar characteristics. They are a permanent threat for large urban areas on the Romanian territory and extended areas in Europe. Bucharest is among the mega cities mostly affected by destructive earthquakes. The early warning system in Romania is to provide individuals and communities exposed to disaster risk due to strong Vrancea earthquakes, with accurate information about an impending hazard as early as possible, to act in a timely and appropriate manner to reduce probability of suffering, personal damage, death and property losses. The purpose of this early system is to issue messages at sites of interest before the destructive seismic energy arrives. Early warning system is a technological instrument to detect, monitor and issue warnings/alerts. It needs to become part of a management information system for decision - making in the context of national institutional frameworks for disaster management and as a part of national and local strategies for disaster risk reduction. (authors)

  5. Innovation Cluster and Economic Development in Bucharest Ilfov Region

    Directory of Open Access Journals (Sweden)

    Ana Cristina Adumitroaei

    2013-08-01

    Full Text Available Simultaneous globalisation tendencies have created policy challenges for national and local governments. One response to these challenges has been a dramatic proliferation of development policies based on clusters of firms and industries. In EU Strategy 2020 – COM 546/6.10.2010 Initiative “An Union of Innovation”, COM 614/27.10.2010 Initiative “Industrial Policy in the Globalization Era” innovative clusters were considered the “engine” of economic development. They represent a framework for business development, collaboration between companies, universities, research institutions, suppliers, customers and competitors located in the same geographical area. Clusters of small and medium sized firms in developing economies are coming under increased pressure from competition as products mature, technology becomes widely available, and companies seek lower cost locations for production. In this paper, we consider that the cluster is an engine for economic development in our region and we need to have a regional strategy for clusters in Bucharest Ilfov Regional Development Plan for 2014-2020.

  6. Operation experience with the TRIGA Reactor Vienna

    International Nuclear Information System (INIS)

    Since the last European TRIGA Users Conference in Bucharest, Romania in September 1992 the TRIGA reactor Vienna operated without any major undesired shutdown. Some problems were centred around the new microprocessor controlled instrumentation installed in summer 1992. The fuel behaviour was excellent, no fuel failures were experienced. The experimental facilities were extensively used for students education and training

  7. National facilities for the management of institutional radioactive waste in Romania: 25 years of operation of radioactive waste treatment plant, Bucharest-Magurele, 15 years of operation at national radioactive repository, Baita-Bihor

    International Nuclear Information System (INIS)

    The management of the non-fuel cycle radioactive wastes from all over Romania is centralised at IFIN-HH in the Radioactive Waste Treatment Plant (STDR). Final disposal is carried out at the National Repository of Radioactive Wastes (DNDR) at Baita-Bihor. Wastes containing short-lived radionuclides, which do not require any special treatment, after the temporary storage at the producer for decay period, are transferred as normal non-radioactive wastes. Wastes containing long-lived radionuclides are collected, treated and conditioned at IFIN-HH before final disposal. Radioactive wastes treated at STDR arise from three main sources: 1. Wastes arising from the WWR-S research reactor during operation and future decommissioning operations. 2. Local wastes from other facilities operating at IFIN-HH site. These latter sources include wastes generated during the normal activities of STDR. 3. Wastes from IFIN-HH off-site facilities and activities including medical, biological and industrial applications all over the country. The operational wastes are both liquids and solids. The paper takes into account the following matters: solid waste treatment, conditioning and storage of radioactive waste containers, STDR capacity, temporary storage and final disposal, updating the management infrastructure of institutional radioactive waste. From November 1974 to November 1999 there were treated at STDR nearly 26,000 m3 LLAW, 2,100 m3 LLSW and 4,000 spent sources resulting over 5,500 conditioned drums disposed at DNDR. After 25 years of operation for STDR and 15 years of operation for DNDR an updating programme started in 1990. The Research and Development activities are based on the bi- and multilateral co-operation with the International Atomic Energy Agency and nuclear developed countries through research contracts and technical assistance. In the last years STDR and DNDR benefited from IAEA assistance by a WAMAP mission, training courses and grants for international meetings

  8. Urban Groundwater Mapping - Bucharest City Area Case Study

    Science.gov (United States)

    Gaitanaru, Dragos; Radu Gogu, Constantin; Bica, Ioan; Anghel, Leonard; Amine Boukhemacha, Mohamed; Ionita, Angela

    2013-04-01

    Urban Groundwater Mapping (UGM) is a generic term for a collection of procedures and techniques used to create targeted cartographic representation of the groundwater related aspects in urban areas. The urban environment alters the physical and chemical characteristics of the underneath aquifers. The scale of the pressure is controlled by the urban development in time and space. To have a clear image on the spatial and temporal distribution of different groundwater- urban structures interaction we need a set of thematic maps is needed. In the present study it is described the methodological approach used to obtain a reliable cartographic product for Bucharest City area. The first step in the current study was to identify the groundwater related problems and aspects (changes in the groundwater table, infiltration and seepage from and to the city sewer network, contamination spread to all three aquifers systems located in quaternary sedimentary formations, dewatering impact for large underground structures, management and political drawbacks). The second step was data collection and validation. In urban areas there is a big spectrum of data providers related to groundwater. Due to the fact that data is produced and distributed by different types of organizations (national agencies, private companies, municipal water regulator, etc) the validation and cross check process is mandatory. The data is stored and managed by a geospatial database. The design of the database follows an object-orientated paradigm and is easily extensible. The third step consists of a set of procedures based on a multi criteria assessment that creates the specific setup for the thematic maps. The assessment is based on the following criteria: (1) scale effect , (2) time , (3) vertical distribution and (4) type of the groundwater related problem. The final step is the cartographic representation. In this final step the urban groundwater maps are created. All the methodological steps are doubled

  9. Preliminary indoor radon and gamma measurements in kindergartens and schools in Bucharest

    International Nuclear Information System (INIS)

    A pilot study on indoor radon and gamma dose rates in schools and kindergartens (totalling one hundred buildings) in the Bucharest metropolitan area was performed jointly by the Institute of Public Health, Bucharest, Romania, and the J. Stefan Institute, Ljubljana, Slovenia. Because the geological structure of subsoil over the whole Bucharest area is uniform (a loess platform), the criteria for selecting a kindergarten or a school to be monitored were the age of the building and the building materials. Indoor radon concentrations were measured by a single one-month exposure of radon monitoring device based on etched track detectors in December 2000. Data show a lognormal distribution within the concentration range of 43/477 Bq/m3. An arithmetic mean of 146 Bq/m3 and a geometric mean of 128 Bq/m3 were obtained. Concomitant with indoor radon levels gamma dose rates were also measured, using thermoluminescent dosimeters. Values ranged from 54 to 100 μSv mo-1, with a mean value of 74 μSv mo-1. Having only a single average indoor radon concentration for a winter month, it is not possible to comment on our results, applying the ICRP Publication 65 methodology for indoor radon action level for the general public. Nevertheless, they give a preliminary picture of indoor radon and gamma dose rate levels in schools and kindergartens in Bucharest, and constitute a solid basis on which to design and perform a nation-wide radon survey programme.(author)

  10. Millipedes (Diplopoda) and centipedes (Chilopoda) from the city of Bucharest, Romania: An introduction study

    Czech Academy of Sciences Publication Activity Database

    Giurginca, A.; Tajovský, Karel; Tuf, I.H.

    Olomouc : Institute of Soil Biology , BC ASCR, 2014. s. 27. ISBN 978-80-86525-28-0. [International Congress of Myriapodology /16./. 20.07.2014-25.07.2014, Olomouc] Institutional support: RVO:60077344 Keywords : millipedes * centipedes * city of Bucharest Subject RIV: EH - Ecology, Behaviour

  11. Strong Vrancea intermediate depth earthquakes and seismic microzonation of Bucharest urban area

    International Nuclear Information System (INIS)

    [Text of English abstract is entered here]. The strong earthquake which took place in Vrancea region on 4th March 1977 provoked crumbling of 32 high buildings in the central area of Bucharest while a dozen of other high buildings were severely damaged. The main cause of this destruction was supposed generally to be the matching of eigen oscillation period of the building to the ground resonance period specific for the underground geologic formations of the city. The main target of the present study is to obtain an assessment of the influence of local geologic features upon the ground response in Bucharest region entailed by the Vrancea strong earthquakes (M > 7) at intermediate depths. To reach this target two data sets were used: (1) geologic, geotechnical and geophysical data based on in situ measurements of transverse waves; (2) the acceleration records of Vrancea earthquakes which took place between 1977 and 2004. The results of our study concerning the local response based on the use of impedance contrasts and amplification factors evidenced two major characteristics of high significance from engineering point of view: disagreement for the case of Bucharest city of the standard approach which extends the depth of investigation up to 30 m for determination of dynamic characteristic of the ground; the local response at strong Vrancea earthquakes is controlled by the Quaternary sedimentary deposits which are by far thicker than 30 m in the underground of Bucharest; (2) The difficulty of defining zones of different responses. Thus for urban area of Bucharest city in case of Vrancea earthquakes of intermediate depths one can refer to regional rather than local effects. (authors)

  12. HUMAN RESOURCES DEVELOPMENT OF THE RURAL AREA - AS A RURAL DEVELOPMENT COMPONENT - IN THE BUCHAREST-ILFOV REGION OF ROMANIA

    OpenAIRE

    Stoicescu, Alina; Alecu, Ioan-Niculae

    2012-01-01

    The paper aimed to present the rural human resources development during the period 2007-2013 in the Bucharest –Ilfov Region of Romania, as a rural development component. It is based on the statistical data provided by our studies regarding HRD projects implemented in this area, financed from structural founds (European Social Found). The data have been processed into the following indicators: number of projects implemented in the Bucharest-Ilfov region promoting long term sustainability of ...

  13. Analysis Particulars of Financial Instruments for Companies Not Listed in the Bucharest Stock Exchange Rate

    Directory of Open Access Journals (Sweden)

    Teodor HADA

    2014-12-01

    Full Text Available The current paper presents the main features on the trading of financial instruments rated on the Unlisted market. The purpose of this paper is to give a general framework to study modalities of stock analysis of unlisted tools on the Bucharest Stock Exchange. In the introduction of the study elements referring to the objectives, research methodology, innovations of this research are presented, specialized literature being also reviewed. The first paragraph summarizes the main stock markets in Romania pursuing that in the following paragraphs it will focus strictly on the market of the instruments listed on the Bucharest Stock Exchange, for which a case study in ALBAPAM JS. has been conducted by performing stock analysis and, after the main legislation is presented, which discusses Rasdaq dismantling, finally, after submitting all the information found in the content of the paper, the findings for each paragraph were presented.

  14. Geological and Geophysical Models Underneath Bucharest City Responsible for the Variability of Seismic Site Effects

    Science.gov (United States)

    Bala, A.; Aldea, A.; Balan, S. F.; Arion, C.

    2012-04-01

    Bucharest, the capital of Romania, with more than 2 million inhabitants, is considered after Istanbul the second-most earthquake-endangered metropolis in Europe. It is identified as a natural disaster hotspot by a recent global study of the World Bank and the Columbia University (Dilley et al., 2005). Four major earthquakes with moment-magnitudes between 6.9 and 7.7 hit Bucharest in the last 65 years. The most recent destructive earthquake of 4. March 1977, with a moment magnitude of 7.4, caused about 1.500 casualties in the capital alone. All disastrous earthquakes are generated within a small epicentral area - the Vrancea region - about 150 km north-east of Bucharest. Thick unconsolidated sedimentary layers in the area of Bucharest amplify the arriving seismic shear-waves causing severe destruction. Most of the PGA variation across the city is due to the package of the Quaternary sedimentary layers which amplify the original strong motion arrived from the earthquake. The largest amplification of the soil will occur at the lowest natural frequency or its fundamental period. In situ measurements of shear wave velocity in the soil and the soil thickness, provide a rough measurement of the characteristic site period. Extensively seismic noise measurements proved to be a much accessible method and computed H/V spectral ratio over large periods of time, may provide a good indication on the fundamental period of the site, even if the position of the bedrock is not well defined. Within the NATO-funded Science for Peace Project 981882 "Site-effect analyses for the earthquake-endangered metropolis Bucharest, Romania" the drilling and the Vp and Vs (seismic longitudinal and shear-wave velocities) measurements in ten boreholes were done in the years 2006-2008 (Bala et al., 2010). Rock samples were taken from each borehole at different depths for laboratory tests to determine the geotechnical parameters of each sedimentary rock type at the sites. Thus a valuable data base is

  15. Improved seismic risk estimation for Bucharest, based on multiple hazard scenarios, analytical methods and new techniques

    Science.gov (United States)

    Toma-Danila, Dragos; Florinela Manea, Elena; Ortanza Cioflan, Carmen

    2014-05-01

    Bucharest, capital of Romania (with 1678000 inhabitants in 2011), is one of the most exposed big cities in Europe to seismic damage. The major earthquakes affecting the city have their origin in the Vrancea region. The Vrancea intermediate-depth source generates, statistically, 2-3 shocks with moment magnitude >7.0 per century. Although the focal distance is greater than 170 km, the historical records (from the 1838, 1894, 1908, 1940 and 1977 events) reveal severe effects in the Bucharest area, e.g. intensities IX (MSK) for the case of 1940 event. During the 1977 earthquake, 1420 people were killed and 33 large buildings collapsed. The nowadays building stock is vulnerable both due to construction (material, age) and soil conditions (high amplification, generated within the weak consolidated Quaternary deposits, their thickness is varying 250-500m throughout the city). A number of 373 old buildings, out of 2563, evaluated by experts are more likely to experience severe damage/collapse in the next major earthquake. The total number of residential buildings, in 2011, was 113900. In order to guide the mitigation measures, different studies tried to estimate the seismic risk of Bucharest, in terms of buildings, population or economic damage probability. Unfortunately, most of them were based on incomplete sets of data, whether regarding the hazard or the building stock in detail. However, during the DACEA Project, the National Institute for Earth Physics, together with the Technical University of Civil Engineering Bucharest and NORSAR Institute managed to compile a database for buildings in southern Romania (according to the 1999 census), with 48 associated capacity and fragility curves. Until now, the developed real-time estimation system was not implemented for Bucharest. This paper presents more than an adaptation of this system to Bucharest; first, we analyze the previous seismic risk studies, from a SWOT perspective. This reveals that most of the studies don't use

  16. Aircraft noise in the region of the Bucharest-Otopeni Airport. [noise pollution in airport environment

    Science.gov (United States)

    Costescu, M.; Gherghel, C.; Curtoglu, A.

    1974-01-01

    Aircraft noise, especially in the region adjoining airports, constitutes a problem that will be aggravated in the near future because of increasing aircraft traffic and the appearance of new types of large tonnage aircraft with continuously increasing powers and speeds. Criteria for the evaluation of aircraft noise are reported and some results of studies carried out in the region of Bucharest-Otopeni Airport are detailed.

  17. Analysis Particulars of Financial Instruments for Companies Not Listed in the Bucharest Stock Exchange Rate

    OpenAIRE

    Teodor HADA; Teodora Maria AVRAM

    2014-01-01

    The current paper presents the main features on the trading of financial instruments rated on the Unlisted market. The purpose of this paper is to give a general framework to study modalities of stock analysis of unlisted tools on the Bucharest Stock Exchange. In the introduction of the study elements referring to the objectives, research methodology, innovations of this research are presented, specialized literature being also reviewed. The first paragraph summarizes the main stock markets i...

  18. 89Sr and 90Sr in atmospheric precipitations in May 1986 in Bucharest-Magurele area

    International Nuclear Information System (INIS)

    Sr-89 and Sr-90 were determined in the fallout of May 1986. The maximum values of 335 Bq/(m2* 6 hours) and 110 Bq/(m2* 6 hours) were observed at May 2 and 5. Throughout May 1986 a quantity of 860 Bq/m2 of Sr-90 deposited from the fallout in the Bucharest -Magurele area was determined. (authors)

  19. An important achievement of Professor Ion Stroescu: the wind tunnel of the Polytechnic School of Bucharest

    Directory of Open Access Journals (Sweden)

    Nicolae-Serban TOMESCU

    2011-12-01

    Full Text Available This paper summarizes the contribution of Ion Stroescu to the experimental aerodynamics development in Romania through the design, in collaboration with Professor Elie Carafoli, of the subsonic wind tunnel of the Polytechnic School in Bucharest. Without any exaggeration, the paper also presents the general context in which this construction was built, when aeronautical higher education was being set up in Romania and young aviation industry made strides to world affirmation by its achievements.

  20. Demographic Research On the Socio Economic Background of Students of the Ecological University of Bucharest

    Directory of Open Access Journals (Sweden)

    Janina Mihaela Mihăilă

    2014-06-01

    Full Text Available The paper describes a socio demographic and economic research performed on the first year students at the Ecological University of Bucharest, where we are focusing on understanding and investigating the conditions inside the families and the social environment in the home towns of these students. This research is a key in understanding the correlations between the socio-economic conditions inside the family geographical area and the actual career options and decisions of the newly admitted students to our faculties.

  1. Using R as an alternative teaching tool in the Ecological University of Bucharest

    OpenAIRE

    Ungureanu, Carmen

    2014-01-01

    In a global world universities want to offer the best education to their students so that they can be competitive on the labour market both in the country where they studied and beyond its borders. The Romanian education system – currently undergoing reform – attaches great importance to the use of traditional efficient teaching tools, along with new alternative ones. The R data analysis system represents such an alternative method that the Ecological University of Bucharest uses in ord...

  2. Marketing faculty of Bucharest Economic Studies University: historic landmarks, present and future developments

    OpenAIRE

    Călin Petrică Vegheş; Ionel Dumitru; Ioana Cecilia Popescu; Mihai Cristian Orzan

    2013-01-01

    This paper aims to present the main events that left their mark on the history and evolution of the Marketing Faculty of Bucharest Economic Studies University, an academic body that this will mark its 10th anniversary this fall. As the only school dedicated exclusively to the study of marketing in Romania, as well as one of the few exclusively marketing schools in Europe, the history of the Marketing Department and, subsequently, of the Marketing Faculty overlaps in the last four decades with...

  3. STUDY OF DETERMINANT FACTORS OF DIVIDEND POLICY PROMOTED BY COMPANIES LISTED ON BUCHAREST STOCK EXCHANGE

    OpenAIRE

    Georgeta VINTILA; MOSCU Raluca Georgiana

    2012-01-01

    Dividend policy is one of the most intriguing topics in financial research. Even now, economists provide considerable attention and thought to solving the dividend puzzle, resulting a large number of conflicting hypotheses, theories and explanations. This paper aims to determine the dividend policies for listed companies on Bucharest Stock Exchange and to explain their dividend payment behavior. Ten hypotheses were investigated using a series of models. So this paper investigates why companie...

  4. Tourism and Cultural Heritage: Sector Priorities of Regional Development Policy within Bucharest-Ilfov Region

    Directory of Open Access Journals (Sweden)

    Claudia Ionescu

    2013-08-01

    Full Text Available The sustainable development gets a great importance in the context of Romania integration in the EU and globalization, a context in which the intersection of the economic, social environmental but also cultural and recreational sector is more and more complex. Having in mind this complex context, in this paper, we present a personal point of view regarding the potential for growth in tourism of Bucharest-Ilfov region, due to vast range of tourist offer (cultural, business, recreational. The Bucharest-Ilfov region has a great tourism potential: the attraction capacity of the Bucharest urban centre is enriched by the environmental and cultural value of the areas and sites surrounding the capital city. This combination of urban, business, cultural and environmental resources is a powerful basis for developing the tourism sector in the region. The tourism sector must be a priority of the regional development policy, because of the importance of the tourism contribution to growth and job creation so the infrastructure improvement is therefore a necessity for tourism development. In line with the above, the main goal of this paper is to demonstrate the necessity of increasing the economic importance of the tourism sector within the regional economy.

  5. Computing seismic damage estimates for buildings within a big city. Bucharest case study.

    Science.gov (United States)

    Toma-Danila, Dragos; Armas, Iuliana

    2016-04-01

    The seismic risk analysis of big cities is a very demanding yet necessary task; the modeling of such complex systems requires first of all insightful input data at good resolution, referring to local effects, buildings and socio-economic aspects. Also, seismic risk estimation methods with good confidence levels are needed. Until recently, these requirements were not fulfilled for Bucharest, one of the most endangered capital city in Europe due to earthquakes. Based on 2011 and 2002 census data, standardized according to the framework of the Near-real time System for Estimating the Seismic Damage in Romania (SeisDaRo) through a unique approach and on relevant hazard scenarios, we estimate for the first time the building damage within the city, divided in more than 120 areas. The methodology applied relies on 48 vulnerability curves for buildings, on the Improved Displacement Coefficient Analytical Method included in the SELENA software for computing damage probabilities and on multiple seismic hazard scenarios, including the maximum possible. In order to compare results with real losses we use a scenario based on the 4 March 1977 Vrancea earthquake (7.4 moment-magnitude) that lead to 1424 deaths in Bucharest. By using overlay analysis with satellite imagery and a new methodology integrated in GIS we show how results can be enhanced, reflecting even more local characteristics. Best practices for seismic risk mapping are also expressed. Results are promising and contribute to the mitigation efforts in Bucharest.

  6. Source, propagation and site effects: impact on mapping strong ground motion in Bucharest area

    International Nuclear Information System (INIS)

    Achievements in the framework of the NATO SfP project 972266 focused on the impact of Vrancea earthquakes on the security of Bucharest urban area are presented. The problem of Bucharest city security to Vrancea earthquakes is discussed in terms of numerical modelling of seismic motion and intermediate term earthquake prediction. A hybrid numerical scheme developed by Faeh et al. (1990; 1993) for frequencies up to 1 Hz is applied for the realistic modelling of the seismic ground motion in Bucharest. The method combines the modal summation for the 1D bedrock model and the finite differences for the 2D local structure model. All the factors controlling the ground motion at the site are considered: source, propagation and site effects, respectively. The input data includes the recent records provided by the digital accelerometer network developed within the Romanian-German CRC461 cooperation programme and CALIXTO'99, VRANCEA'99, VRANCEA2001 experiments. The numerical simulation proves to be a powerful tool in mapping the strong ground motion for realistic structures, reproducing acceptably from engineering point of view the observations. A new model of the Vrancea earthquake scaling is obtained and implications for the determination of the seismic motion parameters are analyzed. The role of the focal mechanism and attenuation properties upon the amplitude and spectral content of the ground motion are outlined. CN algorithm is applied for predicting Vrancea earthquakes. Finally, implications for the disaster management strategy are discussed. (authors)

  7. Reactors

    International Nuclear Information System (INIS)

    Purpose: To provide a spray cooling structure wherein the steam phase in a bwr reactor vessel can sufficiently be cooled and the upper cap and flanges in the vessel can be cooled rapidly which kept from direct contaction with cold water. Constitution: An apertured shielding is provided in parallel spaced apart from the inner wall surface at the upper portion of a reactor vessel equipped with a spray nozzle, and the lower end of the shielding and the inner wall of the vessel are closed to each other so as to store the cooling water. Upon spray cooling, cooling water jetting out from the nozzle cools the vapor phase in the vessel and then hits against the shielding. Then the cooling water mostly falls as it is, while partially enters through the apertures to the back of the shielding plate, abuts against stoppers and falls down. The stoppers are formed in an inverted L shape so that the spray water may not in direct contaction with the inner wall of the vessel. (Horiuchi, T.)

  8. DO THE REGIONS OF ROMANIA HAVE POTENTIAL FOR SERVICE INNOVATION? THE CASE OF THE REGION OF BUCHAREST-ILFOV

    Directory of Open Access Journals (Sweden)

    IOSIF ALINA-ELENA

    2015-07-01

    Full Text Available The paper is focused on conducting an assessment on one particular region of Romania, namely the region of Bucharest-Ilfov, in relation to service innovation. The paper starts with an introductory section that reveals the region’s position in terms of competitiveness and innovation within the European Union. Afterwards, a short snapshot on innovation and service innovation is included, followed by a SWOT analysis of the Region of Bucharest-Ilfov. Both the socio-economic performance of the region and the regional performance in service innovation are analyzed. The paper ends with the conclusion section that includes an overview on the main characteristics of the region from the perspective of service innovation. The region of Bucharest-Ilfov is showing its performance in service innovation through various indicators, particularly by the share of employees in service innovation intensive industries and knowledge intensive service that overcome the EU average. Particularly, the enterprises from the Bucharest-Ilfov region are mostly encountered into the services sector, but they are at their beginnings in terms of service innovation. Moreover, most of the innovation comes from SMEs that tend to offer both product and process innovation. Consequently, service innovation in the region of Bucharest-Ilfov is mainly expected to be driven by the SMEs, but taking into account that big companies have their contribution too.

  9. Seismic zonation of Bucharest by using a deterministic approach of numerical modeling

    International Nuclear Information System (INIS)

    Bucharest city represents the largest European center (about 2 million inhabitants and 230 km2 constructed area) periodically subjected to the strong intermediate-depth earthquakes originating in Vrancea region. The statistics indicate a recurrence interval of 25 years for Mw≥7.0 Vrancea events and a significant earthquake hazard for the city location with a 50% chance for an event of Mw>7.6 every 50 years. The strongest Vrancea events of the last century occurred in 1908 (Mw=7.1), 1940 (Mw=7.7), 1977 (Mw=7.4) and 1986 (Mw=7.1) and inflicted heavy damage and casualties in Bucharest. Under these circumstances, the ground motion evaluation for the city area represents an essential step toward the mitigation of the local seismic risk. This paper presents the new insights coming from direct instrumental observation and interpretation of the local effects as well as realistic numerical modeling that update and improve the input data necessary for a detailed microzoning map of the Romanian capital. Our results show that the synthetic local hazard distribution we obtain with the deterministic approach supplies a realistic estimation of the seismic input, highly sensitive not only to the local conditions, but also to the source and the path structure parameters. The complex hybrid method we use offers the chance to merge the different specific accumulated information in reasonably well constrained scenarios for a level C realistic microzonation of Bucharest area to be use to mitigate the effects of future strong events originating in Vrancea region. (authors)

  10. Estimation of site effects in terms of a new microzonation map of Bucharest

    International Nuclear Information System (INIS)

    Bucharest city represents the largest urban center (about 2 million inhabitants and 230 km2 constructed area) located in the Balcan area periodically subjected to strong subcrustal seismicity conditions originating in the Vrancea region (60-200 km depth), Romania. The statistics indicate a recurrence interval of 25 years for Mw≥7.0 Vrancea events and a significant earthquake hazard for the city location with a 50% chance for an event of Mw>7.6 every 50 years. The strongest Vrancea events of the last century occurred in 1908 (Mw=7.1), 1940 (Mw=7.7), 1977 (Mw=7.4) and 1986 (Mw=7.1) and inflicted heavy damage and casualties in Bucharest. Under these circumstances, the ground motion evaluation for the city area represents an essential step toward the mitigation of the local seismic risk. This paper presents new insights coming from direct instrumental observation and interpretation of the local effects as well as realistic numerical modeling that update and improve the input data necessary for a detailed microzoning map of the Romanian capital. Our results show that the synthetic local hazard distribution we obtain with the deterministic approach supplies a realistic estimation of the seismic input, highly sensitive not only to the local conditions, but also to the source and the path structure parameters. The complex hybrid method we use offers the chance to merge the different specific accumulated information in reasonably well constrained scenarios for a level C realistic microzonation of Bucharest area to be used to mitigate the effects of future strong events originating in the Vrancea region. (author)

  11. Functional Zoning and Urban Development Tendencies of Bucharest City/Romania

    Science.gov (United States)

    Armas, Iuliana; Dumitrascu, Silvia

    2010-05-01

    Any form of urban development policy for environmental management should be based on the differentiation of the structure of a territory that can be found in the shape of functional zoning. Identifying the patterns of morphological structure of the urban space can provide essential clues concerning the proper measures to take into consideration during the activity of urban planning. In this sense, the Bucharest municipality study case provides the example of a dynamic urban space with a complex and distinctive evolutionary structure. The aim of the study is to set out the main events that shaped the Bucharest city space and the patterns resulted from their impact at the functional level of the Romanian capital. In order to identify the development tendencies of the Bucharest municipality, a series of aspects concerning urban morphology should be highlighted that reveal the impact of the socio-economical policies at the structural level of the territory. In this sense, three images of the urban space stand out, representative for the period when they materialized: the Post-Byzantine (XV-XVIII), the Fanariot (XVIII) and the Modern periods (XIX-XX). The corresponding cartographic documents analyzed are: the Franz Purcel Plan (dated 1789), the Romanian Guide Print Plan and, respectively, the AGC Busman Print Plan. The analysis reveals three distinctive morphological types: radial-concentric in the 17th century, polynuclear in the 18th century, leading to the mixed character in the Modern period. The latest trait of the urban territory is based on the concentric character of the street network (three circles were identified at the level of the capital city that point out the evolution of the urban space: Dacia bv-Mircea Vulcanescu, Stefan cel Mare bv-Iancu de Hunedoara and the last circle outlined by the ring road) and the presence of multiple nuclei that accumulate the commercial, administrative and business functions of the city.

  12. Rapid fluctuations of the air and surface temperature in the city of Bucharest (Romania)

    Science.gov (United States)

    Cheval, Sorin; Dumitrescu, Alexandru; Hustiu, Mihaita-Cristinel

    2016-04-01

    Urban areas derive significant changes of the ambient temperature generating specific challenges for society and infrastructure. Extreme temperature events, heat and cold waves affect the human comfort, increase the health risk, and require specific building regulations and emergency preparedness, strongly related to the magnitude and frequency of the thermal hazards. Rapid changes of the temperature put a particular stress for the urban settlements, and the topic has been approached constantly in the scientific literature. Due to its geographical position in a plain area with a temperate climate and noticeable continental influence, the city of Bucharest (Romania) deals with high seasonal and daily temperature variations. However, rapid fluctuations also occur at sub-daily scale caused by cold or warm air advections or by very local effects (e.g. radiative heat exchange, local precipitation). For example, in the area of Bucharest, the cold fronts of the warm season may trigger temperature decreasing up to 10-15 centigrades / hour, while warm advections lead to increasing of 1-2 centigrades / hour. This study focuses on the hourly and sub-hourly temperature variations over the period November 2014 - February 2016, using air temperature data collected from urban sensors and meteorological stations of the national network, and land surface temperature data obtained from satellite remote sensing. The analysis returns different statistics, such as magnitude, intensity, frequency, simultaneous occurrence and areal coverage of the rapid temperature fluctuations. Furthermore, the generating factors for each case study are assessed, and the results are used to define some preliminary patterns and enhance the urban temperature forecast at fine scale. The study was funded by the Romanian Programme Partnership in Priority Domains, PN - II - PCCA - 2013 - 4 - 0509 - Reducing UHI effects to improve urban comfort and balance energy consumption in Bucharest (REDBHI).

  13. BUCHAREST-ILFOV REGION – BETWEEN ECONOMIC AND SOCIAL CONVERGENCE AND DIVERGENCE

    Directory of Open Access Journals (Sweden)

    Catalina Mihaela Badoiu

    2014-06-01

    Full Text Available This paper aims to highlight the main economic disparities between the developing regions of Romania, during the 2005-2011/2012 period. We will focus on the Bucharest-Ilfov region, which differs both in terms of population density, and the galloping economic growth, relative to other regions. In terms of the convergence-divergence analysis, it will be based on key indicators, such as the factors that led to increased inter-regional divergence and to what extent the differences between regions were reduced in the analyzed period.

  14. Reducing Fuel Consumption in Bucharest Terminal Area for Flights Using a Standard Instrument Departure

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    Virgil STANCIU

    2011-06-01

    Full Text Available Reconfiguration of the standard instrument departure and standard arrival routes at certain airports can bring significant reductions in fuel consumption and level of noise. This can be done either by implementing modern radionavigation aids for terminal areas or by eliminating the flying restrictions over cities and inhabited places and designing of low level of noise procedures for these areas. These solutions have other important benefits like decreasing the workload for the air traffic controllers and reducing the total flight time. The paper describes an operational solution in this manner for Bucharest Henri Coanda International Airport.

  15. Physics with small and large size facilities at IFIN-HH Bucharest-Magurele

    International Nuclear Information System (INIS)

    The 'Horia Hulubei' National Institute for Physics and Nuclear Engineering (IFIN-HH) in Bucharest-Magurele is the prime research institute in Romania. With 12 departments, it combines the entire range of duties of a nuclear physics national laboratory with fundamental research in nuclear and particle physics and with applications based on atomic and nuclear techniques. After a brief presentation of the whole institute, past, present and future, I will concentrate on physics we do with small accelerators and other facilities, with emphasis on areas of environment and cultural heritage study and preservation. (author)

  16. Using R as an alternative teaching tool in the Ecological University of Bucharest

    Directory of Open Access Journals (Sweden)

    Carmen UNGUREANU

    2014-06-01

    Full Text Available In a global world universities want to offer the best education to their students so that they can be competitive on the labour market both in the country where they studied and beyond its borders. The Romanian education system – currently undergoing reform – attaches great importance to the use of traditional efficient teaching tools, along with new alternative ones. The R data analysis system represents such an alternative method that the Ecological University of Bucharest uses in order to stimulate the student’s creativity in problem solving.

  17. Pinvox Method to Enhance Self-Study in Blended Learning: Experiences at University of Bucharest

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    Enrique Canessa

    2013-05-01

    Full Text Available We report results on the first large-scale trial implementation of the new Pinvox algorithm carried out at the Department of Distance Learning (DL of the University of Bucharest to encourage hundreds of Bachelor and Master DL students to perform their self-study. Pinvox is an open source tool that helps to ensure "on-line attendance” and to induce “student's attention��� through the identification of different, randomly selected, brief audio PINs embedded automatically in videos or audio files assigned to each student. We argue that checking how students watched a video lecture has many advantages in the formative assessment work.

  18. Asymmetric Responses of CAPM - Beta to the Bull and Bear Markets on the Bucharest Stock Exchange

    OpenAIRE

    RĂZVAN ŞTEFĂNESCU; COSTEL NISTOR; RAMONA DUMITRIU

    2009-01-01

    The CAPM - beta is one of the most used tools to estimate the systematic risks associated to stock. In the last decades different behaviours of beta were revealed for the circumstances of the bull and the bear markets. This paper analyses the CAPM – beta responses for bad and good news for ten representative stocks from the Bucharest Stock Exchange. We identify the bull, the bear and the tranquil markets using a univariate kernal density function and we calculate for each stage the single and...

  19. A new and compact system at the AMS laboratory in Bucharest

    Science.gov (United States)

    Stan-Sion, C.; Enachescu, M.; Petre, A. R.; Simion, C. A.; Calinescu, C. I.; Ghita, D. G.

    2015-10-01

    AMS research started more than 15 years ago at our National Institute for Physics and Nuclear Engineering (IFIN-HH), Bucharest. A first facility was constructed based on our multipurpose 9 MV tandem accelerator and was upgraded several times. In May 2012 a new Cockcroft Walton type 1 MV HVEE tandetron AMS system, was commissioned. Two chemistry laboratories were constructed and are routinely performing the target preparation for carbon dating and for other isotope applications such as for geology, environment physics, medicine and forensic physics. Performance parameters of the new system are shown.

  20. Analysis of the seismic wavefield in the Moesian Platform (Bucharest area)

    Science.gov (United States)

    -Florinela Manea, Elena; Hobiger, Manuel-Thomas; Michel, Clotaire; Fäh, Donat; -Ortanza Cioflan, Carmen

    2016-04-01

    Bucharest is located in the center of the Moesian platform, in a large and deep sedimentary basin (450 km long, 300 km wide and in some places up to 20 km depth). During large earthquakes generated by the Vrancea seismic zone, located approximately 140 km to the North, the ground motion recorded in Bucharest area is characterized by predominant long periods and large amplification. This phenomenon has been explained by the influence of both source mechanism (azimuth and type of incident waves) and mechanical properties of the local structure (geological layering and geometry). The main goal of our study is to better characterize and understand the seismic wave field produced by earthquakes in the area of Bucharest. We want to identify the contribution of different seismic surface waves, such as the ones produced at the edges of the large sedimentary basin or multipath interference waves (Airy phases of Love and Rayleigh waves) to the ground motion. The data from a 35 km diameter array (URS experiment) installed by the National Institute for Earth Physics during 10 months in 2003 and 2004 in the urban area of Bucharest and adjacent zones was used. In order to perform the wave field characterization of the URS array, the MUSIQUE technique was used. This technique consists in a combination of the classical MUSIC and the quaternion-MUSIC algorithms and analyzes the three-component signals of all sensors of a seismic array together in order to analyze the Love and Rayleigh wave dispersion curves as well as the Rayleigh wave ellipticity curve. The analysis includes 20 regional earthquakes with Mw >3 and 5 teleseismic events with Mw> 7 that have enough energy at low frequency (0.1 - 1 Hz), i.e. in the resolution range of the array. For all events, the greatest energy is coming from the backazimuth of the source and the wave field is dominated by Love waves. The results of the array analyses clearly indicate a significant scattering corresponding to 2D or 3D effects in the

  1. The contribution of waste management to the reduction of greenhouse gas emissions with applications in the city of Bucharest.

    Science.gov (United States)

    Sandulescu, Elena

    2004-12-01

    Waste management is a key process to protect the environment and conserve resources. The contribution of appropriate waste management measures to the reduction of greenhouse gas (GHG) emissions from the city of Bucharest was studied. An analysis of the distribution of waste flows into various treatment options was conducted using the material flows and stocks analysis (MFSA). An optimum scenario (i.e. municipal solid waste stream managed as: recycling of recoverable materials, 8%; incineration of combustibles, 60%; landfilling of non-combustibles, 32%) was modelled to represent the future waste management in Bucharest with regard to its relevance towards the potential for GHG reduction. The results indicate that it can contribute by 5.5% to the reduction of the total amount of GHGs emitted from Bucharest. PMID:15666445

  2. Towards Sustainable Tourism Development in Urban Areas: Case Study on Bucharest as Tourist Destination

    Directory of Open Access Journals (Sweden)

    Andreea Zamfir

    2015-09-01

    Full Text Available The issues of tourism sustainability and urban development have become major priorities for public policy makers across the globe. Today, maybe more than ever, there is a need for managing sustainable tourism development, and this cannot be attained without taking into account environmental problems and their global dimension. Various problems and requirements of society and of the development of urban areas may be solved by transforming the cities into attractive tourist destinations. Therefore, this study explores how sustainable tourism development in urban areas can be basically achieved and managed. The paper discloses some success factors for managing sustainable tourism development in urban areas and emphasizes a case study regarding Bucharest, the capital of Romania, as a tourist destination. The originality and value of this study consist of identifying the main ways of developing sustainable tourism in Bucharest based upon empirical research conducted with the aid of a survey. The findings of this study may be helpful for upcoming research in the area of managing sustainable urban tourism development.

  3. COMPREHENSIVE COMMUNICATION AND THE QUALITY OF INTERPERSONAL RELATION BUCHAREST STUDENTS BEHAVIOURAL PATTERNS IN INTERPERSONAL COMMUNICATION

    Directory of Open Access Journals (Sweden)

    Elena NEDELCU

    2010-12-01

    Full Text Available The first part of this paper will deal with the quality of interpersonal communication in a world in full process of technologization – globalisation. Without underestimating the benefits of information technology and “plethoric” communication we outline the unwanted impact they have when used excessively and exclusively in interpersonal communication. In the second part, we will talk about the connections between the quality of interpersonal relation and the behavioural options of the interlocutors in communication. We will show that achieving a high relational coefficient is an aspect conditioned by practicing comprehensive communication, and empathic listening. The third part synthesises the results of a social survey based on questionnaire. The survey’s goal was to find the behaviours of Bucharest students in their interpersonal communication and to find the way they perceive the quality of communication in Romanian society. It emphasises that in Romanian society the un-comprehensive behaviours are at all levels of society, which limits, blocks, distorts communication, maintaining a general low relational coefficient. Bucharest students experience an emphasised feeling of limitation. This restricts their freedom of expression, suffocating their aspiration to profound first-rate communication.

  4. Informational database methodology for urban risk analysis.Case study: the historic centre of Bucharest

    Science.gov (United States)

    Armas, I.; Dumitrascu, S.

    2009-04-01

    The urban environment often deals with issues concerning the deterioration of the constructed space and the quality of the environmental factors, in general terms meaning an unsatisfactory quality of life. Taking into account the complexity of the urban environment and the strong human impact, this ambience can be considered the ideal place for a varied range of risks to appear, being favoured by the external interventions and the dynamics of the internal changes that occur in the urban system, often unexpectedly. In this context, historic centre areas are even more vulnerable because of the age of the buildings and their socio-cultural value. The present study focuses on the development of a rapid assessment system of urban risks, putting emphasis on earthquakes. The importance of the study is shown by the high vulnerability that defines urban settlements, which can be considered socio-ecological systems characterized by a maximum risk level. In general, cities are highly susceptible areas because of their compactness and elevated degree of land occupancy, the Bucharest municipality being no exception. The street and sewerage networks disorganized the natural system resulted from the evolution of the lake-river system in Superior Pleistocene-Holocene and the intense construction activity represents a pressure that hasn't been measured and that is in need for a methodological interdisciplinary approach. In particular, the specific of Bucharest is given by the seismic risk based on an explosive urban evolution and the advanced state of degradation of the buildings. In this context, the Lipscani sector from the historic centre of the capital city is a maximum seismic vulnerability area, this being the result of its location in the Dâmbovita River meadow, on the brow and 80 m terrace, but more precisely because of the degradation of the buildings that cumulated the effects of the repeated earthquakes. The historic centre of Bucharest has not only a cultural function

  5. The Second Conference of Ministers of Education of European Member States (Bucharest, 1973). International Bureau of Education Reference Service 3.

    Science.gov (United States)

    International Bureau of Education, Geneva (Switzerland).

    A catalog of the computer-stored data and the SIRE microfiche series relating to the Second Conference of Ministers of Education of European Member States, held in Bucharest in 1973, is presented. Twenty-eight reports on the theme "Higher Education in Europe" are included in the catalog. The broad topics of correspondence courses, educational…

  6. ASSESSING THE FOREIGN CHILDREN’ SITUATION INTO THE ROMANIAN EDUCATIONAL SYSTEM. AN EMPIRICAL APPROACH FOR THE REGION OF BUCHAREST-ILFOV.

    Directory of Open Access Journals (Sweden)

    Aurica-Iris ALEXE

    2016-05-01

    Full Text Available This research paper analyses the situation of the third-country national children in Romania regarding their access and participation into the Romanian educational system. It is an empirical approach with a special focus on migrant children in the public and private educational system in the Bucharest-Ilfov region where more than a half of the third-country nationals are to be found. The paper provides a qualitative and quantitative analysis regarding the number of non-EU children in the public and private education system in Bucharest-Ilfov, their distribution by age group and type of school: primary, secondary, high-school as well as the schools with high agglomeration of foreign pupils and their distribution in the neighborhoods of Bucharest-Ilfov. The analysis uses, as well, primary data collected during the year of 2013, when a number of 60 schools in the region Bucharest-Ilfov were approached by phone, through emails and face-to-face meetings in order to find out whether they had foreign pupils enrolled in their school and what was the situation on the ground in those schools that reported foreign pupils.

  7. Effect of Foster Care on Language Learning at Eight Years: Findings from the Bucharest Early Intervention Project

    Science.gov (United States)

    Windsor, Jennifer; Moraru, Ana; Nelson, Charles A., III.; Fox, Nathan A.; Zeanah, Charles H.

    2013-01-01

    This study reports on language outcomes at eight years from the Bucharest Early Intervention Project, a randomized controlled study of foster care. We previously have shown that children placed in foster care by age two have substantially stronger preschool language outcomes than children placed later and children remaining in institutional care.…

  8. Identifying and monitoring urban heat island in Bucharest using satellite time series and low cost meteorological sensors

    Science.gov (United States)

    Sandric, Ionut; Onose, Diana; Vanau, Gabriel; Ioja, Cristian

    2016-04-01

    The present study is focusing on the identification of urban heat island in Bucharest using both remote sensing products and low cost temperature sensors. The urban heat island in Bucharest was analyzed through a network of sensors located in 56 points (47 inside the administrative boundary of the city, 9 outside) 2009-2011. The network lost progressively its initial density, but was reformed during a new phase, 2013-2015. Time series satellite images from MODIS were intersected with the sensors for both phases. Statistical analysis were conducted to identify the temporal and spatial pattern of extreme temperatures in Bucharest. Several environmental factors like albedou, presence and absence of vegetation were used to fit a regression model between MODIS satellite products sensors in order to upscale the temperatures values recorded by MODIS For Bucharest, an important role for air temperature values in urban environments proved to have the local environmental conditions that leads to differences in air temperature at Bucharest city scale between 3-5 °C (both in the summer and in the winter). The UHI maps shows a good correlation with the presence of green areas. Differences in air temperature between higher tree density areas and isolated trees can reach much higher values, averages over 24 h periods still are in the 3-5 °C range The results have been obtained within the project UCLIMESA (Urban Heat Island Monitoring under Present and Future Climate), ongoing between 2013 and 2015 in the framework of the Programme for Research-DevelopmentInnovation for Space Technology and Advanced Research (STAR), administrated by the Romanian Space Agency Keywords: time series, urban heat island

  9. Preliminary study on epiphytic lichens as an indicator of environmental quality in forests from around Bucharest Municipality (Romania

    Directory of Open Access Journals (Sweden)

    Ioana VICOL

    2010-05-01

    Full Text Available The epiphytic lichens were investigated for three forests situated around Bucharest Municipality. The comparative historical background studies concerned with epiphytic lichens in relation to environmental conditions were related. Five variables close related with the distance was analysed within this study, as follow: (1 in close correlation with the distance, the taxonomic analysis reveals a major significance regarding the dominant roll of the genera with a low epiphytic lichens diversity, within the Andronache Forest, unlike Cernica and Pustnicul Forest where, the number of genera is do not significantly owing increasing species number; (2 regarding the substrate, epiphytic lichens species from all investigated forests prefer trees with a roughly rhytidoma. Trees sampled in a great deal belong to the Quercus genus with a roughly rhytidoma facilitating a good growing of epiphytic lichens species because keeps for a long periods of time a high degree of humidity; (3 the analysis of toxi-tolerance degree has shown how the sensitive epiphytic lichens species to pollution is increasing depending on the distance; (4 autsozological categories are marked in a great deal by a great distance from an urban Bucharest area. Thus, the number of rare and disappearing lichens species is increasing direct proportional depending on the distance from the Bucharest Municipality area to investigated forests due to improvement of the environmental quality; (5 from geographical distribution of lichens species point of view, take a place an increasing number of epiphytic lichens species which is close correlated with the distance from Bucharest Municipalityarea to investigated forests. In addition, a great importance was conferred the presence of rare and disappearing epiphytic lichensspecies nearest perturbation area of Bucharest Municipality (Andronache Forest. This fact is possible to occur owing to thedirection of prevailed winds. It was used of sensitivity

  10. The month-of-the-year effect on Bucharest Stock Exchange

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    Iulian Panait

    2013-03-01

    Full Text Available This study investigates the presence of month-of-the-year effect on Bucharest Stock Exchange using a both a linear regression and a GARCH-M model with dummy variables for both the mean and the variance equation. We have collected monthly returns for five Romanian official exchange indices and for one MSCI Barra country index during May 2007-March 2013, thereby including both the 2007-2009 financial crisis and the recovery that followed during 2009-2013. Our results show that none of the coefficients of the two models are statistically significant, which lead us to conclude that we can not confirm the presence of the January effect or of any other month-of-the-year effect on the Romanian capital market.

  11. ANALYSIS OF THE BANKING SYSTEM THAT QUOTES AT BUCHAREST STOCK EXCHANGE

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    SUCIU Titus

    2014-06-01

    Full Text Available This study analyses three important banks quoted at Bucharest Stock Exchange: Banca Transilvania SA, BRD – Groupe Société Générale SA, Banca Comecială Carpatica SA. The scope is to identify which is the best to invest in. We follow the instruments give us by the fundamental analysis: Price/ Earning ratio, Capitalization, Return on Assets, Return on Equity, Debt to Assets, Dept to Equity. Fundamental analysis presumes the future prospects of a security are best analyzed through a proper assessment of the intrinsic value of the underlying company. The risk is within us. In the end, the financial risk does not lie in what types of investments have we done, but in what type of investor we are.

  12. COMPARATIVE RESEARCH ON THE FUNDAMENTAL ANALYSIS OF SHARES FROM COMPANIES LISTED ON BUCHAREST STOCK EXCHANGE

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    Mihaela-Cristina Onica

    2015-05-01

    Full Text Available Upon passing to a market economy, it became necessary to find out information as accurate as possible regarding the risk of bankruptcy of a certain companyin the future, in order to determine the share of such a risk and the importance of the fundamental analysis within the prediction of the evolution of stock price. In spite of these, specialists say that this type of analysis, in relation to the technical analysis, in the context of the financial crisis, determined an accentuated decrease of the stock exchange indices on an international level. The paper deals with the results of the research and of a comparative study regarding the fundamental analysis of the shares of 6 companies listed on Bucharest Stock Exchange (BVB.

  13. Potential of the Bucharest 3 MV Tandetron™ for IBA studies of deer antler mineralization

    Science.gov (United States)

    Gomez, S.; Garcia, A.; Landete-Castillejos, T.; Gallego, L.; Pantelica, D.; Pantelica, Ana; Preoteasa, E. A.; Scafes, Adela; Straticiuc, M.

    2016-03-01

    Combined PIXE and PIGE analysis was applied at the new Bucharest Tandetron to investigate biomineralization in two calcified tissues, deer antlers and femur bone. By annual loss and fast re-growth, antlers are a valuable model for bone as a dynamical system. Samples characterized by optical microscopy and histology were analyzed for P, Ca, F, Na, Mg, S, Cl, K, Zn, Sr by 3 MeV proton simultaneous PIXE and PIGE, using a hydroxyapatite standard and other reference materials. Good correlation between methods was found for P, and the concentrations were related to biological data. Antlers showed lower mineralization than femur, with the lowest values in the third antler beam. A power function of mineralization vs. "mineral age" of antlers was found. Thus combined PIXE and PIGE of antlers may bring highly relevant insights in biomineralization research.

  14. A SECTORIAL ANALYSIS OF THE FINANCING PRACTICES OF THE ROMANIAN COMPANIES LISTED ON BUCHAREST STOCK EXCHANGE

    Directory of Open Access Journals (Sweden)

    Laura Raisa MILOŞ

    2009-01-01

    Full Text Available Maintaining the market share of a company, as well as increasing it, implies using an adequate financial policy. The liabilities ratios allow the analysis of this adopted financial policy, by giving useful information about the structure of financing (debt or equity, emphasizing upon some important aspects like financial stability, financial autonomy or indebt. In this paper, the authors try to realize an empirical analysis, upon a sample of 40 reprezentative Romanian companies, all listed on Bucharest Stock Exchange, from different fields of activity (financial, energetic, quemical, equipments and materials sector. Using their financial statements for the period 2002-2007, for the computation of the financial ratios, the authors draw up useful and recent information about the pecularities or similarities between the 5 different sectors, as far as concerns the structure of their liabilities.

  15. SKEWNESS IN STOCK RETURNS: EVIDENCE FROM THE BUCHAREST STOCK EXCHANGE DURING 2000 – 2011

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    IULIAN PANAIT

    2012-05-01

    Full Text Available Our paper investigates the symmetry in stock returns of the 30 most liquid companies traded on Bucharest Stock Exchange during 2000 – 2011 and also the most representative 5 market indices. Our daily data shows that skewness estimates are slightly negative for most indices and individual stocks, but only a few present values significantly different from the characteristics of a normal distribution. We compare our results with skewness estimates for 21 major and emerging stock market indices around the world and find that such results are similar to other low capitalization and trading volume markets. For all the Romanian and international assets studied, the Studentized-Range (St-R and Jarque-Bera (J-B tests reject the hypothesis of normal distribution of daily returns.

  16. THE DETERMINANTS OF PROFITABILITY IN COMPANIES LISTED ON THE BUCHAREST STOCK EXCHANGE

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    SORANA VĂTAVU

    2014-10-01

    Full Text Available This research aims to establish the determinants of financial performance in 126 Romanian companies listed on the Bucharest Stock Exchange, over a period of ten-years (2003-2012. The analysis is based on cross sectional regressions. Return on assets is the performance proxy, while the variables expected to have a significant impact on profitability are debt, asset tangibility, size, liquidity, taxation, risk, inflation and crisis. Regression results indicate that profitable companies operate with limited borrowings. Tangibility, business risk and the level of taxation have a negative impact on return on assets. Although earnings are sustained by significant sales turnover, performance is affected by high levels of liquidity. Periods of unstable economic conditions, reflected by high inflation rates and the current financial crisis, have a strong negative impact on corporate performance.

  17. Assessment of the Green Infrastructure of Bucharest using CORINE and Urban Atlas data

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    Alexandru-Ionuţ Petrişor

    2015-06-01

    Full Text Available Urban ecology provides the theoretical foundation for assessing the interaction between man and nature in cities. Nature seems to be reduced and malfunctioning, resulting into a decrease in the ecosystem services provided to humans. The new method, based on assessing the green infrastructure, is designed to replace monetary and carbon footprint assessments and be particularly relevant for the urban areas, which grow and change fast and are the main drivers of environmental changes. This study uses 2005-2007 CORINE and Urban Atlas data to look at Bucharest. The results show that, despite of the method, the area occupied by the green infrastructure represents about 1/3 of the total area, corresponding to 50 m2/person, although the green spaces only account for 6.5 m2/person, which is far below the European average (26 m2/person.

  18. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    International Nuclear Information System (INIS)

    The VVR-S Nuclear Research Reactor at the 'Horia Hulubei' National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper. (author)

  19. Forecast the Impact of Bucharest – Braşov Highway on the Economic and Functional Structure of Human Settlements in Ilfov County

    Directory of Open Access Journals (Sweden)

    PETRONELA NOVĂCESCU

    2011-01-01

    Full Text Available One of the most publicized issues concerning the infrastructure of Romania is the Bucharest-Braşov highway. The long-awaited project aims to streamline the traffic between the Capital and the central part of the country, representing the central area of the Pan - European Road Corridor IV. The length of the highway on the territory of Ilfov County is 31 km, representing 17% of the total length of Bucharest- Braşov highway. The start of the highway will have strong effects on economic structure and on the way the Bucharest Metropolitan Area will work. We can expect an increase in the disparities between the settlements of Ilfov County. This pattern is also observable on the Bucharest-Ploieşti corridor where, in recent years, much of the Ilfov county's economic activities have migrated to the north, especially along that corridor. Besides economic migration, intense residential migration followed the Bucharest – Ploieşti corridor, residents of the Bucharest itself moving out to the north of Ilfov County. Probably, the future Bucharest – Braşov highway will lead to an increased suburbanization and periurbanization, this in turn giving way to the crowding of the area by businesses eager to have access to the highway. This project will likely increase the gap between north and south of Ilfov County. In addition to changes that may occur at the county level, changes will also have an impact on the localities themselves since the areas located near the highway will have an economic and demographic growth rate superior to more remote areas. In this sense, we conducted a comparative analysis between eight settlements of Ilfov county crossed by the Bucharest-Braşov highway in order to assess the impact. This analysis was based on the information obtained from site and statistical indicators that were processed to obtain a clear picture of the situation in the examined territory.

  20. Leadership Strategies in Promoting the Image of the Mayors on the Websites of Sector Town Halls and of Bucharest City Hall

    OpenAIRE

    Viorica PĂUȘ

    2016-01-01

    The research deals with the leadership strategies used by the mayors of the six sectors and the General Mayor of Bucharest in order to represent and promote the organizational image and their own image. The success, performance and competitiveness of sector town halls and Bucharest City Hall also depend on the quality of leadership and the leaders’ ability to use appropriate, attractive and customized online communication strategies in order to inform the citizens and achieve their electoral ...

  1. H/V spectral ratios technique application in the city of Bucharest: Can we get rid of source effect?

    International Nuclear Information System (INIS)

    The main issue of this paper is to show that, contrary to many examples of monitored strong earthquakes in different urban areas, the intensity and spectral characteristics of the strong ground motion induced in the Bucharest area, by Vrancea intermediate- depth earthquakes, is controlled by the coupled source-site properties rather than by the local site conditions alone. Our results have important implications on the strategy to follow when assessing the seismic microzoning for Bucharest city: we recommend the application of deterministic approaches rather than empirical techniques, like H/V spectral ratios. However, when applied to noise data, the H/V spectral technique succeeds in reproducing the predominant frequency response characteristic for the sedimentary cover beneath the city and the relatively uniform distribution of this structure over the city area. Our results strongly disagree with any strategy of extrapolation from small and moderate earthquakes to strong earthquakes for microzoning purposes. (author)

  2. Decisions of hypermarkets location in dense urban area – effects on streets network congestion in the Bucharest case

    Directory of Open Access Journals (Sweden)

    Eugen ROSCA

    2008-01-01

    Full Text Available The paper represents some partial results of the research carried out by the Transportation, Traffic and Logistics Department - University POLITEHNICA of Bucharest, funded by the Romanian Ministry of Research and Education through the National University Research Council. In this paper we provide: a brief description of the interrelation between the life style changes of Romanian people during the last decades and the car traffic congestion in large cities; the streets network modelling of a radial-circular urban structure (the characteristic of a historically developed city as Bucharest city is, in case of car traffic congestion; the assessment model of the additional car traffic congestion for certain locations with large attractivity. Having an important effect on the entire lifestyle of urban people, the decision of a hypermarket location might be a complex one, taking into consideration the new leisure and shopping tendencies but also the additional car traffic congestion caused by the chosen location.

  3. The companies financial architecture and the market values: is there an interlinkage ? The case of Bucharest Stock Exchange

    OpenAIRE

    Pirtea, Marilen; Bogdan DIMA; Laura Raisa MILOS

    2009-01-01

    Nowadays there is a large debate on whether the financial information proves any relevance for the investors´ prediction of the securities market values/stock prices. The paper focuses, besides reviewing some important literature concerning this issue, on an empirical analysis taking into consideration 44 companies listed on Bucharest Stock Exchange based on pool data linear regressions. It is true that the most recent research state that there is an important evidence of a deterioration of t...

  4. PARENTING AND SOCIAL ROLES IN TURKISH TRADITIONAL FAMILIES: ISSUES AND CHOICES IN PARENTING FOR TURKISH EXPATRIATE FAMILIES LIVING IN BUCHAREST

    OpenAIRE

    Ahmet ECIRLI

    2012-01-01

    This article looks into the issues and challenges of parenting in Turkish families upholding traditional values that live in Bucharest, the capital of Romania. Based on theoretical mainstreams on parenting and the structure of Turkish families, a qualitative research was designed with two aims. The first was to describe the issues and choices in parenting for Turkish expatriate families living in a foreign country. The second was to find out to which of the three ideal-types of families accor...

  5. Board of Directors Independence and Firm Value: Empirical Evidence Based on the Bucharest Stock Exchange Listed Companies

    OpenAIRE

    Georgeta Vintila; Stefan Cristian Gherghina

    2013-01-01

    This paper examines the influence and causal relationship between board of directors independence, CEO duality, and firm value. By estimating multivariate regression models for panel data, unbalanced, for a sample of companies listed on the Bucharest Stock Exchange, there resulted a positive influence of the percentage of independent directors on firm value, but down to a threshold of their representation of 47.23 percent, whereupon their influence becomes negative. When we employed fixed-eff...

  6. The Vision and Mission of the University. Case Study – The Academy of Economic Studies of Bucharest

    OpenAIRE

    Constantin Bratianu; Ionela Jianu

    2007-01-01

    The purpose of this study is to present the meaning of the vision and mission statements for a university, in a strategic management reference. We will consider the vision and mission statements of some known world class universities, in order to illustrate the essential points of such formulations. Then, we will perform a critical analysis of the existing vision and mission statements of the Academy of Economic Studies from Bucharest and suggests new statement formulations, as they are essen...

  7. OBSERVING THE PURCHASING BEHAVIOUR OF THE INDIVIDUALS IN THE LARGE SURFACE STORES DURING THE 2012 WINTER HOLIDAYS IN BUCHAREST

    OpenAIRE

    Mihai Papuc; Tudor Edu

    2013-01-01

    The purpose of our endeavour was to identify the buying behaviour during the 2012 winter holidays. We focused on large surface stores for several reasons. First of all, in Bucharest, there is a strong tendency toward purchasing from the modern retail. Secondly, the assortment displayed in these stores covers, probably, the widest array of needs. Thirdly, the consumer behaviour during this time of the year is more squander-oriented than thrift-oriented. All the above-mentioned coordinates supp...

  8. The Black Sea one decade after the Bucharest Convention an overview of the international activities in the Black Sea Region

    OpenAIRE

    Göktepe, B. Gül

    2002-01-01

    Abstract The catastrophic degradation of the Black Sea in a period of four decade has been the major concern of the Black Sea countries and international communities since the Bucharest Convention signed in 1992.The Black Sea Region has became a challenging intemational arena for political, scientific and socioeconomic activities. Intensive international programmes and establishment of governmental and Non Governmental Organizational structures of the 1990s including Black Sea Economic ...

  9. Wan light of Lithuania in Bucharest. The sources of a non-declared divorce (1918-1926

    Directory of Open Access Journals (Sweden)

    Florin Anghel

    2010-08-01

    Full Text Available Between the Acts of Union and, respectively, of Independence of 1918 and 1926 Romania and Lithuania shared no strategic interests or common regional politics. Although the Bucharest diplomacy insistently asked Warsaw to debate over its Baltic policy, at the end the Romanian-Polish anti-Soviet alliance became one of the most important pieces of so-called “cordon sanitaire” geopolitics, which included Baltic and Black Seas regions countries, but no Lithuania. Both states became locked in cold relations with no contacts and no recognition (until August 1924, which was due to regional politics, but contrary to common interests. The diplomatic relations, officially opened in August 1924, lacked any practical political consequences. The Kaunas coup d’état of December 1926 had little political and media impacts in Bucharest and, in the rarely definitions of Antanas Smetona new nationalist regime, most of Romanians condemned it (contrary with their attitude towards the coup d’état of Warsaw in May 1926. It was only in the last half of the ‘30s that between Bucharest and Kaunas new avenues in bilateral relations had opened, the impact of the fortunate decision of foreign minister Nicolae Titulescu in 1934 to create a Romanian Legation to cover Lithuania.

  10. WHAT MOTIVATES CULTURAL TOURISTS? AN ANALYSIS OF BUCHAREST INHABITANTS' MOTIVATION TO VISIT THE CENTRE REGION

    Directory of Open Access Journals (Sweden)

    Ravar Anamaria Sidonia

    2013-07-01

    Full Text Available Cultural tourism is currently one of the main driving forces of the tourist phenomena, accounting for a significant part of the world's tourist flows. Cultural tourism may take many forms, according to the motivation behind tourists' impetus to travel to a certain destination. Cultural heritage and historical sites, dance, music and theatre performances, art galleries, museums and exhibitions, religious and worship sites and ethnic traditions are the main attractions for tourists motivated by knowledge seeking, self-development and the desire to experience other cultures. Although cultural motivations play an important role in the generation of tourist flows towards cultural tourism destinations, a tourism experience is rarely generated as a result of a single motivation. The act of choosing a specific destination and tourism product is influenced by multiple motivations, not only cultural but also connected to relaxation or family. Furthermore, tourism products are rarely homogeneous – a single holiday may include experiences with cultural content as well as leisure time, sports, adventure or entertainment. Thus, culture is not always the main motivation behind cultural tourism and may in fact be less central to the decision to travel than other factors. This is particularly true in the case of destinations which dispose of various cultural assets, but whose natural tourist resources – such as landscape, climate, access to the sea – also makes them attractive for other types of tourism. The aim of this article is to show that in the case of tourist destinations where cultural attractions represent the vast majority of the areas' tourist heritage, cultural motivations remains central to the decision to travel. Furthermore, we will seek to identify the main types of cultural attractions that motivate cultural tourism in Romania by investigating Bucharest inhabitants' perception of the Centre Region, a cultural destination par excellence in

  11. [Population policies: evolution of the position of the Sahelian countries since the Bucharest conference].

    Science.gov (United States)

    Sow, E B

    1992-07-01

    This work describes the evolution of population policies and attitudes toward them in the Sahel countries since the 1974 World Population Conference. Recommendations of several important international population conferences in which the Sahelian countries participated are then listed. The Bucharest Conference is widely regarded as the 1st serious attempt at coordinated action on population. The divergent approaches of the developed and developing countries toward population phenomena became obvious at the Conference. The developed countries of the north expected the less developed countries of the south to pledge greater efforts at controlling demographic growth, which they viewed as impeding economic development. The countries of the south on the other hand saw the problem as 1 of unequal distribution of wealth. Many African countries also believed their economic growth would be accelerated by the additional workers they would eventually gain through population growth. Reduced population growth in this view would result from rather than contributing to development. Despite these disagreements, Conference participants adopted the World Population Plan of Action which made 5 recommendations including establishment and promotion of family planning education and services. Numerous countries began to pay greater attention to population variables in their development planning after Bucharest. The Sahel countries participated in the Arusha Conference, a July 1984 meeting of African countries preceding the World Population Conference in Mexico City, and in the Mexico City Conference. The Arusha Conference adopted the "Program of Action of Kilimanjaro Concerning African Population and Autonomous Development", which contained 16 recommendations to governments to recognize the interdependence of demographic factors and development. By the 1984 Mexico City Conference, various events such as the drought, chronic economic problems, and rapid population growth combined to bring

  12. Safe operation of TRIGA reactor in the situation of LEU-HEU core conversion

    International Nuclear Information System (INIS)

    Romanian TRIGA reactor was commissioned in 1980. The location of the research institute is Pitesti, 100 Km west of Bucharest. In fact there are two independent cores sharing the same pool. There are a 14 MW Steady State Reactor (SSR), high flux, and materials testing reactor and an Annular Core Pulsing Reactor (ACPR). The SSR reactor is a forced convection reactor cooled via a primary circuit with 4 pumps and 3 heat exchangers. The ACPR is natural convection reactor cooled by the pool water. The characteristics of the two reactors are presented. The reactor core configuration is shown as well as the original start-up core configuration. Fuel management of TRIGA steady state core allows obtaining the requested fluxes for experimental purposes in safe operation condition. One can firmly state that the present operation of the reactor and the HEU-LEU (High Enriched Uranium - Low Enriched Uranium), core conversion fully respect the provisions of the National Regulatory Body and IAEA. (authors)

  13. Information Systems Audit for University Governance in Bucharest Academy of Economic Studies

    Directory of Open Access Journals (Sweden)

    Ion Gh. ROSCA

    2010-01-01

    Full Text Available Today's successful audit leaders never lose sight of the importance of continually assessing and improving the organizations' university governance structure. Focusing on small and large mission, and using practical exercises and individual activities, the auditors will help gain the skills necessary to review and improve university governance structure, while developing techniques to assess risk management activities. Attendees will leave with an understanding of legal and regulatory guidelines as they pertain to university governance and discuss in-depth issues such as business ethics, transparency and disclosure, IT governance and university risks management. Identification, evaluation and management of university risks, is an important element of the university governance system. Today, the Bucharest Academy of Economic Studies is in a complex process to realize a university governance integrate information system. In context of this paperwork there are presented the main aspects for developing and implementing in actual phase information systems audit, to recognize the risks and establish the necessary measures to eliminate them.

  14. Marketing faculty of Bucharest Economic Studies University: historic landmarks, present and future developments

    Directory of Open Access Journals (Sweden)

    Călin Petrică Vegheş

    2013-06-01

    Full Text Available This paper aims to present the main events that left their mark on the history and evolution of the Marketing Faculty of Bucharest Economic Studies University, an academic body that this will mark its 10th anniversary this fall. As the only school dedicated exclusively to the study of marketing in Romania, as well as one of the few exclusively marketing schools in Europe, the history of the Marketing Department and, subsequently, of the Marketing Faculty overlaps in the last four decades with that of Romanian marketing higher education, as well as with the graduate transformation of Romania’s economy to a post-industrial, information-based and customer centric economy. Part of Economic Sciences domain, marketing contains a set of concepts, tools, methods and techniques through which the organization, irrespective of its profile, analyzes the environment where it lives (marketing research, sets goals and strategies to be achieved (strategic marketing planning, design and execute operational activities (marketing programs in order to maximize profits and to satisfy customer’s and society’s needs at the required level. Marketing as a strategic and operational area, captures the interest of Romanian managers and specialists of international organizations, being a source of competitive advantage and positioning of the company and its portfolio brands, in the mind and soul of current and potential customers

  15. Henri H. Stahl’s conception of historical sociology and the Bucharest School of Sociology

    Directory of Open Access Journals (Sweden)

    Nerijus Babinskas

    2010-11-01

    Full Text Available The Romanian school of sociology founded by Dimitrie Gusti was a favorable medium for elaborating theoretic ideas. The school became a cradle for at least two prominent theoreticians (Henri H. Stahl and Traian Herseni whose conceptions are worth of attention not only from sociologists but for the theoretically minded historians, too. We should keep in our mind that according to the methodological attitudes of the Bucharest school field researches were highly encouraged. It means that any generalizations, theoretic suggestions or entire conceptions produced by the followers of Gusti were solidly based on empirical data. Stahl started to elaborate his conception of tributalism in the 1960s. Coincidently, at this period the international discussion about the so-called Asiatic mode of production revived so the Stahl‘s theoretic ideas were well-timed. Stahl was not the only Romanian scholar who got involved in the discussion, but his conception was more original: according to him, tributalism should be treated as something different from Oriental despotism although there were some obvious similarities between the two. Despite the fact that the majority of Romanian historian community ignored the Stahl’s innovative conception, there were some attempts in Romania as well as abroad to elaborate (Daniel Chirot or at least to popularize (Miron Constantinescu, Constantin Daniel his ideas.

  16. Bucharest cyclotron as intense fast neutron source for radiobiological and analytical applications

    International Nuclear Information System (INIS)

    Due to interest for applications in radiobiology and material testing, Bucharest U-120 classical variable energy Cyclotron is employed as an intense source of fast neutrons, using 13.5 MeV deuterons bombarding a Beryllium target placed at 20 deg against the incident beam. Energy spectra, yields, average energy and irradiation doses were determined using time-of-flight (TOF), multiple foils and thermoluminescent detectors (TLD) methods. The average energy is 5.24 MeV. The total yield at 0 deg, obtained by summing up the yields for neutron energies between the lower (0.3 MeV) and upper (17 MeV) thresholds, is 6.7 x 1016 n/sr.C.MeV. The yield of the low energy component (0.3-2 MeV) is 1.88 x 1016 n/sr.C.MeV, i.e. 28% of the total yield at 0 deg. We present studies on the influence of thyotepa, thyroxine, metallic ions (Cs1+ and AL3+) and D3 vitamin on fast neutron radiolysis in tumor DNA conclusions on the role of thyotepa (accelerator for tumor destruction) and of thyroxine, metallic ions and D3 vitamin (protectors). The potential for elemental analysis, especially for light elements (O, Na, Mg, Al, Si) on archaeological glass and ceramics objects is discussed. (authors)

  17. Assessment of environmental quality of Bucharest urban area by multisensor satellite data

    Science.gov (United States)

    Zoran, Maria A.; Zoran, Liviu Florin V.

    2004-10-01

    Urban environmental quality is an important part of efficient urban environment planning and management. A scientific management system for protection, conservation and restoration must be based on reliable information on bio-geophysical and geomorphologic, dynamics processes, and climatic change effects. Synergetic use of quasi-simultaneously acquired multi-sensor data may therefore allow for a better approach of change detection and environmental impact classification and assessment in urban area. As is difficult to quantify the environmental impacts of human and industrial activities in urban areas , often many different indicators can conflict with each other. The spatial and temporal distribution of land cover is a fundamental dataset for urban ecological research. Based on Landsat TM, ETM, SPOT and SAR data for Bucharest metropolitan area in Romania, it was performed a land cover classification based on spectral signatures of different terrain features used to separate surface units of urban and sub-urban area . A complete set of criteria to evaluate and examine the urban environmental quality, including the air pollution condition indicators, water pollution indicators, solid waste treated indicators, noise pollution indicators, urban green space have been widely used .

  18. THE THERMAL COMFORT IN THE SURFACE PUBLIC TRANSPORT FROM BUCHAREST DURING THE SUMMER PERIOD

    Directory of Open Access Journals (Sweden)

    D. MORCOTEŢ

    2012-03-01

    Full Text Available The thermal comfort during the summer period inside the surface public transport from Bucharest. The studies of human biometeorology are few at national level and the existing ones target especially housing or office buildings. This paper aims instead the surface public transport, represented by three categories of vehicles (bus, trolleybus and tram, from a city with over two million passengers per day with this transportation type. The study covers the warm season of the year, because this is the period with the most intense thermal discomfort, due to the excessive daytime heating of the air inside the transport vehicles. This paper is based on the expeditionary measurements undertaken inside seven vehicle models, selected depending on their share in the public transport fleet. A certain transport route was selected for each of those models, and the measurements were performed in certain days, depending on their meteorological characteristics. The study revealed that the construction features of the analyzed vehicles are decisive for the thermal discomfort level of passengers.

  19. Applicability and economic efficiency of earthquake retrofit measures on existing buildings in Bucharest, Romania

    Science.gov (United States)

    Bostenaru, M.

    2009-04-01

    The research discussed in this contribution contains two aspects: on one side the economic efficiency of seismic retrofit measures, and on the other their applicability. The research was limited to housing buildings. Bucharest, the capital of Romania, was the object of the research. Strong earthquakes affect Bucharest about three times in a century, the damaging earthquakes of the 20th century being in 1940 and 1977. Other strong earthquakes occurred in 1986 and 1990. Since it is a broad topic, first the building type was determined, which should serve further research. For this scope the building types of the 20th century, which are common in Bucharest, Romania, were investigated. For each building type reports have been written, which comprised the earthquake resilient features, the seismic defficiencies, the damage patterns and the retrofit measures. Each of these features was listed for elements of the building. A first result of the research was an integrated system in order to include latter aspects in the planning in the first steps. So already at the building survey attention has to be paid on how a building is subdivided in order to be able to determine the economic efficiency of the planned action. So were defined the `retrofit elements`. In a first step the characteristics were defined, through which these retrofit elements (for example column, wall part between two windows) can be recognised in the building survey. In a further one, which retrofit measures can be connected to these. Diagrams were built, in order to visualise these findings. For each retrofit element and the corresponding measure the costs were calculated. Also, these retrofit elements and the measures connected to them were modelled for the simulation with the structural software, so that the benefit of the measures could be determined. In the part which regarded the economic efficiency, benefits and costs of retrofit measures had to be compared, so the improvement in the rigidity

  20. Inelastic slow neutron scattering by strontium chloride

    International Nuclear Information System (INIS)

    The ability of certain compounds to conduct electricity through a mechanism involving the mobility of ions rather than electrons has attracted a great deal of experimental and theoretical attention. Some materials with fluoride structure show a pronounced specific heat anomaly well below their melting temperature. This anomaly is a consequence of lattice disorder and is associated with the fast-ion conduction. The purpose of this paper is to present the results of the experiments in which the inelastic slow neutrons scattering (E0 = 5.2 m eV) from polycrystalline Sr Cl2 was investigated. The measurements have been taken on a time-of-flight spectrometer at WWR-S Reactor in Bucharest. Information concerning the lattice dynamics are obtained from the phonon state density G(ω). The inelastic neutron scattering spectrum shows a good separation of the frequencies of the atomic vibrations. (author)

  1. Neutron activation analysis of essential and toxic elements in sludge from city water treatment

    International Nuclear Information System (INIS)

    Instrumental neutron activation analysis (INAA) method was used to determine the concentrations of 38 elements (Ag, Al, As, Au, Ba, Br, Ca, Ce, Cl, Co, Cr, Cs, Cu, Eu, Fe, Hf, Hg, K, La, Lu, Mn, Na, Ni, Rb, Sb, Sc, Se, Sm, Sr, Ta, Tb, Th, Ti, U, V, W, Yb, Zn) in three sludge samples resulting after city water treatment (WT-L, WT-M, WT-H). These samples were provided by the Institute of Radioecology and Applied Nuclear Techniques from Kosice (Slovakia), in the frame of an intercomparison exercise. Our laboratory data are presented, with respect to the intercomparison values, to emphasize the analytical performances obtained by INAA at WWR-S reactor of NIPNE in Bucharest. (author)

  2. The cultural route of present and lost landscapes in the centre of Bucharest - digital model

    Science.gov (United States)

    Bostenaru-Dan, Maria

    2015-04-01

    We are developing a digital model of the Magheru boulevard in central Bucharest. This N-S axis in the centre of the city is a unique encounter with interwar architecture. It is a protected area in the city, with buildings listed individually or as group of monuments, and also with protection at urban planning level. But at the same time the landscape does not facilitate the building of urban routes between monuments. A GIS model of the area exists, but does not yet take into account this heritage value of the buildings, being developed in a civil engineering environment. It is also one of the few partial 3D models of Bucharest. It allows datascapes of various buidling characteristics. At the same time a 3D model which equally covers all items in an area is ressources expensive. Hence, we propose, similarly to strategic planning to do a Kevin Lynch type selection. Landmarks will be identified as nodes of the routes, and the remaining area treated as zone. Ways connect the nodes and we paid special attention as we will see to their landscape. We developed a concept on how to further build from the idea of layers in GIS to include the issue of scale. As such, floor plans can build strategic points for the nodes of the route such as in Nolli or Sitte plans. Cooperation between GIS and GoogleEarth is envisaged, since GoogleEarth allows for detailing in SketchUp for the interior space. This way we developed an alternative digital model to the levels of detail of CityGML, the classical for 3D city models. The route itself is to be analysed with the method of Space Syntax. While this part of the research focused on the built heritage, on culture, we included also issues of landscape. First, the landscape of the boulevard has to be shaped as to build the route between these nodes of the route. Our concept includes the creation of pocket parks and of links between the pocket parks through vegetal and mineral elements to connect them. Existing urban spaces and empty plots are

  3. Linking geological Heritage Conservation to Education and Research at the University of Bucharest

    Science.gov (United States)

    Andrasanu, A.

    2012-04-01

    MSc curriculum or intensive courses in geoconservation to form professionals able to provide a holistic view of nature and to work for promotion of geoscience, raise public awareness, educate decision-makers (Andrasanu, 2005, Corte Bacci, 2008, Brihlla, 2009, Zouros and Mckeever, 2009) University of Bucharest developed research and educational projects (Erasmus, Leonardo da Vinci) both for geological heritage conservation in the frame of ProGEO and also in fostering geoparks development in Romania. The paper presents geoeducation as part of the geoconservation activities, and the role teaching staff and students are playing in curriculum design, research and educational activities, sustained or developed by University of Bucharest. Three examples were selected to be detailed: (i) a new MSc program Applied Geo-biology in natural and cultural heritage conservation; (ii) Geoconservation as a case study in the frame of the European Virtual Seminar in Sustainable Development (http://www.openuniversiteit.nl), and (iii) Geosciences as part of outdoor learning activities in the frame of the international project In and Out (http://www.viauc.com).

  4. GOVERNANCE ON THE INTERNET. MEASURING THE PERFORMANCES OF E-GOVERNANCE IN BUCHAREST MUNICIPALITIES

    Directory of Open Access Journals (Sweden)

    ANDREI ELVADEANU

    2011-04-01

    Full Text Available This paper analyzes the electronic governance and how it’s functioning in Romania. Being part of a larger institutional reform process, the electronic governance represents a new approach of the relation between Government and the citizen, with the purpose of increasing the participative dimension of the politic action, and as a way to provide more efficient services by the public agencies. E-governance uses information technologies (especially the Internet in the public sector, in order to improve the activity of bureaucratic institutions and encourage citizen participation. This paper analyzes the concept of electronic governance and with a focus on the obvious differences between the ideal model and the way in which these policies are actually implemented in Romania. The analysis was made for the 6 town-halls in Bucharest, but can offer a good sample of how egovernance is made in Romania. The instrument used for measurements is the comprehensive Rutgers egovernance performance index, covered in detail in the article. The areas taken into consideration were the public services offered by the institutions, the usage degree by the citizens and the civic participation dimension, understood as a bi-directional communication between the institutions and the citizen. The final part of the paper is dedicated to explaining the results, with recommendations for the Romanian public institutions. The research has its limits, but the results can draw attention over an institutional process that can represent a huge positive change in the way that governance is usually understood to be made in Romania and a very important improvement in the relation between state and society.

  5. Status and Perspectives for a Slow Positron Beam Facility at the HH--NIPNE Bucharest

    International Nuclear Information System (INIS)

    The development of a positron annihilation spectroscopy laboratory at the HH-NIPNE Bucharest-to be used for material studies and applications was started in the last 10 years. In the framework of a national research project extended over the last 3 years, was designed a low energy positron accelerator, as a high-vacuum dedicated beam line with two options: a 25 mCi 22NaCl source and in line with the NIPNE-cyclotron or a new intense compact cyclotron. The construction of the beam line was planned as a sequence of modules: source- moderator system; magnetical filter for fast positrons in order to select the positrons energies in the range 0.8-1 keV; a modular system for focusing, transport and acceleration of monoenergetic positrons in the energy range 0.8-50 keV and a CDBS analysis chamber. The moderator proposed--is tungsten as a foil of about 3 μm prepared at the Optoelectronics Institute were put into a thermal treatment vacuum chamber and bombarded with electrons from a 100 W electron gun After the treatment, they were tested for changes of elemental composition of the surface and structure at the Polytechnic University. The structure tests were performed on a DRON 3 M diffractometer, with a Co tube (λKα = 1.7903 A) - the angular regions studied were around 34 deg. (1 0 0) and 69 deg. (2 0 0). In the present time, the trajectories of the positron are going to be simulated with dedicated software (an ion and electron optics simulator). For the coincidence measurements (CDBS) set-up we used a home-made 22NaCl source, by separation without carrier from a metallic Mg target irradiated with 12 MeV protons and separated by columnar cation exchange. A home-made biparametric system for CDBS measurements will be reported, also.

  6. Status and Perspectives for a Slow Positron Beam Facility at the HH-NIPNE Bucharest

    Science.gov (United States)

    Straticiuc, Mihai; Craciun, Liviu Stefan; Constantinescu, Olimpiu; Ghita, Ionica Alina; Ionescu, Cristina; Racolta, Petru Mihai; Vasilescu, Angela; Braic, Viorel; Zoita, Catalin; Kiss, Adrian; Bojin, Dionezie

    2009-03-01

    The development of a positron annihilation spectroscopy laboratory at the HH-NIPNE Bucharest-to be used for material studies and applications was started in the last 10 years. In the framework of a national research project extended over the last 3 years, was designed a low energy positron accelerator, as a high-vacuum dedicated beam line with two options: a 25 mCi 22NaCl source and in line with the NIPNE-cyclotron or a new intense compact cyclotron. The construction of the beam line was planned as a sequence of modules: source- moderator system; magnetical filter for fast positrons in order to select the positrons energies in the range 0.8-1 keV; a modular system for focusing, transport and acceleration of monoenergetic positrons in the energy range 0.8-50 keV and a CDBS analysis chamber. The moderator proposed-is tungsten as a foil of about 3 μm prepared at the Optoelectronics Institute were put into a thermal treatment vacuum chamber and bombarded with electrons from a 100 W electron gun After the treatment, they were tested for changes of elemental composition of the surface and structure at the Polytechnic University. The structure tests were performed on a DRON 3 M diffractometer, with a Co tube (λKα = 1.7903 A)-the angular regions studied were around 34° (1 0 0) and 69° (2 0 0). In the present time, the trajectories of the positron are going to be simulated with dedicated software (an ion and electron optics simulator). For the coincidence measurements (CDBS) set-up we used a home-made 22NaCl source, by separation without carrier from a metallic Mg target irradiated with 12 MeV protons and separated by columnar cation exchange. A home- made biparametric system for CDBS measurements will be reported, also.

  7. Status and Perspectives for a Slow Positron Beam Facility at the HH—NIPNE Bucharest

    Science.gov (United States)

    Constantin, Florin; Craciun, Liviu Stefan; Constantinescu, Olimpiu; Ghita, Ionica Alina; Ionescu, Cristina; Racolta, Petru Mihai; Straticiuc, Mihai; Vasilescu, Angela; Braic, Viorel; Zoita, Catalin; Kiss, Adrian; Bojin, Dionezie

    2009-03-01

    The development of a positron annihilation spectroscopy laboratory at the HH-NIPNE Bucharest-to be used for material studies and applications was started in the last 10 years. In the framework of a national research project extended over the last 3 years, was designed a low energy positron accelerator, as a high-vacuum dedicated beam line with two options: a 25 mCi 22NaCl source and in line with the NIPNE-cyclotron or a new intense compact cyclotron. The construction of the beam line was planned as a sequence of modules: source- moderator system; magnetical filter for fast positrons in order to select the positrons energies in the range 0.8-1 keV; a modular system for focusing, transport and acceleration of monoenergetic positrons in the energy range 0.8-50 keV and a CDBS analysis chamber. The moderator proposed—is tungsten as a foil of about 3 μm prepared at the Optoelectronics Institute were put into a thermal treatment vacuum chamber and bombarded with electrons from a 100 W electron gun After the treatment, they were tested for changes of elemental composition of the surface and structure at the Polytechnic University. The structure tests were performed on a DRON 3 M diffractometer, with a Co tube (λKα = 1.7903 A)—the angular regions studied were around 34° (1 0 0) and 69° (2 0 0). In the present time, the trajectories of the positron are going to be simulated with dedicated software (an ion and electron optics simulator). For the coincidence measurements (CDBS) set-up we used a home-made 22NaCl source, by separation without carrier from a metallic Mg target irradiated with 12 MeV protons and separated by columnar cation exchange. A home- made biparametric system for CDBS measurements will be reported, also.

  8. Study of the radfioisotopic composition of rain in 2.05 1986 in Bucharest-Magurele area

    International Nuclear Information System (INIS)

    The paper presents the activities of radionuclides in the rain that fell in Bucharest-Magurele area on May 2nd, 1986. The artificial radionuclides measured were: Sr-89, Sr-90, Ru-103, Ru-106, Sb-125, I-131, (I+Te)-132, Cs-134, Cs-137, (Ba+La)-140, Ce-141, Ce-144, originating in the nuclear accident at Chernobyl. The activities of I-131 and Cs-137 were 28700 Bq/m2 and 3610 Bq/m2 respectively. (authors)

  9. SANS facility at the PITESTI 14MW TRIGA reactor

    International Nuclear Information System (INIS)

    At the present time, an important not yet fully exploited potentiality is represented by the SANS instruments existent at lower power reactors and reactors in developing countries even if they are, generally, endowed with a simpler equipment and are characterized by the lack of infrastructure to maintain and repair high technology accessories. The application of SANS at lower power reactors and in developing countries nevertheless is possible in well selected topics where only a restricted Q range is required, when scattering power is expected to be sufficiently high or when the sample size can be increased at the expense of resolution. The need for the installation of a new SANS facility at the Triga Reactor of the Institute of Nuclear Researches in Pitesti, Romania become actual especially after the shutting down of the VVRS Reactor from Bucharest

  10. Brief history of the reactor physics activities at ICN Pitesti

    International Nuclear Information System (INIS)

    The Institute was established 33 years ago, in April 1971. Several specialists from the Institute for Atomic Physics - Bucharest came at the new research entity and the reactor physics activities had a successful start. One can identify three distinct periods: 1971-1980, the Bucharest years, 1980-1996, solving critical problems years and 1977-present (2004), technical support years. The first period is usually seen as a training one. This is only partially true. Most of the physicists came from University in 1971 and 1972 years. A significant number of them were trained abroad, in France, Germany, Italy, USA, Canada etc., usually under IAEA Vienna fellowships. The work was really pleasant and the progress was exciting. Unfortunately, the main task (to design a thermal reactor and a fast reactor, both for research activities) was, probably, much too difficult from the technical point of view and, in addition, required an unrealistic economic effort. In the Fall of the 1976 year, most of the reactor physicists were removed from Bucharest to Pitesti. One year later, all the remaining specialists were concentrated in Pitesti. The dual core TRIGA reactors were commissioned in the last months of the 1979 year. The CYBER 720 mainframe computer was available in December 1980. Between 1980 and 1992 years, practically all the Romanian activities related to reactor physics were performed in Pitesti, Mioveni compound. The details related to critical problems will be presented in the paper. We mention here four of the problems that have a significant impact even today, namely: -Final dimensioning of the adjuster rods for the Cernavoda NPP, Unit 2. The rods were manufactured in USA and Canada, using the AECL design and the final dimensions have been specified by ICN Pitesti; -Use of the LEU fuel in TRIGA-SSR Reactor, instead of the original HEU fuel; -Design of the irradiation experiments in TRIGA cores, in order to provide the required conditions during the test, according to

  11. Quantitative assessment of the groundwater-sewer network interaction in Bucharest city (Romania)

    Science.gov (United States)

    Boukhemacha, M. A.; Diaconescu, A.; Bica, I.; Gogu, C. R.; Gaitanaru, D.

    2012-04-01

    Groundwater management in urban area must take account of every possible and relevant phenomena arising from the complex interaction between subsurface water, surface water, and urban infrastructure. In Bucharest, the need of the sewer system rehabilitation initiated a study of the interaction between groundwater and the sewer network. Recent conclusions show that the sewer network acts mainly like a drainage system for the groundwater. However, it could be easily proven that several sewer segments located mainly in the unsaturated zone contaminate the groundwater by leakage. The groundwater infiltration in the sewer conduits can cause the decrease of the groundwater level leading to structures instability problems as well as to the increase flow-rates of the sewer system. The last one affects seriously the wastewater treatment plants efficiency. The sewer network leakage cause groundwater pollution and locally could increase the groundwater level triggering buildings instability or other urban operational problems. The current study focuses on the consequences of sealing a part of the sewer system and so disturbing the existing groundwater behavior which may lead to serious consequences. In this framework, the analysis results of a groundwater flow model used to quantify the interaction between the groundwater and the sewer network are presented. The two-layers groundwater flow model simulating the Colentina and Mostistea overlaid sedimentary aquifers covers about 75 km2. Its conceptual model relies on a 3D geological model made by using 23 accurate geological cross-sections of the studied domain. The model set-up and its calibration are done using pumping tests data, groundwater hydraulic heads, and water levels of the sewer system. Infiltration rates into sewers are modeled by applying a modified form of Darcy's law that uses the notion of infiltration factor. This last encompasses the hydraulic conductivity of the clogging layer, the infiltration area and the

  12. Building competencies for New Gen IV Reactors

    International Nuclear Information System (INIS)

    The Advanced Lead Fast Reactor European Demonstrator - ALFRED is designed and sustained by several European countries. It is a 300 MWt (125 MWe) reactor, intended to be built in Romania, near the Pitesti site. Pure lead is used as primary coolant and it is foreseen to have a 40% thermal efficiency. Secondary cycle contains superheated water steam at around 450 Celsius degrees. Through ARCADIA cooperation, 26 partners from all over Europe joined their forces to provide the necessary research support for ALFRED. In Romania, several entities are providing nuclear courses but only the University Politechnica of Bucharest is offering a complete training program for nuclear industry but targeted courses for LFR technology need to be developed and implemented. Issues like physics of breeding, coolant analysis and behavior, targeted computer codes, core design and dynamics, safety still needs to be tackled

  13. Evolution of 137Cs and 90Sr content of the main foodstuff in Bucharest area after the Chernobyl accident

    International Nuclear Information System (INIS)

    Soon after the Chernobyl accident, the radioactive cloud, carrying the nuclides released into the atmosphere, reached Romania and, due to the rainy weather, an important fallout occurred over the Romanian territory. The most important contaminants for Romania were I131, Cs134, Cs137 and Sr90. As in many other countries, in the first days, I131 had the main contribution to the irradiation dose released to the population. After its decay, and the decay of other short-lived radionuclides, Cs137 and Sr90 remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. To assess the radioactive burden of foods, a long term, large scale survey was initiated at the National Institute of Hygiene and Public Health (INISP). These results were then used to assess the doses committed to cesium and strontium intake and the excedentary cancer risk for the population from Bucharest area

  14. CURRENT STUDY ON THE FUNDING SOURCES COVERAGE OF CURRENT ASSETS TO COMPANIES LISTED ON THE BUCHAREST STOCK EXCHANGE

    Directory of Open Access Journals (Sweden)

    Teodor HADA

    2014-06-01

    Full Text Available This paper presents issues about the coverage with financing sources of current assets for 64 companies listed on the Bucharest Stock Exchange. The aim of the study is to see how to calculate indicators specific to current assets and the general framework offered as whole analysis of the financing sources of current assets. The introduction of the paper presents the objective, the research methodology and the novelties brought by this study. Further on, this study shows the various views of the authors about the concept of "current assets", financing sources of current assets, the calculation of net working capital, setting the limits of the normal working capital and determining the speed of rotation. After that was done, based on the theory, a case study was performed, for companies covered in this study. Conclusions focused on determining the final data about what was detailed in the previous paragraphs.

  15. A new slit stabilization system for the beam energy at the Bucharest tandem Van de Graaff accelerator

    Science.gov (United States)

    Moşu, D. V.; Ghiţă, D. G.; Dobrescu, S.; Sava, T.; Mitu, I. O.; Călinescu, I. C.; Naghel, G.; Dumitru, G.; Căta-Danil, Gh.

    2012-11-01

    Recent work has been undertaken to renew the stabilization system for the beam energy at the Bucharest Tandem Accelerator. In the present paper the mechatronic design of the new system is presented and the running consistency of the new electronic circuits is shown. The experimental tests have shown that the new system has improved the quality of the accelerated beams in terms of stability and energy resolution, especially at lower accelerating voltages. As a result of the present development we show an improvement with 20% for the peak to peak medium value of the high voltage ripple on the terminal. This improvement also allowed to lower the minimum stable voltage on the terminal from 1.5 MV to 0.8 MV.

  16. Urban Vulnerability Assessment to Seismic Hazard through Spatial Multi-Criteria Analysis. Case Study: the Bucharest Municipality/Romania

    Science.gov (United States)

    Armas, Iuliana; Dumitrascu, Silvia; Bostenaru, Maria

    2010-05-01

    In the context of an explosive increase in value of the damage caused by natural disasters, an alarming challenge in the third millennium is the rapid growth of urban population in vulnerable areas. Cities are, by definition, very fragile socio-ecological systems with a high level of vulnerability when it comes to environmental changes and that are responsible for important transformations of the space, determining dysfunctions shown in the state of the natural variables (Parker and Mitchell, 1995, The OFDA/CRED International Disaster Database). A contributing factor is the demographic dynamic that affects urban areas. The aim of this study is to estimate the overall vulnerability of the urban area of Bucharest in the context of the seismic hazard, by using environmental, socio-economic, and physical measurable variables in the framework of a spatial multi-criteria analysis. For this approach the capital city of Romania was chosen based on its high vulnerability due to the explosive urban development and the advanced state of degradation of the buildings (most of the building stock being built between 1940 and 1977). Combining these attributes with the seismic hazard induced by the Vrancea source, Bucharest was ranked as the 10th capital city worldwide in the terms of seismic risk. Over 40 years of experience in the natural risk field shows that the only directly accessible way to reduce the natural risk is by reducing the vulnerability of the space (Adger et al., 2001, Turner et al., 2003; UN/ISDR, 2004, Dayton-Johnson, 2004, Kasperson et al., 2005; Birkmann, 2006 etc.). In effect, reducing the vulnerability of urban spaces would imply lower costs produced by natural disasters. By applying the SMCA method, the result reveals a circular pattern, signaling as hot spots the Bucharest historic centre (located on a river terrace and with aged building stock) and peripheral areas (isolated from the emergency centers and defined by precarious social and economic

  17. Methods to Assess the Site Effects Based on in situ Measurements in large urban Areas. Application in Bucharest City, Romania

    Science.gov (United States)

    Bala, A.; Aldea, A.; Ritter, J. R. R.; Hannich, D.

    2009-04-01

    In seismic microzonation we want to display the variation in seismic response of the subsurface and subsequently determine where the soil is being amplified to a level that may damage existing buildings. Although is not always adequate, frequently peak ground acceleration (PGA)is used to determine the maximum horizontal forces that can be expected. Considering the earthquake of 27.10.2004 (Mw = 6), the PGA map of the horizontal component EW shows variation in the PGA from 16 to 60 cm/s*s in the Bucharest area of 20 km diameter. Most of this variation is due to the package of the Quaternary sedimentary layers which amplify the original strong motion arrived from the earthquake. The largest amplification of the soil will occur at the lowest natural frequency or its fundamental frequency. In situ measurements of shear wave velocity in the soil and the soil thickness, provide a direct measure of the characteristic site period. But the sedimentary layers will also amplify the original frequency content of the earthquake signal arriving at the bedrock during a moderate or strong earthquake. Thus borehole recordings of acceleration during an earthquake is also an important issue. Extensively seismic noise measurements is a much accessible method and computed H/V spectral ratio can also provide a good indication on the fundamental frequency of the site. Within the NATO-funded Science for Peace Project 981882 "Site-effect analyses for the earthquake-endangered metropolis Bucharest, Romania" the drilling and the Vp and Vs (seismic longitudinal and shear-wave velocities) measurements in ten boreholes were done in the years 2006-2007 (Bala et al., 2007). Rock samples were taken from each borehole at different depths for laboratory tests to determine the geotechnical parameters of each sedimentary rock type at the sites. Thus a valuable data base is assembled which contains: Vp and Vs values for each sedimentary layer, density and geologic characteristics of each layer, which

  18. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  19. The Early Warning System(EWS) as First Stage to Generate and Develop Shake Map for Bucharest to Deep Vrancea Earthquakes

    Science.gov (United States)

    Marmureanu, G.; Ionescu, C.; Marmureanu, A.; Grecu, B.; Cioflan, C.

    2007-12-01

    EWS made by NIEP is the first European system for real-time early detection and warning of the seismic waves in case of strong deep earthquakes. EWS uses the time interval (28-32 seconds) between the moment when earthquake is detected by the borehole and surface local accelerometers network installed in the epicenter area (Vrancea) and the arrival time of the seismic waves in the protected area, to deliver timely integrated information in order to enable actions to be taken before a main destructive shaking takes place. Early warning system is viewed as part of an real-time information system that provide rapid information, about an earthquake impeding hazard, to the public and disaster relief organizations before (early warning) and after a strong earthquake (shake map).This product is fitting in with other new product on way of National Institute for Earth Physics, that is, the shake map which is a representation of ground shaking produced by an event and it will be generated automatically following large Vrancea earthquakes. Bucharest City is located in the central part of the Moesian platform (age: Precambrian and Paleozoic) in the Romanian Plain, at about 140 km far from Vrancea area. Above a Cretaceous and a Miocene deposit (with the bottom at roundly 1,400 m of depth), a Pliocene shallow water deposit (~ 700m thick) was settled. The surface geology consists mainly of Quaternary alluvial deposits. Later loess covered these deposits and the two rivers crossing the city (Dambovita and Colentina) carved the present landscape. During the last century Bucharest suffered heavy damage and casualties due to 1940 (Mw = 7.7) and 1977 (Mw = 7.4) Vrancea earthquakes. For example, 32 high tall buildings collapsed and more then 1500 people died during the 1977 event. The innovation with comparable or related systems worldwide is that NIEP will use the EWS to generate a virtual shake map for Bucharest (140 km away of epicentre) immediately after the magnitude is estimated

  20. THE SPATIAL DISTRIBUTION OF THE SOURCES OF ENVIRONMENTAL DEGRADATION IN DISTRICT 4, CITY OF BUCHAREST, IN RELATION WITH THE URBAN ENVIRONMENT

    OpenAIRE

    Cornelia Dincă

    2008-01-01

    The pollution sources produce noxious emissions, harmful to the environment and the public health. District 4 of the city of Bucharest is considered to be very polluted due to factors such as industry, heavy traffic, building sites,thermoelectric power plants, sources of diffusive combustion, and also the reduction of green spaces. These sources produce both noxious emissions and noise pollution. The air contamination, the water and soil pollution contribute to the deterioration of public hea...

  1. Young generation in Romanian nuclear system - Romanian nuclear organizations implication in nuclear knowledge management at University 'Politehnica' of Bucharest - Results and expectations

    International Nuclear Information System (INIS)

    The knowledge management should be assumed by the major players within the nuclear community: government, industry and university. Starting from these problems this article gives an overview about Romanian nuclear knowledge management and the Young Generation implications. In Romania there are many government and non-government nuclear institutions such: CNCAN (Romanian Regulatory Body), ROMATOM (Romanian Atomic Forum), AREN (Romanian 'Nuclear Energy' Association), and companies: SNN ('Nuclearelectrica' SA National Company), CITON (Centre of Technology and Engineering for Nuclear Projects), SCN (Institute for Nuclear Research), ROMAG - PROD (Romanian Heavy Water Plant). All these institutes and companies are sustaining the national nuclear program and promoting the new technologies in the nuclear industry according with CNCAN and ROMATOM regulations. University 'POLITEHNICA' of Bucharest - Power Engineering Faculty - through Nuclear Power Plant Department is the promoter of nuclear knowledge management. It is implied in assuring and maintaining a high-quality training for young staff. Young Generation is implicated in nuclear knowledge management through University 'Politehnica' of Bucharest - Power Engineering Faculty - Nuclear Power Plant Department and AREN (Romanian 'Nuclear Energy' Association). Young Generation Department has special educational programs for attracting and supporting students. It provides adequate information and interacts with potential students. Moreover the article gives results about Romanian nuclear engineers since 1970 till now. An analysis of these data is done. Also it is discussed how University 'Politehnica' of Bucharest, the Romanian Government and the Industry work together to co-ordinate more effectively their efforts to encourage the young generation. (author)

  2. Young generation in Romanian nuclear system - Romanian nuclear organizations implication in nuclear knowledge management at University 'Politehnica' of Bucharest: Results and expectations

    International Nuclear Information System (INIS)

    Full text: The knowledge management should be assumed by the major players within the nuclear community: government, industry and university. Starting from these problems this article gives an overview about Romanian nuclear knowledge management and the Young Generation implications. In Romania there are many government and non-government nuclear institutions such: CNCAN (Romanian Regulatory Body), ROMATOM (Romanian Atomic Forum), AREN (Romanian 'Nuclear Energy' Association), and companies: SNN ('Nuclearelectrica' SA National Company), CITON (Centre of Technology and Engineering for Nuclear Projects), SCN (Institute for Nuclear Research ), ROMAG - PROD ( Romanian Heavy Water Plant). All these institutes and companies are sustaining the national nuclear program and promoting the new technologies in the nuclear industry according with CNCAN and ROMATOM regulations. University 'POLITEHNICA' of Bucharest - Power Engineering Faculty - through Nuclear Power Plant Department is the promoter of nuclear knowledge management. It is implied in assuring and maintaining a high - quality training for young staff. Young Generation is implicated in nuclear knowledge management through University 'Politehnica' of Bucharest - Power Engineering Faculty - Nuclear Power Plant Department and AREN (Romanian 'Nuclear Energy' Association). Young Generation Department has special educational programs for attracting and supporting students. It provides adequate information and interacts with potential students. Moreover the article gives results about Romanian nuclear engineers since 1970 till now. An analysis of these data is done. Also it is discussed how University 'Politehnica' of Bucharest, the Romanian Government and the Industry work together to co-ordinate more effectively their efforts to encourage the young generation. (author)

  3. The Metropolitan Area of the Municipality of Bucharest. Present-Day Features Relating to Some Environmental Issues in an International Context

    Directory of Open Access Journals (Sweden)

    INES GRIGORESCU

    2005-01-01

    Full Text Available The development of metropolitan areas represents the main characteristic of today’s urban evolution trends. The first initiatives to delimitate and define metropolitan areas have been in the United States since 1910. In Europe, this concept was adopted at the beginning of the1990s when the United States had already had 250 metropolitan areas. Romania adopted the concept of metropolitan area in the late 1990s, namely in 1997 when a study on the Directions, Ways, and Intensities of Development in the Municipality of Bucharest and its Metropolitan Zone. Environmental protection politics appeared. This made public a point of view about the Bucharest metropolitan area, which was legally defined by Law no. 351 of July 6th 2001 regarding the National Territory Management Plan, Section IV – Settlements. But many other limits of this area were also taken into account. The uncontrolled evolution of the Bucharest Metropolitan Area as well as of many other European capital cities can be stopped or stabilized by developing green belts or green areas.

  4. The Black Sea one decade after the Bucharest Convention an overview of the international activities in the Black Sea region

    International Nuclear Information System (INIS)

    The catastrophic degradation of the Black Sea in a period of four decade has been the major concern of the Black Sea countries and international communities since Bucharest Convention signed in 1992. The Black Sea Region has became a challenging international arena for political scientific and socio-economic activities. Intensive international programmes and establishment of governmental and Non Governmental Organizational structures of the 1990s including Black Sea Economic Cooperation (BSEC), Black Sea Environmental Programme(BSEP), Environmental Programme for the Danube River Basin, Marine Environmental Assessment of the Black Sea Region Technical Cooperation Programme by the IAEA and establishment of the Black Sea Commission Permanent Secretariat are some of the major international efforts of the past decade that emphasizes the multi-nationality and large dimension of the Black Sea environmental management issues. The environmental degradation of the Black Sea is briefly reviewed based on the BSEP reports and data available for land based pollution sources. The environmental risk of marine vessel accidents are indicated and environmental safety concern is emphasized under the current conditions of intense energy transportation projects in the Black Sea and Caspian regions. The international policy actions, co-operation issues and scientific programmes of the past decade are overviewed with emphasis on the international achievements. Concluding remarks include the vital importance of continuation of the international commitments and sharing the political, scientific and socio-economic responsibility on the transboundary environmental pollution, rehabilitation and the safety issues of the Black Sea

  5. THE IMPLICATIONS OF THE IMPROVEMENT OF MARKETING ACTIVITY ON THE PERFORMANCE OF CENTRAL UNIVERSITY LIBRARY IN BUCHAREST

    Directory of Open Access Journals (Sweden)

    Ruxandra Irina POPESCU

    2010-01-01

    Full Text Available After a prolonged and complex process of reconstruction, extension and modernization, Central University Library "Carol I" in Bucharest has re-opened to public access in November 2001, bringing a new concept on what library services should mean. Under these auspicious circumstances, the library's offer has widened, the quality of services offered has improved, gradually displaying an interest in developing a closer relationship with its customers. The necessity of being more oriented to the marketing tools and techniques has become more apparent. Therefore, the top managers of the Central University Library have included in their three general development strategies produced so far, specific objectives, such as: an increase of the volume of paid serviced provided, promoting the services and work elaborated by its specialists through leaflets, presentations, albums, folders with press extracts. Beyond these actions with positive effects, the efforts of Central University Library for strengthening its position on the market of the providers of information services are diminished by the various malfunctions that characterize the marketing activity of this institution. Therefore, this work intends to contribute to the improvement of the marketing activity of the library by coming up with some solutions that could remove or at least diminish these weak points.

  6. Social vulnerability assessment using spatial multi-criteria analysis (SEVI model) and the Social Vulnerability Index (SoVI model) - a case study for Bucharest, Romania

    Science.gov (United States)

    Armaş, I.; Gavriş, A.

    2013-06-01

    In recent decades, the development of vulnerability frameworks has enlarged the research in the natural hazards field. Despite progress in developing the vulnerability studies, there is more to investigate regarding the quantitative approach and clarification of the conceptual explanation of the social component. At the same time, some disaster-prone areas register limited attention. Among these, Romania's capital city, Bucharest, is the most earthquake-prone capital in Europe and the tenth in the world. The location is used to assess two multi-criteria methods for aggregating complex indicators: the social vulnerability index (SoVI model) and the spatial multi-criteria social vulnerability index (SEVI model). Using the data of the 2002 census we reduce the indicators through a factor analytical approach to create the indices and examine if they bear any resemblance to the known vulnerability of Bucharest city through an exploratory spatial data analysis (ESDA). This is a critical issue that may provide better understanding of the social vulnerability in the city and appropriate information for authorities and stakeholders to consider in their decision making. The study emphasizes that social vulnerability is an urban process that increased in a post-communist Bucharest, raising the concern that the population at risk lacks the capacity to cope with disasters. The assessment of the indices indicates a significant and similar clustering pattern of the census administrative units, with an overlap between the clustering areas affected by high social vulnerability. Our proposed SEVI model suggests adjustment sensitivity, useful in the expert-opinion accuracy.

  7. ENVIRONMENTAL LEVELS AND DISTRIBUTION OF CARBON MONOXIDE IN BUCHAREST URBAN AREA CASE STUDY: 1. 07. 2006 – 31.03.2007

    Directory of Open Access Journals (Sweden)

    POPESCU NICOLAE CRISTIAN

    2013-03-01

    Full Text Available Ambient concentrations of carbon monoxide in the vicinity of or inside urban and industrial areas can substantially exceed environmental background levels and can be detrimental to human health and welfare. In this period of analysis (July 2006 – March 2007, the maximum allowable concentration (MAC was exceeded especially at Mihai Bravu and Cercul Militar. The accompanying diagrams showing the time evolution and charts revealing the spatial distribution of CO ambient air concentrations (based on GIS techniques can be useful instruments in identifying the potential risk areas, like the important streets in the center of Bucharest.

  8. Urban heritage value and seismic vulnerability mapping: challenges for engineering and architectural assessments. Case study of a protected area in Bucharest, Romania

    OpenAIRE

    Emil-Sever GEORGESCU; Gociman, Cristina Olga; Iolanda-Gabriela CRAIFALEANU; Tiberiu FLORESCU; Cristian MOSCU; Mihaela Stela GEORGESCU; Claudiu-Sorin DRAGOMIR

    2015-01-01

    The paper evaluates the urban heritage situation at almost four decades after the Bucharest, March 4, 1977 earthquake disaster, followed by a razing of the present Civic Center area and a large-scale remodeling project. The first results of the URBASRISK Project (2012) are presented as a contribution to a new multi-hazard paradigm to cope with European urban scale threats, especially in heritage areas, with a case study of a historic zone now designated as protected area. The cultural and uti...

  9. ASPECTS CONCERNING THE DETERMINATION OF BANKRUPTCY RISK BY SOLVENCY AND LIQUIDITY RATIOS IN THE COMPANIES LISTED ON THE BUCHAREST STOCK EXCHANGE

    Directory of Open Access Journals (Sweden)

    Teodor Hada

    2014-07-01

    Full Text Available This paper presents issues related to determining the bankruptcy risk for 64 companies listed on the Bucharest Stock Exchange.The purpose of this paper is to determine the percentage of companies falling within the normal range. In the introduction, we set the goal, the research methodology, and the novelty value of this work. Hereinafter, we presented different views of risk concepts, bankruptcy, solvency and liquidity. After that, based on theoretical presentations, a case study was conducted to determine the solvency and liquidity ratios. In the end, on the basis of the above considerations, the conclusions were established and some proposals were listed.

  10. THUNDERSTORMS-RISK FACTORS IN AVIATION. CASE STUDY: AREA OF RESPONSABILITY OF THE BUCHAREST-OTOPENI AERODROME ON 30.06.2009

    Directory of Open Access Journals (Sweden)

    C. L. ŞCHIOPU

    2015-10-01

    Full Text Available Thunderstorms are always dangerous weather phenomena for flight safety and, irrespective of their nature, they have a negative impact on all aviation activities. Thunderstorm clouds can generate severe and rapid changes of various meteorological elements (visibility, cloudiness and cloud lower base, wind, sometimes to such a great extent that landing may become impossible. Thunderstorms are serious weather hazards in aviation and may produce great damage and even casualties. One such unfortunate aviation event took place in the vicinity of the Bucharest-Otopeni Aerodrome, on 30.06.2009, when a military aircraft, which was operating a training flight in the responsibility area of the Bucharest - Otopeni military aerodrome, was struck by lightning at local hour 18:20. The present study actually makes an inventory of the extremely hazardous flying conditions, by thoroughly analyzing the relevant weather reports and data, as well as visual and synoptic messages from that very day. All these materials showed that the airdrome of destination was under the influence of an anti-cyclonic ridge, which accounted for the very poor meteorological conditions. On such severe weather, although the crew members tried to avoid the Cumulonimbus clouds in which a severe thunderstorm was developing, the flight was put in danger since the aircraft was struck by lightning, which simply blurred out the radar system and, therefore, landmarks orientation became almost impossible, thus creating false perceptions to the pilots trying hard to stabilize the plane.

  11. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  12. An integrated strategy for modelling and simulating the transitory regimes in Nuclear Power Plants. Proactive educational and training oriented approach at the University 'Politehnica' of Bucharest

    International Nuclear Information System (INIS)

    This paper is a brief presentation of the preoccupation of the thermohydraulics modelling and simulating group acting at the Power Plants Department of the Faculty of Power Engineering in Bucharest aiming at creating an integrated software library to study the NPP components in abnormal and transitory regimes. The studies accomplished developed mathematical models which can be solved by using advanced codes (ACSR, MMS, MATLAB) and can be integrated in an evolving strategy for simulation. The basic elements of this strategy are: modular modelling, anticipatory approach of the evolution of the analysed systems and adaptive dynamic control. The global goal of developed simulations is an efficient identification and control of the transitory regimes having an impact on the safety performances of the plant. (author). 2 tabs. 3 figs., 12 refs

  13. At the Meeting Point of the Internet and School. Case Study for the Use of the Internet by High School Students in Bucharest

    Directory of Open Access Journals (Sweden)

    ANCA VELICU

    2008-03-01

    Full Text Available Starting from the idea that there is a gap between the possibilities of information offered by the new information and communication technologies, and especially the internet, and the concrete use thereof for information purposes, and especially for school-related information, we have analyzed the meeting point of the internet and school from the point of view of the complementarity or overlapping of the two, of the transformations they undergo but also of the transformations each of the two information institutions determines. The concrete field for the study of these potentially public and philosophical (gnoseology, epistemology, etc. issues was the use of the internet by the high school students in Bucharest.

  14. Use of combined scaling of real seismic records to obtain code-compliant sets of accelerograms: application for the city of Bucharest

    Directory of Open Access Journals (Sweden)

    Iolanda-Gabriela CRAIFALEANU

    2012-12-01

    Full Text Available A recently proposed method for scaling real accelerograms to obtain sets of code-compliant records is assessed. The method, which uses combined time and amplitude scaling, corroborated with an imposed value of an instrumental, Arias type intensity, allows the generation of sets of accelerograms for which the values of the mean response spectrum for a given period range are not less than 90% of the elastic response spectrum specified by the code. The method, which is compliant with both for the Romanian seismic code, P100-1/2006, and Eurocode 8, was described in previous papers. Based on dynamic analyses of single-degree-of freedom (SDOF and of multi degree-of-freedom (MDOF systems, a detailed application and assessment of the method is performed, for the case of the long corner period design spectrum in Bucharest. Conclusions are drawn on the advantages of the method, as well as on its potential improvement in the future.

  15. Use of combined scaling of real seismic records to obtain code-compliant sets of accelerograms: application for the city of Bucharest

    CERN Document Server

    Craifaleanu, Iolanda-Gabriela

    2013-01-01

    A recently proposed method for scaling real accelerograms to obtain sets of code-compliant records is assessed. The method, which uses combined time and amplitude scaling, corroborated with an imposed value of an instrumental, Arias type intensity, allows the generation of sets of accelerograms for which the values of the mean response spectrum for a given period range are not less than 90% of the elastic response spectrum specified by the code. The method, which is compliant with both for the Romanian seismic code, P100-1/2006, and Eurocode 8, was described in previous papers. Based on dynamic analyses of single-degree-of freedom (SDOF) and of multi degree-of-freedom (MDOF) systems, a detailed application and assessment of the method is performed, for the case of the long corner period design spectrum in Bucharest. Conclusions are drawn on the advantages of the method, as well as on its potential improvement in the future.

  16. An innovative view to the seismic hazard from strong Vrancea intermediate-depth earthquakes: the case studies of Bucharest (Romania) and Russe (Bulgaria)

    International Nuclear Information System (INIS)

    An advanced procedure for ground motion modelling, capable of synthesizing the seismic ground motion from basic understanding of fault mechanism and seismic wave propagation, is applied to compute seismic signals at Bucharest (Romania) and Russe, NE Bulgaria, due to the seismic hazard from intermediate-depth Vrancea earthquakes. The theoretically obtained signals are successfully compared with the available observations. For both case studies site response estimates along selected geological cross sections are provided for three recent, strong and intermediate-depth, Vrancea earthquakes: August 30, 1986 and May 30 and 31, 1990. The applied ground motion modelling technique has proved that it is possible to investigate the local effects, taking into account both the seismic source and the propagation path effects. The computation of realistic seismic input, utilising the huge amount of geological, geophysical and geotechnical data, already available, goes well beyond the conventional deterministic approach and gives an economically valid scientific tool for seismic microzonation. (author)

  17. THE SPATIAL DISTRIBUTION OF THE SOURCES OF ENVIRONMENTAL DEGRADATION IN DISTRICT 4, CITY OF BUCHAREST, IN RELATION WITH THE URBAN ENVIRONMENT

    Directory of Open Access Journals (Sweden)

    Cornelia Dincă

    2008-10-01

    Full Text Available The pollution sources produce noxious emissions, harmful to the environment and the public health. District 4 of the city of Bucharest is considered to be very polluted due to factors such as industry, heavy traffic, building sites,thermoelectric power plants, sources of diffusive combustion, and also the reduction of green spaces. These sources produce both noxious emissions and noise pollution. The air contamination, the water and soil pollution contribute to the deterioration of public health. Keeping a record of all the pollution sources, being aware of all their characteristics and the emissions they produce, as well as keeping them under strict control can be considered the necessary premises for maintaining a satisfying quality of the environment.

  18. NATIONAL COUNCIL FOR COMBATING DISCRIMINATION – COURT OF JUSTICE OF EUROPEAN UNION – BUCHAREST COURT OF APPEAL. CAUSE C-81/12

    Directory of Open Access Journals (Sweden)

    Cristian JURA

    2014-05-01

    Full Text Available The scope of this investigation consists in closing the jurisdictional circle initiated in 2010 and analysing the national and European procedural, jurisdictional-administrative issues, in case of notifying some institutions related to certain discriminatory assertions. The investigation relies on assertions made during a radio show. On 12 October 2011 the Bucharest Court of Appeal ruled the notification of the Court of Justice of European Union related to preliminary questions formulated and ordered the suspension of the case until the settlement of the procedure. In 2013, the Bucharest Court of Appeal, although initially accepting the preliminary application of ACCEPT, submitting the case to the Court of Justice of European Union in order to determine the manner of interpretation of communitarian legislation related to the claims of plaintiff, eventually all arguments of CNCD have been accepted that is the warning is an effective, reasonable, dissuasive and (contextual proportional sanction, and such declaration cannot be understood as a discrimination in the labour field. De facto, the assertions of CNCD were in full agreement with the resolution of the Court of Justice of European Union, that is the communitarian legislation does not exclude the application of some sanctions without pecuniary character, such as the sanction with warning, since this kind of sanction does not have only a symbolic character, being a contraventional legal sanction, mainly when associated a relevant degree of advertising (such in the case, and the addressee is addressed, with arguments, directly and expressly the recommendation of meeting the non-discrimination principle, under the implicit effect of a more drastic sanction in case of relapse (discrimination in the same field.

  19. Ground level ozone (O3) associated with radon (222Rn) and particulate matter (PM) concentrations in Bucharest metropolitan area and adverse health effects

    International Nuclear Information System (INIS)

    The aim of this paper is to contribute with new information in the application of ground based radon (222Rn) observations to atmospheric research, namely its relation with air pollution due to ground-level ozone (O3) and particle matter in two size fractions (PM10 and PM2.5) for Bucharest metropolitan area in Romania. During January 1-December 31, 2011, ground levels of radon, ozone and particulate matter (PM) have been continuously monitored in synergy with the main meteorological parameters (air temperature, humidity and pressure), and daily global air quality indices. A systematic analysis of surface ozone observations of ground level radon, ozone and PM is presented. Observational results indicate the following yearly daily mean ground level concentrations: 40.26 ± 7.54 Bq/m3 for radon, 90.51 μg/m3 for ozone, 35.96 μg/m3 for PM2.5, and 40.91 μg/m3 for PM10. The assessment of the results showed the influence of local and meteorological conditions on the daily mean radon, ozone and PM concentrations. However, in densely populated metropolitan area of Bucharest the mean daily values of ozone, PM2.5, PM10, and attached 222Rn are sometimes higher than European Community limit values leading to serious public concern during the last years. Due to the high risk of increased levels of O3, PM2.5, PM10, and attached 222Rn on human health respiratory function (especially for children and older persons), and urban green, the results are very useful for atmospheric, radiological protection, epidemiological and environmental studies. (author)

  20. Reactor Physics

    International Nuclear Information System (INIS)

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

  1. Reactor Physics

    International Nuclear Information System (INIS)

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

  2. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

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

  3. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  4. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  5. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  6. Research reactors

    International Nuclear Information System (INIS)

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  7. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  8. Research reactors

    International Nuclear Information System (INIS)

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world's research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted

  9. Reactor container

    International Nuclear Information System (INIS)

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  10. Tradition and prospects in nuclear physics

    International Nuclear Information System (INIS)

    In my talk concerning the commemoration of Professor Horia Hulubei, I would like to recall first of all, that at the beginning of the thirties, being a young visiting scientist in France, Horia Hulubei was among the first pioneers of transmutation reactions by using accelerated beams. Afterwards, I would like to recall, that another link of Horia Hulubei's activities with the Nuclear Physics in the thirties, is his effort directed to the search for transuranium elements in nature. Further I will remind the direct involvement of Professor Horia Hulubei as a chief of school in the Nuclear Physics research, that were initiated in Romania in the late fifties, after the installing of the WWR-S Reactor and of the Cyclotron in Bucharest. Finally, I would like to add some considerations related to present trends in Nuclear Physics at the international level. The paper contains the following sections: 1 Introduction; 2. Horia Hulubei - A pioneer in transmutation reactions with accelerated beams at the beginning of the thirties; 3. Horia Hulubei's researches concerning the identification of transuranic elements in nature; 4. Horia Hulubei - A leader of the Nuclear Physics School at the Institute of Atomic Physics in Romania; 5. Prospects of Nuclear Physics research; 6. Some recent results in the fusion induced by halo nuclei

  11. Effective doses committed in Bucharest area due to Cs-137 and Sr-90 intake 9 years after the Chernobyl accident

    International Nuclear Information System (INIS)

    On the 26th of April, 1986, a major accident occurred at the fourth reactor of the Chernobyl nuclear power plant, in Ukraine. The meteorological conditions lead to important fallout over our country. The most important radionuclides carried by the radioactive plume over Romania were I131, Cs134, Cs131 and Sr90. After the decay of I131, and of the other short-lived radionuclides, Cs137 and Sr90 remained the most important contaminants on the Romanian territory. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. Therefore, we have measured Cs137 and Sr90 content in dietary intake for a group of adult subjects. The data for dietary intake were used to determine the effective doses committed annually, with the dose factors recommended by ICRP 67. (author)

  12. Implementation of Eugene Wigner Training Course at University 'Politehnica' of Bucharest Power Engineering Faculty Nuclear Power Plant Department

    International Nuclear Information System (INIS)

    Full text: 'Eugene Wigner Course' Training Course for Reactor Physics Experiments has been supported by the 5th Framework Programme of the European Commission, and it has been integrated in the ENEN (European Nuclear Engineering Network) program. This project has been prepared for the future European Nuclear Education schemes and degrees. Starting from a general presentation of the course this paper presents my opinion as a former student about the course impact. Presented is my opinion about the following: The content of theoretical courses; The usefulness of the textbook; The content of the practical experiments; The usefulness of the textbook for the practical experiments, and evaluations. Moreover, parts of this course were implemented to my seminars. Results and also expectations and conclusions about the usefulness of the course are presented. (author)

  13. PCR coupled with mass-spectrometry for detection of Clostridium difficile virulence markers during the emergence of ribotype 027 in Bucharest area

    Directory of Open Access Journals (Sweden)

    Florea Dragos

    2015-12-01

    Full Text Available In recent years Clostridium difficile infection (CDI has represented a serious public health issue, mainly due to the global spread of the hypervirulent strain NAP1/027/BI. The purpose of the present study was to evaluate the utility of a PCR coupled with electrospray ionization mass spectrometry (ESI-MS commercial assay for the detection of C. difficile virulence markers. Non-duplicative C. difficile isolates from patients with CDI diagnosed in a tertiary level hospital from Bucharest were tested for toxin A, toxin B, binary toxin genes and deletion in tcdC gene using PCR/capillary gel electrophoresis and PCR/ESI-MS. The study analysed 45 non-duplicative isolates, 33 strains (73.3% belonging to ribotype 027. The concordance between PCR/capillary gel electrophoresis and PCR/ESI-MS was 100% for toxin A gene, 97.8% for toxin B gene, 91.1% for binary toxin subunit A gene and 95.6% for binary toxin subunit B gene. The general concordance for the complete panel of markers was 88.9% but was 100% for ribotype 027 isolates. PCR/ESI-MS might be a valid method for the detection of C. difficile virulence markers, including binary toxin.

  14. Estimate of the internal doses received by the population of Bucharest due to 137 Cs and 90 Sr intake in the first five years after the Chernobyl accident

    International Nuclear Information System (INIS)

    The evolution of the 137 Cs and 90 Sr daily intake between April 1986 and March 1991 as well as the internal doses resulting from ingestion of contaminated food is presented for a group of adults living in Bucharest. The results indicate that the effective doses due to 137 Cs and 90 Sr dietary intake had the highest values in the first year after the Chernobyl accident, namely, 796 μSv as a result of 137 Cs dietary intake and 23 μSv as a result of the 90 Sr dietary intake. The effective doses committed annually due to the Caesium-137 dietary intake decreased very fast from 796 μSv committed in the first year after the accident to 7.3 μSv committed in the fifth year after the accident. Although the effective dose committed in the first year after the accident due to the Strontium-90 dietary intake was much smaller than the dose due to the Caesium-137 (23 μSv), the decrease was slower so that the effective dose committed in the fifth year after the accident due to the Strontium-90 dietary intake was 7.5 μSv. (authors)

  15. Urban heritage value and seismic vulnerability mapping: challenges for engineering and architectural assessments. Case study of a protected area in Bucharest, Romania

    Directory of Open Access Journals (Sweden)

    Emil-Sever GEORGESCU

    2015-07-01

    Full Text Available The paper evaluates the urban heritage situation at almost four decades after the Bucharest, March 4, 1977 earthquake disaster, followed by a razing of the present Civic Center area and a large-scale remodeling project. The first results of the URBASRISK Project (2012 are presented as a contribution to a new multi-hazard paradigm to cope with European urban scale threats, especially in heritage areas, with a case study of a historic zone now designated as protected area. The cultural and utility value was identified and graded on specific scales for further analysis and mapping. For this phase of study some data of 1977 were adjusted to express the vulnerability by the Mean Damage Degree, GA, with a possibility to make corrections after visual inspection. The URBASRISKdb geodatabase was created for storing the attributes of the buildings. The basic source, i.e. the ESRI World Street Map layer, was verified against satellite, aerial and street views freely available online from various providers. The final version of the map was obtained by also considering information obtained by field visits.

  16. STRATEGIC OPTIONS IN THE CONSTRUCTION OF THE BUCHAREST BRAND THROUGH THE APPLICATION ANALYSIS OF THE MEASURING INSTRUMENTS FOR THE URBAN BRANDS

    Directory of Open Access Journals (Sweden)

    RUXANDRA IRINA POPESCU

    2010-01-01

    Full Text Available The reality demonstrates that, in the present context, the competition between the cities is harsh, amplified by the economic and politic effects of the globalization. Thecities are fighting to attract investments, influence, businesses, tourists, residents. One of the challenges of the urban management in its efforts to grow the performance is linked around the construction of the urban brand as a solution in the process of the cities’ development. This construction implies the validity, credibility, simplicity, attractiveness and distinctiveness of the city’s image. The answer of the researchers to the need of a critical effective instrument in this area was the creation of the Urban Brand Index. Through these measuring instruments, the actors implied in the administration of the cities can easily understand the perception of the visitors, investors, costumers and future residents upon the image of the city, to identify and apply some pro-active measures to stimulate and improvement of the existing opportunities that have as main result the development of the city. In this study are presented three of these instruments - The City Brands Index, The European Barometer of City Brands and The Global Cities Index - and the way in which these can contribute to the actions for constructing a powerful urban brand of Bucharest, is analyzed.

  17. Normalization of EEG activity among previously institutionalized children placed into foster care: A 12-year follow-up of the Bucharest Early Intervention Project.

    Science.gov (United States)

    Vanderwert, Ross E; Zeanah, Charles H; Fox, Nathan A; Nelson, Charles A

    2016-02-01

    Extreme social and cognitive deprivation as a result of institutional care has profound effects on developmental outcomes across multiple domains for many abandoned or orphaned children. The Bucharest Early Intervention Project (BEIP) examines the outcomes for children originally placed in institutions who were assessed comprehensively and then randomized to foster care (FCG) or care as usual (CAUG) and followed longitudinally. Here we report on the brain electrical activity (electroencephalogram: EEG) of 12-year-old children enrolled in the BEIP. Previous reports suggested improvement in resting EEG activity for the group of children placed in the foster care intervention, particularly those placed before 24 months of age compared to children who were randomized to CAUG or those placed into families after this age. At 12 years, differences between those in the FCG and those in the CAUG persist in the alpha band (8-13 Hz), but not in higher frequency bands (i.e. in the beta band; 15-30 Hz), except in those children placed into the FCG who remained in high quality care environments over the course of the study. These findings highlight the importance of maintaining a stable high quality caregiving environment, particularly for children exposed to early psychosocial deprivation, for promoting healthy brain development. PMID:26724564

  18. Normalization of EEG activity among previously institutionalized children placed into foster care: A 12-year follow-up of the Bucharest Early Intervention Project

    Directory of Open Access Journals (Sweden)

    Ross E. Vanderwert

    2016-02-01

    Full Text Available Extreme social and cognitive deprivation as a result of institutional care has profound effects on developmental outcomes across multiple domains for many abandoned or orphaned children. The Bucharest Early Intervention Project (BEIP examines the outcomes for children originally placed in institutions who were assessed comprehensively and then randomized to foster care (FCG or care as usual (CAUG and followed longitudinally. Here we report on the brain electrical activity (electroencephalogram: EEG of 12-year-old children enrolled in the BEIP. Previous reports suggested improvement in resting EEG activity for the group of children placed in the foster care intervention, particularly those placed before 24 months of age compared to children who were randomized to CAUG or those placed into families after this age. At 12 years, differences between those in the FCG and those in the CAUG persist in the alpha band (8–13 Hz, but not in higher frequency bands (i.e. in the beta band; 15–30 Hz, except in those children placed into the FCG who remained in high quality care environments over the course of the study. These findings highlight the importance of maintaining a stable high quality caregiving environment, particularly for children exposed to early psychosocial deprivation, for promoting healthy brain development.

  19. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  20. Heterogeneous reactors

    International Nuclear Information System (INIS)

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author)

  1. Plasma reactor

    OpenAIRE

    Molina Mansilla, Ricardo; Erra Serrabasa, Pilar; Bertrán Serra, Enric

    2008-01-01

    [EN] A plasma reactor that can operate in a wide pressure range, from vacuum and low pressures to atmospheric pressure and higher pressures. The plasma reactor is also able to regulate other important settings and can be used for processing a wide range of different samples, such as relatively large samples or samples with rough surfaces.

  2. Reactor physics

    International Nuclear Information System (INIS)

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  3. Main problems regarding the decommissioning of VVR-S research reactors

    International Nuclear Information System (INIS)

    The Romanian VVR-S research reactor has been put in operation in 1957 and it worked continuously without major events up to the present moment. During this period, there were not made major modifications concerning the core and the main circuits. The reactor works with the original equipment and control instrumentation supplied by the Soviets. Taking into account the long time of operation (over 35 years), the limited fuel reserve (for about 3-4 years), the low neutron flux performances (about 1013 n/cm2 s) and the safety aspects, a decommissioning project is imposed. This complex activity began in Romania in 1992. This paper presents the major aspects of our activity in this field: preparation of up-to-date libraries of nuclear data including all materials in the real composition of the reactor structures; the reactor calculation system adaptation at the specific activities of decommissioning; technical analysis of VVR-S Bucharest research reactor; safety analysis; the improvement of decontamination methods; modern method for waste management and disposal. There are also provided some preliminary results regarding calculated radioactive inventory, measured primary circuit contamination, technical and safety analysis. (author) 1 fig., 1 tab., 5 refs

  4. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  5. Safe operation of a TRIGA reactor in the situation of LEU-HEU core conversion

    International Nuclear Information System (INIS)

    Romanian TRIGA reactor was commissioned in 1980. The location of the research institute is Pitesti, 100 Km west of Bucharest. In fact there are two independent cores sharing the same pool. There are a 14 MW Steady State Reactor (SSR), high flux, and materials testing reactor and an Annular Core Pulsing Reactor (ACPR). The SSR reactor is a forced convection reactor cooled via a primary circuit with 4 pumps and 3 heat exchangers. The ACPR is natural convection cooled by the pool water. Modifications performed concerning core configuration resulted in the following. Removal the central pin from the bundle leads to slightly temperature increase of approximately 1% for the corner and edge pins, for the same pin power density. Also, the temperature slightly decreases for the 4 pins adjacent to the water hole. This is caused by the coolant flow redistribution. But, according to preliminary neutronic computations, PPF-s are decreasing, the edge and corner temperatures changes are no more detectable. DNB are decreasing, leading to a safer operation. Fuel management of TRIGA steady state core allows to obtain the requested fluxes for experimental reasons in the safer operation conditions. We can firmly state that the present operation of the reactor and the HEU-LEU core conversion fully respect the provisions of the National Regulatory Body and the IAEA. On the other side, we have to mention the common fact that research reactors cannot sustain themselves in the financial domain. The lack of sufficient financial support leads to shortage of the maintenance programs and to reduce of activities and personnel member; this is a real danger in maintaining the actual standards of nuclear safety. During this transition period, the Romanian TRIGA reactor is used much its capability in the frame of international cooperation this facility can ensure support for various research programmes in the fields of interest

  6. Negative Ecodomy in Romanian Politics and Religion: Anti-Muslim Attitudes in the Bucharest Mosque Scandal during the Summer of 2015

    Directory of Open Access Journals (Sweden)

    Corneliu C. Simuț

    2015-12-01

    Full Text Available This paper focuses on a chronology of events presented by the Romanian media, especially newspapers with national coverage and impact like Gândul and Adevărul, between the first week of June to the first week of September 2015, when the issue of having a mosque erected in Bucharest, the capital city of Romania, was intensely debated by intellectuals, politicians, and religious professionals. The debates were intensely heated from the onset of these events and most of them revealed that most of the participants were driven by anti-Muslim attitudes, xenophobia, and assertive nationalism, a complex of feelings that I called “negative ecodomy”. The concept of “negative ecodomy” presupposes an attempt to built a safe environment, in this case for Romanians in their own country, but the adjective “negative” was added to the the positive idea of “ecodomy” because these efforts to offer a safe context for Romanians were accompanied by the negativity of anti-Muslim, xenophobic, and nationalistic activities. This array of negative ecodomic attitudes were displayed by Romanians not only in online media but also in the street through protests and other similar actions in a country which has been a member of the European Union for almost a decade and was supposed to adhere to the European Union’s basic principles of multiculturalism and the free circulation of persons. The totality of these events show that Romanians are still rather far from accepting the European Union’s fundamental philosophy or perhaps these principles themselves should be reconsidered and reinterpreted in the context of the massive Middle Eastern and African immigration and the constant, if not increasing threat of Islamic terrorism.

  7. Time-series MODIS satellite and in-situ data for spatio-temporal distribution of aerosol pollution assessment over Bucharest metropolitan area

    Science.gov (United States)

    Zoran, Maria A.; Savastru, Roxana S.; Savastru, Dan M.

    2015-10-01

    With the increasing industrialization and urbanization, especially in the metropolis regions, aerosol pollution has highly negative effects on environment. Urbanization is responsible of three major changes that may have impact on the urban atmosphere: replacement of the natural surfaces with buildings and impermeable pavements, heat of anthropogenic origin and air pollution. The importance of aerosols for radiative and atmospheric chemical processes is widely recognized. They can scatter and/or absorb solar radiation leading to changes of the radiation budget. Also, the so-called indirect effect of aerosols describes the cloud-aerosol interactions, which can modify the chemical and physical processes in the atmosphere. Their high spatial variability and short lifetime make spaceborne sensors especially well suited for their observation. Remote sensing is a key application in global-change science and urban climatology. Since the launch of the MODerate resolution Imaging Spectroradiometer (MODIS) there is detailed global aerosol information available, both over land and oceans The aerosol parameters can be measured directly in situ or derived from satellite remote sensing observations. All these methods are important and complementary. The objective of this work was to document the seasonal and inter-annual patterns of the aerosol pollution particulate matter in two size fractions (PM10 and PM2.5) loading and air quality index (AQI) over Bucharest metropolitan area in Romania based on in-situ and MODIS (Terra-Moderate Resolution Imaging Spectoradiometer) satellite time series data over 2010-2012 period. Accurate information of urban air pollution is required for environmental and health policy, but also to act as a basis for designing and stratifying future monitoring networks.

  8. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  9. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  10. Nuclear reactors

    International Nuclear Information System (INIS)

    This draft chart contains graphical symbols from which the type of (nuclear) reactor can be seen. They will serve as illustrations for graphical sketches. Important features of the individual reactor types are marked out graphically. The user can combine these symbols to characterize a specific reactor type. The basic graphical symbol is a square with a point in the centre. Functional groups can be depicted for closer specification. If two functional groups are not clearly separated, this is symbolized by a dotted line or a channel. Supply and discharge lines for coolant, moderator and fuel are specified in accordance with DIN 2481 and can be further specified by additional symbols if necessary. The examples in the paper show several different reactor types. (orig./AK)

  11. Multifunctional reactors

    OpenAIRE

    Westerterp, K.R.

    1992-01-01

    Multifunctional reactors are single pieces of equipment in which, besides the reaction, other functions are carried out simultaneously. The other functions can be a heat, mass or momentum transfer operation and even another reaction. Multifunctional reactors are not new, but they have received much emphasis in research in the last decade. A survey is given of modern developments and the first successful applications on a large scale. It is explained why their application in many instances is ...

  12. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  13. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  14. Breeder reactors

    International Nuclear Information System (INIS)

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components

  15. Research reactors - an overview

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.

    1997-03-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  16. Reactor utilization

    International Nuclear Information System (INIS)

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  17. Reactor Neutrinos

    CERN Document Server

    Lasserre, T; Lasserre, Thierry; Sobel, Henry W.

    2005-01-01

    We review the status and the results of reactor neutrino experiments, that toe the cutting edge of neutrino research. Short baseline experiments have provided the measurement of the reactor neutrino spectrum, and are still searching for important phenomena such as the neutrino magnetic moment. They could open the door to the measurement of coherent neutrino scattering in a near future. Middle and long baseline oscillation experiments at Chooz and KamLAND have played a relevant role in neutrino oscillation physics in the last years. It is now widely accepted that a new middle baseline disappearance reactor neutrino experiment with multiple detectors could provide a clean measurement of the last undetermined neutrino mixing angle theta13. We conclude by opening on possible use of neutrinos for Society: NonProliferation of Nuclear materials and Geophysics.

  18. Nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor has a large prompt negative temperature coefficient of reactivity. A reactor core assembly of a plurality of fluid-tight fuel elements is located within a water-filled tank. Each fuel element contains a solid homogeneous mixture of 50-79 w/o zirconium hydride, 20-50 w/o uranium and 0.5-1.5 W erbium. The uranium is not more than 20 percent enriched, and the ratio of hydrogen atoms to zirconium atoms is between 1.5:1 and 7:1. The core has a long lifetime, E.G., at least about 1200 days

  19. Nuclear reactors

    International Nuclear Information System (INIS)

    In a liquid cooled nuclear reactor, the combination is described for a single-walled vessel containing liquid coolant in which the reactor core is submerged, and a containment structure, primarily of material for shielding against radioactivity, surrounding at least the liquid-containing part of the vessel with clearance therebetween and having that surface thereof which faces the vessel make compatible with the liquid, thereby providing a leak jacket for the vessel. The structure is preferably a metal-lined concrete vault, and cooling means are provided for protecting the concrete against reaching a temperature at which damage would occur. (U.S.)

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    In an improved reactor core for a high conversion BWR reactor, Pu-breeding type BWR type reactor, Pu-breeding type BWR type rector, FEBR type reactor, etc., two types of fuel assemblies are loaded such that fuel assemblies using a channel box of a smaller irradiation deformation ratio are loaded in a high conversion region, while other fuel assemblies are loaded in a burner region. This enables to suppress the irradiation deformation within an allowable limit in the high conversion region where the fast neutron flux is high and the load weight from the inside of the channel box due to the pressure loss is large. At the same time, the irradiation deformation can be restricted within an allowable limit without deteriorating the neutron economy in the burner region in which fast neutron flux is low and the load weight from the inside of the channel box is small since a channel box with smaller neutron absorption cross section or reduced wall thickness is charged. As a result, it is possible to prevent structural deformations such as swelling of the channel box, bending of the entire assemblies, bending of fuel rods, etc. (K.M.)

  1. TERRITORIAL INTELLIGENCE AMONG BUCHAREST REGION

    OpenAIRE

    Ioan RADU; BRÂNZAŞ Beniamin Viorel; MATEI Ramona Mihaela

    2013-01-01

    TThis paper proposes a relatively new concept for Romania, but commonly used in developed countries such as Germany, France, Holland and Italy. Debate on the scope of economic and territorial intelligence in Romania derived from a series of government measures and projects which foster the integration of urban and rural settlements in their own organizational entities, even autonomous. According to the literature and to developed cities, there might be patterned some specific features that ar...

  2. Reactor container

    International Nuclear Information System (INIS)

    A reactor container has a suppression chamber partitioned by concrete side walls, a reactor pedestal and a diaphragm floor. A plurality of partitioning walls are disposed in circumferential direction each at an interval inside the suppression chamber, so that independent chambers in a state being divided into plurality are formed inside the suppression chamber. The partition walls are formed from the bottom portion of the suppression chamber up to the diaphragm floor to isolate pool water in a divided state. Operation platforms are formed above the suppression chamber and connected to an access port. Upon conducting maintenance, inspection or repairing, a pump is disposed in the independent chamber to transfer pool water therein to one or a plurality of other independent chambers to make it vacant. (I.N.)

  3. Reactor building

    International Nuclear Information System (INIS)

    The present invention concerns a structure of ABWR-type reactor buildings, which can increase the capacity of a spent fuel storage area at a low cost and improved earthquake proofness. In the reactor building, the floor of a spent fuel pool is made flat, and a depth of the pool water satisfying requirement for shielding is ensured. In addition, a depth of pool water is also maintained for a equipment provisionally storing pool for storing spent fuels, and a capacity for a spent fuel storage area is increased by utilizing surplus space of the equipment provisionally storing pool. Since the flattened floor of the spent fuel pool is flushed with the floor of the equipment provisionally storing pool, transfer of horizontal loads applied to the building upon occurrence of earthquakes is made smooth, to improve earthquake proofness of the building. (T.M.)

  4. Nuclear reactors

    International Nuclear Information System (INIS)

    Disclosed is a nuclear reactor cooled by a freezable liquid has a vessel for containing said liquid and comprising a structure shaped as a container, and cooling means in the region of the surface of said structure for effecting freezing of said liquid coolant at and for a finite distance from said surface for providing a layer of frozen coolant on and supported by said surface for containing said liquid coolant. In a specific example, where the reactor is sodium-cooled, the said structure is a metal-lined concrete vault, cooling is effected by closed cooling loops containing NaK, the loops extending over the lined surface of the concrete vault with outward and reverse pipe runs of each loop separated by thermal insulation, and air is flowed through cooling pipes embedded in the concrete behind the metal lining. 7 claims, 3 figures

  5. NEUTRONIC REACTORS

    Science.gov (United States)

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    The liquid metal (sodium) cooled fast breeder reactor has got fuel subassemblies which are bundled and enclosed by a common can. In order to reduce bending of the sides of the can because of the load caused by the coolant pressure the can has got a dodecagon-shaped crosssection. The surfaces of the can may be of equal width. One out of two surfaces may also be convex towards the center. (RW)

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    A detector having high sensitivity to fast neutrons and having low sensitivity to thermal neutrons is disposed for reducing influences of neutron detector signals on detection values of neutron fluxes when the upper end of control rod pass in the vicinity of the neutron flux detector. Namely, the change of the neutron fluxes is greater in the thermal neutron energy region while it is smaller in the fast neutron energy region. This is because the neutron absorbing cross section of B-10 used as neutron absorbers of control rods is greater in the thermal neutron region and it is smaller in the fast neutron region. As a result, increase of the neutron detection signals along with the local neutron flux change can be reduced, and detection signals corresponding to the reactor power can be obtained. Even when gang withdrawal of operating a plurality of control rods at the same time is performed, the reactor operation cycle can be measured accurately, thereby enabling to shorten the reactor startup time. (N.H.)

  8. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    In a BWR type nuclear reactor, the number of first fuel assemblies (uranium) loaded in a reactor core is smaller than that of second fuel assemblies (mixed oxide), the average burnup degree upon take-out of the first fuel assemblies is reduced to less than that of the second fuel assemblies, and the number of the kinds of the fuel rods constituting the first fuel assemblies is made smaller than that of the fuel rods constituting the second fuel assemblies. As a result, the variety of the plutonium enrichment degree is reduced to make the distribution of the axial enrichment degree uniform, thereby enabling to simplify the distribution of the enrichment degree. Then the number of molding fabrication steps for MOX fuel assemblies can be reduced, thereby enabling to reduce the cost for molding and fabrication. (N.H.)

  9. Types of Nuclear Reactors

    International Nuclear Information System (INIS)

    The presentation is based on the following areas: Types of Nuclear Reactors, coolant, moderator, neutron spectrum, fuel type, pressurized water reactor (PWR), boiling water reactor (BWR) reactor pressurized heavy water (PHWR), gas-cooled reactor, RBMK , Nuclear Electricity Generation,Challenges in Nuclear Technology Deployment,EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR.

  10. National facilities for the management of institutional radioactive waste in Romania: 25 years of operation for radioactive waste treatment plant, Bucharest-Magurele, 15 years of operation for national radioactive repository, Baita-Bihor

    International Nuclear Information System (INIS)

    The management of the non-fuel cycle radioactive wastes in Romania is centralized at IFIN-HH in the Radioactive Waste Treatment Plant (STDR) Bucharest-Magurele and the National Repository of Radioactive Waste (DNDR) Baita-Bihor. From November 1974 to November 1999 there were treated at STDR nearly 26,000 m3 LLAW, 2,100 m3 LLSW and 4,000 spent sources resulting over 5,500 conditioned packages disposed at DNDR. After 25 years of operation for STDR and 15 years of operation for DNDR an updating programme started in 1991. The R and D programme will improve the basic knowledge and waste management practices for the increasing of nuclear safety in the field. (authors)

  11. Nuclear reactor

    International Nuclear Information System (INIS)

    A nuclear reactor is described in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assemblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters in the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters in the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance

  12. Nuclear research reactors

    International Nuclear Information System (INIS)

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.)

  13. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  14. Nuclear reactor

    International Nuclear Information System (INIS)

    Cover gas spaces for primary coolant vessel, such as a reactor container, a pump vessel and an intermediate heat exchanger vessel are in communication with each other by an inverted U-shaped pressure conduit. A transmitter and a receiver are disposed to the pressure conduit at appropriate positions. If vibration frequencies (pressure vibration) from low frequency to high frequency are generated continuously from the transmitter to the inside of the communication pipe, a resonance phenomenon (air-column resonance oscillation) is caused by the inherent frequency or the like of the communication pipe. The frequency of the air-column resonance oscillation is changed by the inner diameter and the clogged state of the pipelines. Accordingly, by detecting the change of the air-column oscillation characteristics by the receiver, the clogged state of the flow channels in the pipelines can be detected even during the reactor operation. With such procedures, steams of coolants flowing entrained by the cover gases can be prevented from condensation and coagulation at a low temperature portion of the pipelines, otherwise it would lead clogging in the pipelines. (I.N.)

  15. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)

    2011-01-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  16. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  17. SANS facility at the Pitesti 14 MW Triga reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ionita, I.; Anghel, E.; Mincu, M.; Datcu, A. [Institute for Nuclear Research - Pitesti (Romania); Grabcev, B.; Todireanu, S. [National Institute of Materials Physics (NIMP) Bucharest (Romania); Constantin, F. [National Institute of Physics and Nuclear Engineering Bucharest (Romania); Shvetsov, V. [Joint Institute for Nuclear Research Dubna (Russian Federation); Popescu, G. [National College Al. Odobescu Pitesti (Romania)

    2006-07-01

    Full text of publication follows: At the present time, an important not yet fully exploited potentiality is represented by the SANS instruments existent at lower power reactors and reactors in developing countries even if they are, generally, endowed with a simpler equipment and are characterized by the lack of infrastructure to maintain and repair high technology accessories. The application of SANS at lower power reactors and in developing countries nevertheless is possible in well selected topics where only a restricted Q range is required, when scattering power is expected to be sufficiently high or when the sample size can be increased at the expense of resolution. Examples of this type of applications are: 1) Phase separation and precipitates in material science, 2) Ultrafine grained materials (nano-crystals, ceramics), 3) Porous materials such as concretes and filter materials, 4) Conformation and entanglements of polymer-chains, 5) Aggregates of micelles in microemulsions, gels and colloids, 6) Radiation damage in steels and alloys. The need for the installation of a new SANS facility at the Triga Reactor of the Institute of Nuclear Researches in Pitesti, Romania become actual especially after the shutting down of the VVRS Reactor from Bucharest. A monochromatic neutron beam with 1.5 Angstrom {<=} {lambda} {<=} 5 Angstrom is produced by a mechanical velocity selector with helical slots.The distance between sample and detectors plane is (5.2 m ). The sample width may be fixed between 10 mm and 20 mm. The minimum value of the scattering vector is Q{sub min} = 0.005 Angstrom{sup -1} while the maximal value is Q{sub max} = 0.5 Angstrom{sup -1}. The relative error is {delta}Q/Q{sub min} = 0.5. The cooperation partnership between advanced research centers and the smaller ones from developing countries could be fruitful. The formers act as mentors in solving specific problems. Such a partnership was established between INR Pitesti, Romania and JINR Dubna, Russia

  18. SANS facility at the Pitesti 14 MW Triga reactor

    International Nuclear Information System (INIS)

    Full text of publication follows: At the present time, an important not yet fully exploited potentiality is represented by the SANS instruments existent at lower power reactors and reactors in developing countries even if they are, generally, endowed with a simpler equipment and are characterized by the lack of infrastructure to maintain and repair high technology accessories. The application of SANS at lower power reactors and in developing countries nevertheless is possible in well selected topics where only a restricted Q range is required, when scattering power is expected to be sufficiently high or when the sample size can be increased at the expense of resolution. Examples of this type of applications are: 1) Phase separation and precipitates in material science, 2) Ultrafine grained materials (nano-crystals, ceramics), 3) Porous materials such as concretes and filter materials, 4) Conformation and entanglements of polymer-chains, 5) Aggregates of micelles in microemulsions, gels and colloids, 6) Radiation damage in steels and alloys. The need for the installation of a new SANS facility at the Triga Reactor of the Institute of Nuclear Researches in Pitesti, Romania become actual especially after the shutting down of the VVRS Reactor from Bucharest. A monochromatic neutron beam with 1.5 Angstrom ≤ λ ≤ 5 Angstrom is produced by a mechanical velocity selector with helical slots.The distance between sample and detectors plane is (5.2 m ). The sample width may be fixed between 10 mm and 20 mm. The minimum value of the scattering vector is Qmin = 0.005 Angstrom-1 while the maximal value is Qmax = 0.5 Angstrom-1. The relative error is ΔQ/Qmin = 0.5. The cooperation partnership between advanced research centers and the smaller ones from developing countries could be fruitful. The formers act as mentors in solving specific problems. Such a partnership was established between INR Pitesti, Romania and JINR Dubna, Russia. The first step in this cooperation consists

  19. Reactor container

    International Nuclear Information System (INIS)

    Purpose: To prevent shocks exerted on a vent head due to pool-swell caused within a pressure suppression chamber (disposed in a torus configuration around the dry well) upon loss of coolant accident in BWR type reactors. Constitution: The following relationship is established between the volume V (m3) of a dry well and the ruptured opening area A (m2) at the boundary expected upon loss of coolant accident: V >= 30340 (m) x A Then, the volume of the dry well is made larger than the ruptured open area, that is, the steam flow rate of leaking coolants upon loss of coolant accident to decrease the pressure rise in the dry well at the initial state where loss of coolant accident is resulted. Accordingly, the pressure of non-compressive gases jetted out from the lower end of the downcomer to the pool water is decreased to suppress the pool-swell. (Ikeda, J.)

  20. Survey of research reactors

    International Nuclear Information System (INIS)

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  1. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  2. RB reactor noise analysis

    International Nuclear Information System (INIS)

    Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed

  3. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  4. Reactor Physics Training

    International Nuclear Information System (INIS)

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  5. Introduction of Nuclear Reactor Engineering

    International Nuclear Information System (INIS)

    This book introduces development, status, supply and demand and resource of nuclear reactor. It deals with basic knowledge of nuclear reactor, which are reactor system, heat recovery in reactor core, structural feature in reactor, materials of structure in reactor, shielding of gamma ray, shielding of reactor, safety and environmental problem of nuclear power plant, nuclear fuel and economical efficiency of nuclear energy.

  6. Safeguarding research reactors

    International Nuclear Information System (INIS)

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  7. Research nuclear reactors

    International Nuclear Information System (INIS)

    Since the divergence of the first nuclear reactor in 1942, about 600 research or test reactors have been built throughout the world. Today 255 research reactors are operating in 57 countries and about 70% are over 25 years old. Whereas there are very few reactor types for power plants because of rationalization and standardisation, there is a great diversity of research reactors. We can divide them into 2 groups: heavy water cooled reactors and light water moderated reactors. Heavy water cooled reactors are dedicated to the production of high flux of thermal neutrons which are extracted from the core by means of neutronic channels. Light water moderated reactors involved pool reactors and slightly pressurized closed reactors, they are polyvalent but their main purposes are material testing, technological irradiations, radionuclide production and neutron radiography. At the moment 8 research reactors are being built in Canada, Germany, Iran, Japan, Kazakhstan, Morocco, Russia and Slovakia and 8 others are planned in 7 countries (France, Indonesia, Nigeria, Russia, Slovakia, Thailand and Tunisia. Different research reactors are described: Phebus, Masurca, Phenix and Petten HFR. The general principles of nuclear safety applied to test reactors are presented. (A.C.)

  8. Achievements and future directions in the reactors physics and nuclear safety research

    International Nuclear Information System (INIS)

    A historical overlook is presented with respect to inception and development of reactor physics research and on the job training in Romania. First these activities were carried out at the Institute for Atomic Physics and Institute for Power Reactors (IRNE) in Bucharest and afterward at the Institute for Nuclear Technologies, later on transformed in the Institute of Nuclear Research at Pitesti. CYBER Computer installed at Pitesti allowed formation in as early as 1971 reactor specialists who worked out computer programs for neutron physics calculations. These specialists were able to assimilate the characteristic of CANDU 6 type reactor as well as the AECL methodology of simulating processes of CANDU reactor physics. At present four programs are under way. These are: 1. The nuclear reactor physics; 2. The nuclear facility safety; 3. Safety analyses for the transport and radioactive waste disposal; 4. Analyses for radiation shielding and biological protection. There are presented results of the work associated to the CANDU type reactor: 1. Adapting and improving the code system for neutron and thermohydraulic calculation for CANDU type reactor, as supplied by AECL; 2. The IRNE manual for CANDU reactor neutron designing; 3. Final sizing of shim rods of Cernavoda NPP Unit 2; 4. Tests and measurements of reactor physics at the Cernavoda NPP Unit 1 commissioning; 5. Simulation and independent analysis of thermosiphoning carried out at Cernavoda NPP Unit 1 commissioning; 6. Static and dynamical response of the detectors in the CANDU reactor core and their time evolution following the burnup in the neutron flux and their ageing effects; 7. PSA studies at Unit 1; 8. Safety analyses for the radioactive waste disposal at Saligny repository. Also, reported are the results of the work associated to the TRIGA reactor, as follows: 1. Flux measurements and neutron computations necessary in the reactor commissioning; 2. Cleaning up controversial issues relating to neutron flux

  9. Nuclear reactor building

    International Nuclear Information System (INIS)

    Purpose: To prevent seismic vibrations of external buildings from transmitting to the side walls of a reactor container in a tank type FBR reactor building. Constitution: The reactor building is structured such that the base mat for a reactor container chamber and a reactor container is separated from the base mat for the walls of building, and gas-tight material such as silicon rubber is filled in the gap therebetween. With such a constitution, even if the crane-supporting wall vibrates violently upon occurrence of earthqualkes, the seismic vibrations do not transmit toward the reactor container chamber. (Horiuchi, T.)

  10. Reactor Physics Programme

    International Nuclear Information System (INIS)

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

  11. Conferinţa Mondială a Populaţiei, Bucureşti 1974. Semnificaţii politice (World Population Conference, Bucharest 1974. Political Meanings

    Directory of Open Access Journals (Sweden)

    Cezar STANCIU

    2014-09-01

    Full Text Available n 1974, the United Nations organized the first inter-governmental conference dedicated especially to problems of population and demography. Apart from technical issue involved, the conference represented yet another manifestation of disagreements between the industrialized countries, on one hand, and the underdeveloped or developing countries. The first group argued that overpopulation was a major risk as the Earth did not have sufficient resources to feed the ever-growing population and birth control measures were required. The latter group disagreed with this perspective and claimed that population issues could be solved only by the development of the poor countries. Development, argued this group of countries, had to be insured by a restructuring of the international economy and more financial assistance from the developed countries. This paper examines Romania’s position in this context, analyzing how the regime in Bucharest tried to balance between foreign constraints such as its obligation as host country to remain neutral, its effort to build bridges to the underdeveloped or developing countries thus trying to tacitly evade it international status of Warsaw Pact member and gain acceptance in the Group of 77. The World Population Conference in 1974 is a conclusive case study for Romania’s foreign policy after the Soviet-American détente of 1972.

  12. Greenhouse gas reduction by recovery and utilization of landfill methane and CO{sub 2} technical and market feasibility study, Boului Landfill, Bucharest, Romania. Final report, September 30, 1997--September 19, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Cook, W.J.; Brown, W.R.; Siwajek, L. [Acrion Technologies, Inc., Cleveland, OH (United States); Sanders, W.I. [Power Management Corp., Bellevue, WA (United States); Botgros, I. [Petrodesign, SA, Bucharest (Romania)

    1998-09-01

    The project is a landfill gas to energy project rated at about 4 megawatts (electric) at startup, increasing to 8 megawatts over time. The project site is Boului Landfill, near Bucharest, Romania. The project improves regional air quality, reduces emission of greenhouse gases, controls and utilizes landfill methane, and supplies electric power to the local grid. The technical and economic feasibility of pre-treating Boului landfill gas with Acrion`s new landfill gas cleanup technology prior to combustion for power production us attractive. Acrion`s gas treatment provides several benefits to the currently structured electric generation project: (1) increase energy density of landfill gas from about 500 Btu/ft{sup 3} to about 750 Btu/ft{sup 3}; (2) remove contaminants from landfill gas to prolong engine life and reduce maintenance;; (3) recover carbon dioxide from landfill gas for Romanian markets; and (4) reduce emission of greenhouse gases methane and carbon dioxide. Greenhouse gas emissions reduction attributable to successful implementation of the landfill gas to electric project, with commercial liquid CO{sub 2} recovery, is estimated to be 53 million metric tons of CO{sub 2} equivalent of its 15 year life.

  13. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  14. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    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

  15. Process heat reactors

    International Nuclear Information System (INIS)

    The consumption of heat, for industrial and domestic needs, takes up half of the national energy supply; direct utilization of the heat produced by nuclear reactors could therefore contribute to reduce the deficit in the energetic results. The restraints proper to heat consumption (dispersal and variety of consumers, irregular demand) involve the development of the heat transport system structures and adequate nuclear reactors. With this in view, the Commissariat a l'Energie Atomique and Technicatome are developing the CAS reactor series, pressurized water reactors (PWR), (CAS 3G reactor with a power of 420 MW.th.), and the Thermos reactor (100 MW.th.), directly conceived to produce heat at 1200C and whose technology derives from the experimental pool reactors type. In order to prove the value of the Thermos design, an experimental reactor should soon be constructed in the Saclay nuclear research centre

  16. Reactor System Design

    International Nuclear Information System (INIS)

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  17. Nuclear Reactor RA Safety Report, Vol. 11, Reactor operation

    International Nuclear Information System (INIS)

    This volume includes the following chapters describing: Organisation of reactor operation (including operational safety, fuel management, and regulatory rules for RA reactor operation); Control and maintenance of reactor components (reactor core, nuclear fuel, heavy water and cover gas systems, mechanical structures, electric power supply system, reactor instrumentation); Quality assurance and Training of the reactor personnel

  18. The Chernobylsk reactor accident

    International Nuclear Information System (INIS)

    The construction, the safety philosophy, the major reactor physical parameters of RBMK-1000 type reactor units and the detailed description of the Chernobylsk-4 reactor accident, its causes and conclusions, the efforts to reduce the consequences on the reactor site and in the surroundings are discussed based on different types of Soviet documents including the report presented to the IAEA by the Soviet Atomic Energy Agency in August 1986. (V.N.)

  19. Zero energy reactor 'RB'

    International Nuclear Information System (INIS)

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  20. High solids fermentation reactor

    Science.gov (United States)

    Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.

    1993-01-01

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  1. Fossil nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Maurette, M.

    1976-01-01

    The discussion of fossil nuclear reactors (the Oklo phenomenon) covers the earth science background, neutron-induced isotopes and reactor operating conditions, radiation-damage studies, and reactor modeling. In conclusion possible future studies are suggested and the significance of the data obtained in past studies is summarized. (JSR)

  2. Fusion reactor studies

    International Nuclear Information System (INIS)

    A review is given of fusion reactor systems studies, the objectives of these studies are outlined and some recent conceptual reactor designs are described. The need for further studies in greater depth is indicated so that progress towards a commercial fusion reactor may be consolidated. (U.K.)

  3. Reactor power measuring device

    International Nuclear Information System (INIS)

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  4. Research nuclear reactor and particle accelerator as complementary facilities in obtaining experimental nuclear data

    International Nuclear Information System (INIS)

    In the last decade a large amount of diverse and high precision nuclear data is in high demand to support both power applications (in nuclear fusion and fission reactors, fuel cycle in all its stages, nuclear safety) and non-power applications (radiation dosimetry, life sciences, ecology, industry, etc.) of atomic and nuclear techniques. The atomic and nuclear data are generated from experimental measurements, theoretical model calculations and data evaluation, which are finally validated internationally and included in data bases under standardized formats. Measuring of these data imply utilization of research reactors and charged particle accelerators, in complex experiments characterized by high degree of complementarity. Aspects of this complementarity in the nuclear data obtained from reactors and accelerators will be presented in this work. In Romania an advanced research reactor (TRIGA at INR Pitesti) and an electrostatic 4-5 MeV/nucleon accelerator (TANDEM Van de Graaff at IFIN - HH, Bucharest) are operational and a rich scientific expertise in the field of nuclear structure and reaction mechanisms is available. Consequently, the paper considers a project at a national scale for measuring and evaluating nuclear data. Having in view numerous signals launched by international organizations (IAEA-Vienna, NEA-OECD, NNDC-USA) such a project would have a powerful international support because of increasing world wide demand of atomic and nuclear data. Nuclear data are either structure and decay nuclear data or reaction nuclear data. The first class refers to nuclear state properties (masses, excitation energies, quantum numbers, lifetimes, etc.) as well as to their decay modes. Data from the second class refer to differential or integral cross sections. The paper presents comparatively the data obtainable at accelerators and reactors for the two above mentioned classes of nuclear data, particularly, the data required for building ADS (Accelerator Driven Systems

  5. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  6. Nuclear reactor repairing device

    International Nuclear Information System (INIS)

    Purpose: To enable free repairing of an arbitrary position in an LMFBR reactor. Constitution: A laser light emitted from a laser oscillator installed out of a nuclear reactor is guided into a portion to be repaired in the reactor by using a reflecting mirror, thereby welding or cutting it. The guidance of the laser out of the reactor into the reactor is performed by an extension tube depending into a through hole of a rotary plug, and the guidance of the laser light into a portion to be repaired is performed by the transmitting and condensing action of the reflecting mirror. (Kamimura, M.)

  7. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  8. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  9. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPRTM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENATM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENATM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  10. The Maple reactor project

    International Nuclear Information System (INIS)

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  11. High temperature reactors

    International Nuclear Information System (INIS)

    With the advent of high temperature reactors, nuclear energy, in addition to producing electricity, has shown enormous potential for the production of alternate transport energy carrier such as hydrogen. High efficiency hydrogen production processes need process heat at temperatures around 1173-1223 K. Bhabha Atomic Research Centre (BARC), is currently developing concepts of high temperature reactors capable of supplying process heat around 1273 K. These reactors would provide energy to facilitate combined production of hydrogen, electricity, and drinking water. Compact high temperature reactor is being developed as a technology demonstrator for associated technologies. Design has been also initiated for a 600 MWth innovative high temperature reactor. High temperature reactor development programme has opened new avenues for research in areas like advanced nuclear fuels, high temperature and corrosion resistant materials and protective coatings, heavy liquid metal coolant technologies, etc. The paper highlights design of these reactors and their material related requirements

  12. Spinning fluids reactor

    Science.gov (United States)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  13. Reactor Safety: Introduction

    International Nuclear Information System (INIS)

    The programme of the Reactor Safety Division focuses on the development of expertise on materials behaviour under irradiation for fission and fusion oriented applications. Furthermore, as nuclear energy needs international public acceptance with respect to safety and efficient management of natural resources and wants to reduce the burden of nuclear waste, the Reactor Safety Division enhanced its efforts to develop the MYRRHA project. MYRRHA, an accelerator driven sub-critical system, might have the potential to cope in Europe with the above mentioned constraints on acceptability and might serve as a technological platform for GEN IV reactor development, in particular the Liquid Metal Fast Reactor.The Reactor Safety Division gathers three research entities that are internationally recognised: the Reactor Materials Research department, the Reactor Physics and MYRRHA department and the Instrumentation department.The objectives of Reactor Materials Research are: to evaluate the integrity and behaviour of structural materials and nuclear fuels used in present and future nuclear power industry; to perform research to unravel and understand the parameters that determine the material and fuel behaviour under or after irradiation; to contribute to the interpretation and modelling of the materials and fuels behaviour in order to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the Reactor Materials Research department concentrate on four distinct disciplines: Reactor Pressure Vessel Steel embrittlement Stress corrosion cracking in reactor coolant environment, including Irradiation Assisted Stress Corrosion Cracking; Nuclear Fuel characterisation and development of new fuel types for commercial and test reactors. Development of materials for Fusion and advanced nuclear fission reactors. The safe operation of present nuclear power plants relies primarily on the integrity of the reactor pressure vessel

  14. INAA of microelements in plant species from the Danube floodplain

    International Nuclear Information System (INIS)

    A research was developed and implemented in the Danube floodplain, as a part of a program dealing with biogeochemistry of metals, to assess the possibility of using the ubiquitous plant species in the soil pollution monitoring activity. The Danube River is heavily polluted by the input from a catchment, which includes 12 countries. Even if the concentrations in the Danube water and sediments reach acute values only in some hot spots, due to the dilution effect, they could have negative consequences by phenomena of bioaccumulation and bioconcentration. The content of Al, Ag, As, Au, Ba, Br, Ca, Cl, Ce, Co, Cr, Cs, Cu, Eu, Fe, Hg, Hf, K, La, Mg, Mn, Na, Ni, Rb, Sc, Se, Sm, Sr, Th, V and Zn in Bidens tripartita, Rubus caesius, Stachys palustris and Xanthium strumarium ubiquitous plant species, collected from two areas located on different regularly flooded islands of the Danube river was investigated by instrumental neutron activation analysis method at WWR-S reactor in Bucharest. From the statistical point of view, three groups of elements present highly correlated concentrations in the investigated plant samples (p(0.05))//. The first one includes Al, As, Ce, Cs, Eu, Fe, Hf, La, Sc, Sm, Th and V, the second one Au, Ca, Cu and Sr, and the third one Br, Cr, Na and Mn. For the elements of the first group, the elemental concentrations are found to be in similar ratios in the species investigated, namely: Xanthium s. < Rubus c. < Bidens t. < Stachys p. as well as for the third group: Bidens t. < Rubus c. < Stachys p. < Xanthium s, suggesting that physiological features of the species could be responsible for the observed patterns of distribution. The soil and dominating plant species were analysed for Cr, Cu, Fe, Mn, Ni, Pb, Zn and Zr by the X-ray fluorescence method at the Institute for Geological Explorations, Bucharest. The elemental content in soil is reflected in the analysed plants for Cr, Cu, Fe, Ni, Pb and Zn, but not for Mn. This could be explained by the redox

  15. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  16. Thai research reactor

    International Nuclear Information System (INIS)

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  17. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  18. Development of new MMS modules for CANDU reactors, using CompGen program

    International Nuclear Information System (INIS)

    Modelling of thermodynamic processes in stationary and dynamic regimes are very important for nuclear power plants from both design and operation point of view. Since safety requirements for NPPs are higher than the ones for classical power plants simulation analyses are necessary in this field. In the last years there where developed and improved many computing codes which can be used in such analyses. One of these codes is MMS. MMS package was developed by Framatome Technologies, Bacok and Wilcox and nHance Technologies Inc. It uses a modular architecture based on ACSL program. MMS is provided with a rich library of modules including control, electromechanical, gas, water, boundary, fossil and nuclear modules. Unfortunately, the water and nuclear modules were developed initially only for light LWR NPPs. The main problem of using MMS for CANDU NPPs was the lack of heavy water properties. Recently nHance Technologies improved some of existing modules allowing to work also with heavy water systems. However, development of new modules appropriate to CANDU reactors is necessary to simulate various systems in CANDU NPPs. New MMS modules developed by the authors, characteristic for CANDU NPPs concern: Calandria, heat exchanger, delay tank, end shield., fuel storage pool, calandria vault. These modules were built with means of CompGen program, which is included in the MMS package. They were used at Center of Technology and Engineering for Nuclear Projects - CITON, at Bucharest to simulate operational regimes of the primary circuit in Cernavoda NPP. In this present paper the capabilities of MMS package regarding thermal-hydraulic simulation of nuclear systems are shown . Also, presented are the results of a joint research of Power Plants Simulation Laboratory of University 'Politehnica' at Bucharest and CITON on several MMS modules, developed by using CompGen. These results serve for safety analyses for Cernavoda 2 NPP. As an illustration, a 'real' safety analysis for the

  19. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.)

  20. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  1. Evaluation of research reactors

    International Nuclear Information System (INIS)

    The present status of research reactors with highly enriched (93%) uranium fuel at JAERI, JRR-2 and JMTR is described. JRR-2 is a heterogeneous type of reactor, using heavy water as moderator and coolant. It uses both MTR type and cylindrical type of fuel elements. The maximum thermal power and the thermal neutron flux are 10 MW and 2x1014 n/cm2 see respectively. The reactor has been used for various experiments such as solid state physics, material irradiation, reactor fuel irradiation and radioisotope production. The JMTR is a multi-purpose tank type material testing reactor, and light water moderator and coolant, operated at 50 MW. The evaluation of lower enriched fuel and its consequences for both reactors is considered more especially

  2. Multipurpose research reactors

    International Nuclear Information System (INIS)

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  3. The nuclear soliton reactor

    International Nuclear Information System (INIS)

    The basic reactor physics of a completely novel nuclear fission reactor design - the soliton-reactor - is presented on the basis of a simple model. In such a reactor, the neutrons in the critical region convert either fertile material in the adjacent layers into fissile material or reduce the poisoning of fissile material in such a manner that successively new critical regions emerge. The result is an autocatalytically driven burn-up wave which propagates throughout the reactor. Thereby, the relevant characteristic spatial distributions (neutron flux, specific power density and the associated particle densities) are solitons - wave phenomena resulting from non-linear partial differential equations which do not change their shape during propagation. A qualitativley new kind of harnessing nuclear fission energy may become possible with fuel residence times comparable with the useful lifetime of the reactor system. In the long run, fast breeder systems which exploit the natural uranium and thorium resources, without any reprocessing capacity are imaginable. (orig.)

  4. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  5. Fusion reactor research

    International Nuclear Information System (INIS)

    This work covers four separate areas: (1) development of technology for processing liquid lithium from blankets, (2) investigation of hydrogen isotope permeation in candidate structural metals and alloys for near-term fusion reactors, (3) analytical studies encompassing fusion reactor thermal hydraulics, tritium facility design, and fusion reactor safety, and (4) studies involving dosimetry and damage analysis. Recent accomplishments in each of these areas are summarized

  6. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  7. The replacement research reactor

    International Nuclear Information System (INIS)

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  8. PFBR reactor protection

    International Nuclear Information System (INIS)

    Design philosophy adopted for Prototype Fast breeder Reactor (PFBR) is a classical one and has the following features: triplicated sensors for measuring important safety parameters; two independent reactor protection Logic Systems based on solid state devices; reactivity control achieved by control rods; gas equipped modules at the core blanket interface providing negative reactivity. Design verification of these features showed that safety of the reactor can be achieved by a traditional approach since the inherent features of LMFBR make this easy

  9. Reactor BR2

    International Nuclear Information System (INIS)

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  10. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  11. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  12. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  13. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  14. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

  15. New reactor concepts

    International Nuclear Information System (INIS)

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  16. Reactor construction steels

    International Nuclear Information System (INIS)

    The basic functions of light water reactor components are shown on the example of a pressurized water reactor and the requirements resulting therefrom for steel, the basic structural material, are derived. A detailed analysis of three main groups of reactor steels is presented and the applications are indicated of low-alloyed steels, high-alloyed austenitic steels, and steels with a high content of Ni and of alloying additions for steam generator pipes. An outline is given of prospective fast breeder reactor steels. (J.K.)

  17. Commercialization of fast reactors

    International Nuclear Information System (INIS)

    Comparative analysis has been performed of capital and fuel cycle costs for fast BN-type and pressurized light water VVER-type reactors. As a result of materials demand and components costs comparison of NPPs with VVER-1000 and BN-600 reactors, respectively, conclusion was made, that under equal conditions of the comparison, NPP with fast reactor had surpassed the specific capital cost of NPP with VVER by about 30 - 40 %. Ways were determined for further decrease of this difference, as well as for the fuel cycle cost reduction, because at present it is higher than that of VVER-type reactors. (author)

  18. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  19. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, a reactor core is disposed such that the top of the reactor core is always situated in a flooded position even if pipelines connected to the pressure vessel are ruptured and the level at the inside of the reactor vessel is reduced due to flashing. Further, a lower dry well situated below the pressure vessel is disposed such that it is in communication with a through hole to a pressure suppression chamber situated therearound and the reactor core is situated at the level lower than that of the through hole. If pipelines connected to the pressure vessel are ruptured to cause loss of water, although the water level is lowered after the end of the flashing, the reactor core is always flooded till the operation of a pressure accummulation water injection system to prevent the top of the reactor core even from temporary exposure. Further, injected water is discharged to the outside of the pressure vessel, transferred to the lower dry well, and flows through the through hole to the pressure control chamber and cools the surface of the reactor pressure vessel from the outside. Accordingly, the reactor core is cooled to surely and efficiently remove the after-heat. (N.H.)

  20. INVAP's Research Reactor Designs

    International Nuclear Information System (INIS)

    INVAP, an Argentine company founded more than three decades ago, is today recognized as one of the leaders within the research reactor industry. INVAP has participated in several projects covering a wide range of facilities, designed in accordance with the requirements of our different clients. For complying with these requirements, INVAP developed special skills and capabilities to deal with different fuel assemblies, different core cooling systems, and different reactor layouts. This paper summarizes the general features and utilization of several INVAP research reactor designs, from subcritical and critical assemblies to high-power reactors IAEA safety

  1. Reactor power control device

    International Nuclear Information System (INIS)

    The present invention provides a control device which can conduct scram and avoid lowering of the power of a nuclear power plant upon occurrence of earthquakes. Namely, the device of the present invention comprises, in addition to an existent power control device, (1) an earthquake detector for detecting occurrence and annihilation of earthquakes and (2) a reactor control device for outputting control rod operation signals and reactor core flow rate control signals depending on the earthquake detection signals from the detector, and reactor and plant information. With such a constitution, although the reactor is vibrated by earthquakes, the detector detects slight oscillations of the reactor by initial fine vibration waves as premonitory symptoms of serious earthquakes. The earthquake occurrence signals are outputted to the reactor control device. The reactor control device, receiving the signals, changes the position of control rods by way of control rod driving mechanisms to make the axial power distribution in the reactor core to a top peak type. As a result, even if the void amount in the reactor core is reduced by the subsequent actual earthquakes, since the void amount is moved, effects on the increase of neutron fluxes by the actual earthquakes is small. (I.S.)

  2. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  3. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

  4. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  5. One piece reactor removal

    International Nuclear Information System (INIS)

    Japan Research Reactor No.3 (JRR-3) was the first reactor consisting of 'Japanese-made' components alone except for fuel and heavy water. After reaching its initial critical state in September 1962, JRR-3 had been in operation for 21 years until March 1983. It was decided that the reactor be removed en-bloc in view of the work schedule, cost and management of the reactor following the removal. In the special method developed jointly by the Japanese Atomic Energy Research Institute and Shimizu Construction Co., Ltd., the reactor main unit was cut off from the building by continuous core boring, with its major components bound in the block with biological shield material (heavy concrete), and then conveyed and stored in a large waste store building constructed near the reactor building. Major work processes described in this report include the cutting off, lifting, horizontal conveyance and lowering of the reactor main unit. The removal of the JRR-3 reactor main unit was successfully carried out safely and quickly by the en-block removal method with radiation exposure dose of the workers being kept at a minimum. Thus the high performance of the en-bloc removal method was demonstrated and, in addition, valuable knowhow and other data were obtained from the work. (Nogami, K.)

  6. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  7. The fusion reactor

    International Nuclear Information System (INIS)

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  8. Polymerization Reactor Engineering.

    Science.gov (United States)

    Skaates, J. Michael

    1987-01-01

    Describes a polymerization reactor engineering course offered at Michigan Technological University which focuses on the design and operation of industrial polymerization reactors to achieve a desired degree of polymerization and molecular weight distribution. Provides a list of the course topics and assigned readings. (TW)

  9. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  10. Gas-cooled reactors

    International Nuclear Information System (INIS)

    The present study is the second part of a general survey of Gas Cooled Reactors (GCRs). In this part, the course of development, overall performance and present development status of High Temperature Gas Cooled Reactors (HTCRs) and advances of HTGR systems are reviewed. (author)

  11. Light water reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  12. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  13. Light water type reactor

    International Nuclear Information System (INIS)

    The nuclear reactor of the present invention prevents disruption of a reactor core even in a case of occurrence of entire AC power loss event, and even if a reactor core disruption should occur, it prevents a rupture of the reactor container due to excess heating. That is, a high pressure water injection system and a low pressure water injection system operated by a diesel engine are disposed in the reactor building in addition to an emergency core cooling system. With such a constitution, even if an entire AC power loss event should occur, water can surely be injected to the reactor thereby enabling to prevent the rupture of the reactor core. Even if it should be ruptured, water can be sprayed to the reactor container by the low pressure water injection system. Further, if each of water injection pumps of the high pressure water injection system and the low pressure water injection system can be driven also by motors in addition to the diesel engine, the pump operation can be conducted more certainly and integrally. (I.S.)

  14. Naval propulsion reactors

    International Nuclear Information System (INIS)

    This article deals with the design and exploitation of naval propulsion reactors, mainly of PWR-type. The other existing or conceivable types of reactors are also presented: 1 - specificities of nuclear propulsion (integration in the ship, marine environment, maneuverability, instantaneous availability, conditions of exploitation-isolation, nuclear safety, safety authority); 2 - PWR-type reactor (stable operation, mastered technology, general design, radiation protection); 3 - other reactor types; 4 - compact or integrated loops architecture; 5 - radiation protection; 6 - reactor core; 7 - reactivity control (core lifetime, control means and mechanisms); 8 - core cooling (natural circulation, forced circulation, primary flow-rate program); 9 - primary loop; 10 - pressurizer; 11 - steam generators and water-steam secondary loop; 12 - auxiliary and safety loops; 13 - control instrumentation; 14 - operation; 15 - nuclear wastes and dismantling. (J.S.)

  15. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  16. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 1014 n/cm2/sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  17. Reactor core monitoring method

    Energy Technology Data Exchange (ETDEWEB)

    Mori, Michitsugu [Tokyo Electric Power Co., Inc. (Japan); Kanemoto, Shigeru; Enomoto, Mitsuhiro; Ebata, Shigeo

    1998-05-06

    The present invention provides a method of monitoring the state of coolant flow in a reactor of a BWR power plant. Namely, a plurality of local power region monitors (LPRM) are disposed to the inside of the reactor core for monitoring a power distribution. Signals of at least two optional LPRM detectors situated at positions different in axial or radial positions of the reactor core are obtained. General fluctuation components which nuclear hydrothermally fluctuate in overall reactor core are removed from the components of the signals. Then, correlational functions between these signals are determined. The state of coolant flow in the reactor is monitored based on the correlational function. When the axial flowing rate and radial flow interference are monitored, the accuracy upon monitoring axial and radial local behaviors of coolants can be improved by thus previously removing the general fluctuation components from signals of LPRM detectors and extracting local void information near to LPRM detectors at high accuracy. (I.S.)

  18. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    This manual covers all the aspects of the science of neutron transport in nuclear reactors and can be used with great advantage by students, engineers or even reactor experts. It is composed of 18 chapters: 1) basis of nuclear physics, 2) the interactions of neutrons with matter, 3) the interactions of electromagnetic radiations and charged-particles with matter, 4) neutron slowing-down, 5) resonant absorption, 6) Doppler effect, 7) neutron thermalization, 8) Boltzmann equation, 9) calculation methods in neutron transport theory, 10) neutron scattering, 11) reactor reactivity, 12) theory of the critical homogenous pile, 13) the neutron reflector, 14) the heterogeneous reactor, 15) the equations of the fuel cycle, 16) neutron counter-reactions, 17) reactor kinetics, and 18) calculation methods in neutron scattering

  19. Mirror reactor surface study

    International Nuclear Information System (INIS)

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  20. FBR type reactor

    International Nuclear Information System (INIS)

    A circular neutron reflector is disposed vertically movably so as to surround the outer circumference of a reactor core barrel. A reflector driving device comprises a driving device main body attracted to the outer wall surface of the reactor barrel by electromagnetic attraction force and an inertia body disposed above the driving device main body vertically movably. A reflector is connected below the reactor driving device. At the initial stage, a spontaneous large current is supplied to upper electromagnetic repulsion coils of the reflector driving device, impact electromagnetic repulsion force is caused between the inertia body and the reflector driving device, so that the driving device main body moves downwardly by a predetermined distance and stopped. The reflector driving device can be lowered in a step-like manner to an appropriate position suitable to restart the reactor during stoppage of the reactor core by conducting spontaneous supply of current repeatedly to the upper electromagnetic repulsion coils. (I.N.)

  1. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  2. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  3. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  4. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  5. Multi-purpose reactor

    International Nuclear Information System (INIS)

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MWth, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co60) production capacity is 50000 Ci/yr, 200Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  6. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author)

  7. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

  8. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1983 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  9. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and activities of the Committee on Reactor Physics. (auth.)

  10. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  11. 5 February 2010: Romanian Former Minister of Justice V. Stoica (4th from left) visiting SM18 with, from left to right, University of Bucharest Faculty of Physics A. Costescu, DESY Hamburg C. Diaconu; Mrs Valeriu Stoica; Université de Montpellier II S. Ciulli; Technology Department Vacuum, Surfaces and Coatings group S. Ilie; Technology Department Head F. Bordry and Adviser for Russian Federation, Central and Eastern Europe T. Kurtyka.

    CERN Multimedia

    Maximilien Brice

    2010-01-01

    5 February 2010: Romanian Former Minister of Justice V. Stoica (4th from left) visiting SM18 with, from left to right, University of Bucharest Faculty of Physics A. Costescu, DESY Hamburg C. Diaconu; Mrs Valeriu Stoica; Université de Montpellier II S. Ciulli; Technology Department Vacuum, Surfaces and Coatings group S. Ilie; Technology Department Head F. Bordry and Adviser for Russian Federation, Central and Eastern Europe T. Kurtyka.

  12. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

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

  13. Safety of research reactors

    International Nuclear Information System (INIS)

    The number of research reactors that have been constructed worldwide for civilian applications is about 651. Of the reactors constructed, 284 are currently in operation, 258 are shut down and 109 have been decommissioned. More than half of all operating research reactors worldwide are over thirty years old. During this long period of time national priorities have changed. Facility ageing, if not properly managed, has a natural degrading effect. Many research reactors face concerns with the obsolescence of equipment, lack of experimental programmes, lack of funding for operation and maintenance and loss of expertise through ageing and retirement of the staff. Other reactors of the same vintage maintain effective ageing management programmes, conduct active research programmes, develop and retain high calibre personnel and make important contributions to society. Many countries that operate research reactors neither operate nor plan to operate power reactors. In most of these countries there is a tendency not to create a formal regulatory body. A safety committee, not always independent of the operating organization, may be responsible for regulatory oversight. Even in countries with nuclear power plants, a regulatory regime differing from the one used for the power plants may exist. Concern is therefore focused on one tail of a continuous spectrum of operational performance. The IAEA has been sending missions to review the safety of research reactors in Member States since 1972. Some of the reviews have been conducted pursuant to the IAEA' functions and responsibilities regarding research reactors that are operated within the framework of Project and Supply Agreements between Member States and the IAEA. Other reviews have been conducted upon request. All these reviews are conducted following procedures for Integrated Safety Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety

  14. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  15. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  16. Slurry reactor design studies

    Energy Technology Data Exchange (ETDEWEB)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. (Bechtel Group, Inc., San Francisco, CA (USA)); Akgerman, A. (Texas A and M Univ., College Station, TX (USA)); Smith, J.M. (California Univ., Davis, CA (USA))

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  17. FBR type reactor

    International Nuclear Information System (INIS)

    The present invention provides an FBR type reactor in which the combustion of reactor core fuels is controlled by reflectors, and the position of a reflector driving device can be controlled even during shut down of the reactor. Namely, the reflector driving device is attracted to the outer wall surface of a reactor core barrel by electromagnetic attraction force. An inertia body is disposed vertically movably to the upper portion of the reflector driving device. Magnetic repulsive coils generate instantaneous magnetic repulsive force between the inertia body and the reflector driving device. With such a constitution, the reflector driving device can be driven by using magnetic repulsion of the electromagnetic repulsive coils and inertia of the inertia body. As a result, not only the reflectors can be elevated at an ultraslow speed during normal reactor operation, but also fine position adjustment for the reflector driving device, as well as fine position adjustment of the reflectors required upon restart of the reactor can be conducted by lowering the reflector driving device during shut down of the reactor. (I.S.)

  18. Reactor water sampling device

    International Nuclear Information System (INIS)

    The present invention concerns a reactor water sampling device for sampling reactor water in an in-core monitor (neutron measuring tube) housing in a BWR type reactor. The upper end portion of a drain pipe of the reactor water sampling device is attached detachably to an in-core monitor flange. A push-up rod is inserted in the drain pipe vertically movably. A sampling vessel and a vacuum pump are connected to the lower end of the drain pipe. A vacuum pump is operated to depressurize the inside of the device and move the push-up rod upwardly. Reactor water in the in-core monitor housing flows between the drain pipe and the push-up rod and flows into the sampling vessel. With such a constitution, reactor water in the in-core monitor housing can be sampled rapidly with neither opening the lid of the reactor pressure vessel nor being in contact with air. Accordingly, operator's exposure dose can be reduced. (I.N.)

  19. Test reactor technology

    International Nuclear Information System (INIS)

    The Reactor Development Program created a need for engineering testing of fuels and materials. The Engineering Test Reactors were developed around the world in response to this demand. The design of the test reactors proved to be different from that of power reactors, carrying the fuel elements closer to the threshold of failure, requiring more responsive instrumentation, more rapid control element action, and inherent self-limiting behavior under accident conditions. The design of the experimental facilities to exploit these reactors evolved a new, specialized, branch of engineering, requiring a very high-lvel scientific and engineering team, established a meticulous concern with reliability, the provision for recovery from their own failures, and detailed attention to possible interactions with the test reactors. This paper presents this technology commencing with the Materials Testing Reactor (MTR) through the Fast Flux Test Facility, some of the unique experimental facilities developed to exploit them, but discusses only cursorily the experiments performed, since sample preparation and sample analyses were, and to some extent still are, either classified or proprietary. The Nuclear Engineering literature is filled with this information

  20. Advanced reactor licensing issues

    International Nuclear Information System (INIS)

    In July 1986 the US Nuclear Regulatory Commission issued a Policy Statement on the Regulation of Advanced Nuclear Power Plants. As part of this policy advanced reactor designers were encouraged to interact with NRC early in the design process to obtain feedback regarding licensing requirements for advanced reactors. Accordingly, the staff has been interacting with the Department of Energy (DOE) and its contractors on the review of three advanced reactor conceptual designs: one modular High Temperature Gas-Cooled Reactor (MHTGR) and two Liquid Metal Reactors (LMRs). As a result of these interactions certain safety issues associated with these advanced reactor designs have been identified as key to the licensability of the designs as proposed by DOE. The major issues in this regard are: (1) selection and treatment of accident scenarios; (2) selection of siting source term; (3) performance and reliability of reactor shutdown and decay heat removal systems; (4) need for conventional containment; (5) need for conventional emergency evacuation; (6) role of the operator; (7) treatment of balance of plant; and (8) modular approach. This paper provides a status of the NRC review effort, describes the above issues in more detail and provides the current status and approach to the development of licensing guidance on each

  1. Nuclear reactor power monitor

    International Nuclear Information System (INIS)

    The device of the present invention monitors phenomena occurred in a nuclear reactor more accurately than usual case. that is, the device monitors a reactor power by signals sent from a great number of neutron monitors disposed in the reactor. The device has a means for estimating a phenomenon occurred in the reactor based on the relationship of a difference of signals between each of the great number of neutron monitors to the positions of the neutron monitors disposed in the reactor. The estimation of the phenomena is conducted by, for example, conversion of signals sent from the neutron monitors to a code train. Then, a phenomenon is estimated rapidly by matching the code train described above with a code train contained in a data base. Further. signals sent from the neutron monitors are processed statistically to estimate long term and periodical phenomena. As a result, phenomena occurred in the reactor are monitored more accurately than usual case, thereby enabling to improve reactor safety and operationability. (I.S.)

  2. Reactor Sharing Program

    International Nuclear Information System (INIS)

    Support utilization of the RINSC reactor for student and faculty instructions and research. The Department of Energy award has provided financial assistance during the period 9/29/1995 to 5/31/2001 to support the utilization of the Rhode Island Nuclear Science Center (RINSC) reactor for student and faculty instruction and research by non-reactor owning educational institutions within approximately 300 miles of Narragansett, Rhode Island. Through the reactor sharing program, the RINSC (including the reactor and analytical laboratories) provided reactor services and laboratory space that were not available to the other universities and colleges in the region. As an example of services provided to the users: Counting equipment, laboratory space, pneumatic and in-pool irradiations, demonstrations of sample counting and analysis, reactor tours and lectures. Funding from the Reactor Sharing Program has provided the RINSC to expand student tours and demonstration programs that emphasized our long history of providing these types of services to the universities and colleges in the area. The funding have also helped defray the cost of the technical assistance that the staff has routinely provided to schools, individuals and researchers who have called on the RINSC for resolution of problems relating to nuclear science. The reactor has been featured in a Public Broadcasting System documentary on Pollution in the Arctic and how a University of Rhode Island Professor used Neutron Activation Analysis conducted at the RINSC to discover the sources of the ''Arctic Haze''. The RINSC was also featured by local television on Earth Day for its role in environmental monitoring

  3. Determination of research reactor safety parameters by reactor calculations

    International Nuclear Information System (INIS)

    Main research reactor safety parameters such as power density peaking factors, shutdown margin and temperature reactivity coefficients are treated. Reactor physics explanation of the parameters is given together with their application in safety evaluation performed as part of research reactor operation. Reactor calculations are presented as a method for their determination assuming use of widely available computer codes. (author)

  4. Reactor de plasma

    OpenAIRE

    Erra Serrabasa, Pilar; Molina Mansilla, Ricardo; Beltrán Serra, Eric

    2008-01-01

    Reactor de plasma. Se trata de un reactor de plasma que puede trabajar en un amplio rango de presión, desde el vacío y presiones reducidas hasta la presión atmosférica y presiones superiores. Adicionalmente el reactor de plasma tiene la capacidad de regular otros parámetros importantes y permite su uso para el tratamiento de muestras de tipología muy diversa, como por ejemplo las de tamaño relativamente grande o de superficie rugosa.

  5. Integral nuclear reactor

    International Nuclear Information System (INIS)

    The invention deals with an inprovement of the design of an integral pressurized water nuclear reactor. A typical embodyment of the invention includes a generally cylindrical pressure vessel that is assembled from three segments which are bolted together at transverse joints to form a pressure tight unit that encloses the steam generator and the reactor. The new construction permits primary to secondary coolant heat exchange and improved control rod drive mecanisms which can be exposed for full service access during reactor core refueling, maintenance and inspection

  6. Microfluidic electrochemical reactors

    Science.gov (United States)

    Nuzzo, Ralph G.; Mitrovski, Svetlana M.

    2011-03-22

    A microfluidic electrochemical reactor includes an electrode and one or more microfluidic channels on the electrode, where the microfluidic channels are covered with a membrane containing a gas permeable polymer. The distance between the electrode and the membrane is less than 500 micrometers. The microfluidic electrochemical reactor can provide for increased reaction rates in electrochemical reactions using a gaseous reactant, as compared to conventional electrochemical cells. Microfluidic electrochemical reactors can be incorporated into devices for applications such as fuel cells, electrochemical analysis, microfluidic actuation, pH gradient formation.

  7. Licensed operating reactors

    International Nuclear Information System (INIS)

    The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

  8. First Algerian research reactor

    International Nuclear Information System (INIS)

    In 1985, both the Algerian Commissariat of New Energies and the Argentine National Atomic Energy Commission plus the firm INVAP S.E., started a series of mutual visits aimed at defining the mechanisms for cooperation in the nuclear field. Within this framework, a commercial contract was undersigned covering the supply of a low-power reactor (RUN), designed for basic and applied research in the fields of reactor physics and nuclear engineering. The reactor may also be used for performing experiences with neutron beams, for the irradiation of several materials and for the training of technicians, scientists and operators

  9. Course on reactor physics

    International Nuclear Information System (INIS)

    In Germany only few students graduate in nuclear technology, therefore the NPP operating companies are forced to develop their own education and training concepts. AREVA NP has started together with the Technical University of Dresden a one-week course ''reactor physics'' that includes the know-how of the nuclear power plant construction company. The Technical University of Dresden has the training reactor AKR-2 that is retrofitted by modern digital instrumentation and control technology that allows the practical training of reactor control.

  10. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts

  11. Nuclear reactor theory

    International Nuclear Information System (INIS)

    This textbook is composed of two parts. Part 1 'Elements of Nuclear Reactor Theory' is composed of only elements but the main resource for the lecture of nuclear reactor theory, and should be studied as common knowledge. Much space is therefore devoted to the history of nuclear energy production and to nuclear physics, and the material focuses on the principles of energy production in nuclear reactors. However, considering the heavy workload of students, these subjects are presented concisely, allowing students to read quickly through this textbook. (J.P.N.)

  12. PWR type reactor

    International Nuclear Information System (INIS)

    From a PWR with a primary circuit, consisting of a reactor pressure vessel, a steam generator and a reactor coolant pump, hot coolant is removed by means of an auxiliary system containing h.p. pumps for feeding water into the primary circuit and being connected with a pipe, originating at the upper part, which has got at least one isolating value. This is done by opening an outlet in a part of the auxiliary system that has got a lower pressure than the reactor vessel. Preferably a water jet pump is used for mixing with the water of the auxiliary system. (orig.)

  13. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the behaviour of fusion reactor materials and components during and after irradiation. Ongoing projects include: the study of the mechanical behaviour of structural materials under neutron irradiation; the investigation of the characteristics of irradiated first wall material such as beryllium; the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; and the study of dismantling and waste disposal strategy for fusion reactors. Progress and achievements in these areas in 2000 are discussed

  14. International tokamak reactor

    International Nuclear Information System (INIS)

    Since 1978, the US, the European Communities, Japan, and the Soviet Union have collaborated on the definition, conceptual design, data base assessment, and analysis of critical technical issues for a tokamak engineering test reactor, called the International Tokamak Reactor (INTOR). During 1985-1986, this activity has been expanded in scope to include evaluation of concept innovations that could significantly improve the tokamak as a commercial reactor. The purposes of this paper are to summarize the present INTOR design concept and to summarize the work on concept innovations

  15. Joyo experimental reactor tour

    International Nuclear Information System (INIS)

    JAEA cooperation in remote monitoring focuses on the Joyo Experimental Reactor at the O'arai Research and Development Center. Joyo performs irradiation of test fuels to support development of the fast reactor cycle in Japan, both in international cooperation and in support of the Monju fast reactor, which is now undergoing reconstruction. The tour included an introduction at the model, a visit to the control room, entry into the containment vessel, and viewing of remote monitoring equipment in the Fresh Fuel Storage and at one of the Spent Fuel Ponds. (author)

  16. Fast Breeder Reactor studies

    Energy Technology Data Exchange (ETDEWEB)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

  17. nuclear reactor design calculations

    International Nuclear Information System (INIS)

    In this work , the sensitivity of different reactor calculation methods, and the effect of different assumptions and/or approximation are evaluated . A new concept named error map is developed to determine the relative importance of different factors affecting the accuracy of calculations. To achieve this goal a generalized, multigroup, multi dimension code UAR-DEPLETION is developed to calculate the spatial distribution of neutron flux, effective multiplication factor and the spatial composition of a reactor core for a period of time and for specified reactor operating conditions. The code also investigates the fuel management strategies and policies for the entire fuel cycle to meet the constraints of material and operating limitations

  18. Nuclear reactor internal structures

    International Nuclear Information System (INIS)

    The upper internal structures of the reactor are connected to the closing head so as to be readily removed with the latter and a skirt connected to the lower portion of said upper structures so as to surround the latter, extends under the control rods when they are removed from the reactor core. Through such an arrangement the skirt protects the control rods and supports the vessel closing-head and the core upper structures, whenever the head is severed from the vessel and put beside the latter in order to discharge the reactor

  19. Reactor monitoring system

    International Nuclear Information System (INIS)

    The present invention concerns a device for monitoring the inside of an FBR type reactor which can not be monitored by a usual optical camera. An ultrasonic camera having an excellent propagating property in a liquid metal sodium is scanned, and reflected waves of the ultrasonic waves are received as signals. The signals are processed by using a virtual realistic feeling (VR) technique such as a head mounting type image display (HMD) and a three dimensional pointing device. With such procedures, the inside of the FBR type reactor can be observed with such a realistic feeling that the inside of the FBR type reactor were seen directly. (I.S.)

  20. Research reactor support

    International Nuclear Information System (INIS)

    Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

  1. Study of power reactor dynamics by stochastic reactor oscillator method

    International Nuclear Information System (INIS)

    Stochastic reactor oscillator and cross correlation method were used for determining reactor dynamics characteristics. Experimental equipment, fast reactor oscillator (BOR-1) was activated by random pulses from the GBS-16 generator. Tape recorder AMPEX-SF-300 and data acquisition tool registered reactor response to perturbations having different frequencies. Reactor response and activation signals were cross correlated by digital computer for different positions of stochastic oscillator and ionization chamber

  2. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    An improved nuclear power reactor fuel element is described which consists of fuel rods, rod guide tubes and an end plate. The system allows direct access to an end of each fuel rod for inspection purposes. (U.K.)

  3. Reactor power control device

    International Nuclear Information System (INIS)

    The present invention concerns a method of controlling reactor power to shift it into a partial power operation upon occurrence of recycling pump tripping or loss of generator load. Operation state of a reactor is classified into a plurality of operation states based on values of the reactor core flow rate and the reactor power. Different insertion patterns for selected control rods are determined on every classified operation states. Then, an insertion pattern corresponding to the operation state upon occurrence of recycling pump tripping or loss of power generator load is carried out to shift into partial power operation. The operation is shifted to a load operation solely in the station while avoiding risks such as TPM scram. Then neutron fluxes are suppressed upon transient to increase margin of fuel integrity. Selected control rod pattern of the optimum reactivity is set to each of operation regions, thereby enabling to conduct flexible countermeasure so as to attain optimum operationability. (N.H.)

  4. Reactor pressure boundary materials

    International Nuclear Information System (INIS)

    With a long-term operation of nuclear power plants, the component materials are degraded under severe reactor conditions such as neutron irradiation, high temperature, high pressure and corrosive environment. It is necessary to establish the reliable and practical technologies for improving and developing the component materials and for evaluating the mechanical properties. Especially, it is very important to investigate the technologies for reactor pressure boundary materials such as reactor vessel and pipings in accordance with their critical roles. Therefore, this study was focused on developing and advancing the microstructural/micro-mechanical evaluation technologies, and on evaluating the neutron irradiation characteristics and radiation effects analysis technology of the reactor pressure boundary materials, and also on establishing a basis of nuclear material property database

  5. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

  6. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

  7. Reactor parameter simulation system

    International Nuclear Information System (INIS)

    A reactor parameter simulation system (RPSS) has been built with the capability of analyzing any reactor signals, decomposing those signals into their deterministic and stochastic components, then reconstructing new, simulated signals that possess the same statistical and correlation structure as the original plant variables. Important uses of the RPSS are for integration with reactor simulation software to provide tools for plant control strategy development, and for safety-study investigations of scenarios that can arise involving signal faults generated from degraded sensors. A third use of the RPSS is for frequency-domain filtering of reactor process variables contaminated with serially correlated noise, which is important for our ongoing development of expert systems for sensor-operability surveillance. 5 refs., 4 figs., 3 tabs

  8. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

  9. 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).

  10. Nuclear reactor fuel assembly

    International Nuclear Information System (INIS)

    A fuel assembly construction for liquid metal cooled fast breeder reactors is described in which the sub-assemblies carry a smaller proportion of parasitic material than do conventional sub-assemblies. (U.K.)

  11. Ageing of research reactors

    International Nuclear Information System (INIS)

    Historically, many of the research institutions were centred on a research reactor facility as main technological asset and major source of neutrons for research. Important achievements were made in time in these research institutions for development of nuclear materials technology and nuclear safety for nuclear energy. At present, ageing of nuclear research facilities among these research reactors and ageing of staff are considerable factors of reduction of competence in research centres. The safe way of mitigation of this trend deals with ageing management by so called, for power reactors, Plant Life Management and new investments in staff as investments in research, or in future resources of competence. A programmatic approach of ageing of research reactors in correlation with their actual and future utilisation, will be used as a basis for safety evaluation and future spending. (author)

  12. Experience with Kamini reactor

    International Nuclear Information System (INIS)

    Kamini is a 233U fuelled, 30 kW(th) research reactor. It is one of the best neutron source facility with a core average flux of 1012 n/cm2/s in IGCAR used for neutron radiography of active and nonradioactive objects, activation analysis and radiation physics research. The core consists of nine plate type fuel elements with a total fuel inventory of 590 g of 233U. Two safety control plates made of cadmium are used for start up and shutdown of the reactor. Three beam tubes, two-thimble irradiation site outside reflector and one irradiation site nearer to the core constitute the testing facilities of Kamini. Kamini attained first criticality on 29th October 96 and nominal power of 30 kW in September 1997. This paper covers the design features of the reactor, irradiation facilities and their utilities and operating experience of the reactor. (author)

  13. Dossier: research reactors

    International Nuclear Information System (INIS)

    Research reactors are used at the CEA (the French atomic energy commission) since many years. Their number has been reduced but they remain unique tools that CEA valorize continuously. The results of the programs involving such reactors are of prime importance for the operation of Electricite de France (EdF) park of existing power plants but also for the design of future nuclear power plants and future research reactors. This dossier presents three examples of research reactors in use at the CEA: Osiris and Orphee (CEA-Saclay), devoted to nuclear energy and fundamental research, respectively, and the critical mockups Eole, Minerve and Masurca (CEA-Cadarache) devoted to nuclear data libraries and neutronic calculation. (J.S.)

  14. Reactor vessel sealing plug

    International Nuclear Information System (INIS)

    This invention relates to an apparatus and method for sealing the cold leg nozzles of a nuclear reactor pressure vessel from a remote location during maintenance and inspection of associated steam generators and pumps while the pressure vessel and refueling canal are filled with water. The apparatus includes a sealing plug for mechanically sealing the cold leg nozzle from the inside of a reactor pressure vessel. The sealing plugs include a primary and a secondary O-ring. An installation tool is suspended within the reactor vessel and carries the sealing plug. The tool telescopes to insert the sealing plug within the cold leg nozzle, and to subsequently remove the plug. Hydraulic means are used to activate the sealing plug, and support means serve to suspend the installation tool within the reactor vessel during installation and removal of the sealing plug

  15. Future Reactor Experiments

    CERN Document Server

    He, Miao

    2013-01-01

    The measurement of the neutrino mixing angle $\\theta_{13}$ opens a gateway for the next generation experiments to measure the neutrino mass hierarchy and the leptonic CP-violating phase. Future reactor experiments will focus on mass hierarchy determination and the precision measurement of mixing parameters. Mass hierarchy can be determined from the disappearance of reactor electron antineutrinos based on the interference effect of two separated oscillation modes. Relative and absolute measurement techniques have been explored. A proposed experiment JUNO, with a 20 kton liquid scintillator detector of $3%/$$\\sqrt{E(MeV)}$ energy resolution, $\\sim$ 53 km far from reactors of $\\sim$ 36 GW total thermal power, can reach to a sensitivity of $\\Delta\\chi^{2}>16$ considering the spread of reactor cores and uncertainties of the detector response. Three of mixing parameters are expected to be measured to better than 1% precision. There are multiple detector options for JUNO under investigation. The technical challenges...

  16. Reactor hot spot analysis

    Energy Technology Data Exchange (ETDEWEB)

    Vilim, R.B.

    1985-08-01

    The principle methods for performing reactor hot spot analysis are reviewed and examined for potential use in the Applied Physics Division. The semistatistical horizontal method is recommended for future work and is now available as an option in the SE2-ANL core thermal hydraulic code. The semistatistical horizontal method is applied to a small LMR to illustrate the calculation of cladding midwall and fuel centerline hot spot temperatures. The example includes a listing of uncertainties, estimates for their magnitudes, computation of hot spot subfactor values and calculation of two sigma temperatures. A review of the uncertainties that affect liquid metal fast reactors is also presented. It was found that hot spot subfactor magnitudes are strongly dependent on the reactor design and therefore reactor specific details must be carefully studied. 13 refs., 1 fig., 5 tabs.

  17. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given

  18. Research Reactor Benchmarks

    International Nuclear Information System (INIS)

    A criticality benchmark experiment performed at the Jozef Stefan Institute TRIGA Mark II research reactor is described. This experiment and its evaluation are given as examples of benchmark experiments at research reactors. For this reason the differences and possible problems compared to other benchmark experiments are particularly emphasized. General guidelines for performing criticality benchmarks in research reactors are given. The criticality benchmark experiment was performed in a normal operating reactor core using commercially available fresh 20% enriched fuel elements containing 12 wt% uranium in uranium-zirconium hydride fuel material. Experimental conditions to minimize experimental errors and to enhance computer modeling accuracy are described. Uncertainties in multiplication factor due to fuel composition and geometry data are analyzed by sensitivity analysis. The simplifications in the benchmark model compared to the actual geometry are evaluated. Sample benchmark calculations with the MCNP and KENO Monte Carlo codes are given

  19. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author)

  20. Reactor Neutrino Spectra

    CERN Document Server

    Hayes, A C

    2016-01-01

    We present a review of the antineutrino spectra emitted from reactors. Knowledge of these and their associated uncertainties are crucial for neutrino oscillation studies. The spectra used to-date have been determined by either conversion of measured electron spectra to antineutrino spectra or by summing over all of the thousands of transitions that makeup the spectra using modern databases as input. The uncertainties in the subdominant corrections to beta-decay plague both methods, and we provide estimates of these uncertainties. Improving on current knowledge of the antineutrino spectra from reactors will require new experiments. Such experiments would also address the so-called reactor neutrino anomaly and the possible origin of the shoulder observed in the antineutrino spectra measured in recent high-statistics reactor neutrino experiments.

  1. Pulsed fusion reactors

    International Nuclear Information System (INIS)

    This summer school specialized in examining specific fusion center systems. Papers on scientific feasibility are first presented: confinement of high-beta plasma, liners, plasma focus, compression and heating and the use of high power electron beams for thermonuclear reactors. As for technological feasibility, lectures were on the theta-pinch toroidal reactors, toroidal diffuse pinch, electrical engineering problems in pulsed magnetically confined reactors, neutral gas layer for heat removal, the conceptual design of a series of laser fusion power plants with ''Saturn'', implosion experiments and the problem of the targets, the high brightness lasers for plasma generation, and topping and bottoming cycles. Some problems common to pulsed reactors were examined: energy storage and transfer, thermomechanical and erosion effects in the first wall and blanket, the problems of tritium production, radiation damage and neutron activation in blankets, and the magnetic and inertial confinement

  2. Reactor fueling of BWR type reactors

    International Nuclear Information System (INIS)

    Purpose: To enable the pattern exchange for control rods during burning in Control Cell Core type BWR reactors. Constitution: A plurality of control cells are divided into a plurality of groups such that the control cells is aparted from each other by way of at least two fuel assemblies other than the control cells with respect to the vertical and lateral directions of the reactor core cross section, as well as they are in adjacent with control cells of other groups with respect to the orthogonal direction. This enables to perform the pattern exchange for the control rods during burning in the control cell core with ease, and the control blade and the story effect harmful to the mechanical soundness of fuels can thus be suppressed. (Moriyama, K.)

  3. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in fiscal 1974 in Reactor Engineering Division of eight laboratories and computing center are described. Works in the division are closely related with the development of a multi-purpose High-temperature Gas Cooled Reactor, the development of a Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation, and engineering of thermonuclear fusion reactors. They cover nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and aspects of the computing center. (auth.)

  4. Special lecture on nuclear reactor

    International Nuclear Information System (INIS)

    This book gives a special lecture on nuclear reactor, which is divided into two parts. The first part has explanation on nuclear design of nuclear reactor and analysis of core with theories of integral transports, diffusion Nodal, transports Nodal and Monte Carlo skill parallel computer and nuclear calculation and speciality of transmutation reactor. The second part deals with speciality of nuclear reactor and control with nonlinear stabilization of nuclear reactor, nonlinear control of nuclear reactor, neural network and control of nuclear reactor, control theory of observer and analysis method of Adomian.

  5. The replacement research reactor

    International Nuclear Information System (INIS)

    The contract for the design, construction and commissioning of the Replacement Research Reactor was signed in July 2000. This was followed by the completion of the detailed design and an application for a construction licence was made in May 2001. This paper will describe the main elements of the design and their relation to the proposed applications of the reactor. The future stages in the project leading to full operation are also described

  6. OECD Halden reactor project

    International Nuclear Information System (INIS)

    This report summarizes the activities of the OECD Halden Reactor Project for the year 1976. The main items reported on are: a) the process supervision and control which have focused on core monitoring and control, and operator-process communication; b) the fuel performance and safety behavior which have provided data and analytical descriptions of the thermal, mechanical and chemical behavior of fuel under various operating conditions; c) the reactor operations and d) the administration and finance

  7. Nuclear reactor fuel elements

    International Nuclear Information System (INIS)

    A nuclear reactor fuel element comprising a column of vibration compacted fuel which is retained in consolidated condition by a thimble shaped plug. The plug is wedged into gripping engagement with the wall of the sheath by a wedge. The wedge material has a lower coefficient of expansion than the sheath material so that at reactor operating temperature the retainer can relax sufficient to accommodate thermal expansion of the column of fuel. (author)

  8. Small reactor return

    International Nuclear Information System (INIS)

    Current state of the development of present-day small reactors in different countries is performed. Various designs of low and middle power reactors, among which are CAREM (25 MW, PWR), KLT-40 (40 MW, PWR), MRX (30 MW, PWR), IRIS (50 MW, PWR), SMART (1000 MW, PWR), Modular SBWR (50 MW, BWR), PBMR (120 MW, HTGR), GT-HMR (285 MW, HTGR), are discussed

  9. Reactor lattice transport calculations

    International Nuclear Information System (INIS)

    The present lecture is a continuation of the lecture on Introduction to the Neutron Transport Phenomena. It comprises three aspects of lattice calculations. First the idea of a reactor lattice is introduced. Then the main definitions used in reactor lattice analysis are given, and finally two basic methods applied for solution of the transport equations are defined. Several remarks on secondary results from lattice transport calculations are added. (author)

  10. Thermal or epithermal reactor

    International Nuclear Information System (INIS)

    In a thermal or epithermal heavy-water reactor of the pressure tube design the reactivity is to be increased by different means: replacement of the moderator by additional rods with heavy metal in the core or in the reflector; separation of the moderator (heavy water) from the coolant (light water) by means of shroud tubes. In light-water reactor types neutron losses are to be influenced by using the heavy elements in different configurations. (orig./PW)

  11. Future reactor experiments

    International Nuclear Information System (INIS)

    The non-zero neutrino mixing angle θ13 has been discovered and precisely measured by the current generation short-baseline reactor neutrino experiments. It opens the gate of measuring the leptonic CP-violating phase and enables the neutrino mass ordering. The JUNO and RENO-50 proposals aim at resolving the neutrino mass ordering using reactors. The experiment design, physics sensitivity, technical challenges as well as the progresses of those two proposed experiments are reviewed in this paper

  12. Water cooled nuclear reactor

    International Nuclear Information System (INIS)

    The description is given of a water cooled nuclear reactor comprising a core, cooling water that rises through the core, vertical guide tubes located inside the core and control rods vertically mobile in the guide tubes. In this reactor the cooling water is divided into a first part introduced at the bottom end of the core and rising through it and a second part introduced at the top end of the guide tubes so as to drop in them

  13. Jet-Stirred Reactors

    OpenAIRE

    Herbinet, Olivier; Guillaume, Dayma

    2013-01-01

    The jet-stirred reactor is a type of ideal continuously stirred-tank reactor which is well suited for gas phase kinetic studies. It is mainly used to study the oxidation and the pyrolysis of hydrocarbon and oxygenated fuels. These studies consist in recording the evolution of the conversion of the reactants and of the mole fractions of reaction products as a function of different parameters such as reaction temperature, residence time, pressure and composition of the inlet gas. Gas chromatogr...

  14. Generation IV reactors: economics

    International Nuclear Information System (INIS)

    The operating nuclear reactors were built over a short period: no more than 10 years and today their average age rounds 18 years. EDF (French electricity company) plans to renew its reactor park over a far longer period : 30 years from 2020 to 2050. According to EDF this objective implies 3 constraints: 1) a service life of 50 to 60 years for a significant part of the present operating reactors, 2) to be ready to built a generation 3+ unit in 2020 which infers the third constraint: 3) to launch the construction of an EPR (European pressurized reactor) prototype as soon as possible in order to have it operating in 2010. In this scheme, generation 4 reactor will benefit the feedback experience of generation 3 and will take over in 2030. Economic analysis is an important tool that has been used by the generation 4 international forum to select the likely future reactor systems. This analysis is based on 4 independent criteria: the basic construction cost, the construction time, the operation and maintenance costs and the fuel cycle cost. This analysis leads to the evaluation of the global cost of electricity generation and of the total investment required for each of the reactor system. The former defines the economic competitiveness in a de-regulated energy market while the latter is linked to the financial risk taken by the investor. It appears, within the limits of the assumptions and models used, that generation 4 reactors will be characterized by a better competitiveness and an equivalent financial risk when compared with the previous generation. (A.C.)

  15. Future reactor experiments

    Science.gov (United States)

    Wen, Liangjian

    2015-07-01

    The non-zero neutrino mixing angle θ13 has been discovered and precisely measured by the current generation short-baseline reactor neutrino experiments. It opens the gate of measuring the leptonic CP-violating phase and enables the neutrino mass ordering. The JUNO and RENO-50 proposals aim at resolving the neutrino mass ordering using reactors. The experiment design, physics sensitivity, technical challenges as well as the progresses of those two proposed experiments are reviewed in this paper.

  16. Department of Reactor Technology

    DEFF Research Database (Denmark)

    Risø National Laboratory, Roskilde

    The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included.......The general development of the Department of Reactor Technology at Risø during 1981 is presented, and the activities within the major subject fields are described in some detail. Lists of staff, publications, and computer programs are included....

  17. AVR reactor physics

    International Nuclear Information System (INIS)

    A process for reactivity control was developed and used for fuelling the AVR reactor core, which is largely based on experimentally determined values. By adding fuel elements with different quantities of heavy metals paired with various experimental requirements, great demands were made of reactivity control. Although only a small range of control was available, this was sufficient to operate the reactor and to shut it down safely in the required power and temperature range. (orig.)

  18. Moon base reactor system

    Science.gov (United States)

    Chavez, H.; Flores, J.; Nguyen, M.; Carsen, K.

    1989-01-01

    The objective of our reactor design is to supply a lunar-based research facility with 20 MW(e). The fundamental layout of this lunar-based system includes the reactor, power conversion devices, and a radiator. The additional aim of this reactor is a longevity of 12 to 15 years. The reactor is a liquid metal fast breeder that has a breeding ratio very close to 1.0. The geometry of the core is cylindrical. The metallic fuel rods are of beryllium oxide enriched with varying degrees of uranium, with a beryllium core reflector. The liquid metal coolant chosen was natural lithium. After the liquid metal coolant leaves the reactor, it goes directly into the power conversion devices. The power conversion devices are Stirling engines. The heated coolant acts as a hot reservoir to the device. It then enters the radiator to be cooled and reenters the Stirling engine acting as a cold reservoir. The engines' operating fluid is helium, a highly conductive gas. These Stirling engines are hermetically sealed. Although natural lithium produces a lower breeding ratio, it does have a larger temperature range than sodium. It is also corrosive to steel. This is why the container material must be carefully chosen. One option is to use an expensive alloy of cerbium and zirconium. The radiator must be made of a highly conductive material whose melting point temperature is not exceeded in the reactor and whose structural strength can withstand meteor showers.

  19. BWR type nuclear reactor

    International Nuclear Information System (INIS)

    Purpose: To simplify the structure of an emergency core cooling system while suppressing the flow out of coolants upon rapture accidents in a coolant recycling device of BWR type reactors. Constitution: Recirculation pumps are located at a position higher than the reactor core in a pressure vessel, and the lower plenum is bisected vertically by a partition plate. Further, a gas-liquid separator is surrounded with a wall and the water level at the outer side of the wall is made higher than the water level in the inside of the wall. In this structure, coolants are introduced from the upper chamber in the lower plenum into the reactor core, and the steams generated in the reactor core are separated in the gas-liquid separator, whereby the separated liquid is introduced as coolants by way of the inner chamber into the lower chamber of the lower plenum and further sent by way of the outer chamber into the reactor core. Consequently, idle rotation of the recycling pumps due to the flow-in of saturated water is prevented and loss of coolants in the reactor core can also be prevented upon raptures in the pipeway and the driving section of the pump connected to the pressure vessel and in the bottom of the pressure vessel. (Horiuchi, T.)

  20. Emergency reactor scram system

    International Nuclear Information System (INIS)

    The present invention provides an emergency reactor scram system capable of shut down a reactor safely upon occurrence of pump trip by improving a passive scram performance for an FBR-type reactor. Namely, a driving motor and an electric generator are connected to a main pump of a primary system. An AC/DC convertor is connected to the electric generator. A shielding plug is disposed to the upper end opening of a reactor container, a control rod drive mechanism is erected on the shielding plug, and an extension pipe is attached to scram magnets of the control rod drive mechanism. The extension pipe is connected to a control rod. The rotation of the shaft of the pump is used as a direct rotator to provide an integrated-type electric generator. The electric generator is electrically connected with the power source of a scram magnet of the emergency scram system. Accordingly, the control rod of the emergency scram system is automatically and rapidly inserted to the reactor core using the power source of the electric generator upon trip of the main pump thereby enabling to scram the reactor safely. (I.S.)

  1. A modular reactor plant

    International Nuclear Information System (INIS)

    This paper describes a new concept in liquid metal reactors that is being developed by General Electric under contract to the Department of Energy. This concept is called the Modular Reactor Plant. While this effort is not expected to have a near-term impact, it is directed toward three principal issues currently affecting nuclear power in the United States. First, plant costs have escalated to the point where the startup of new plants require large electric rate increases. Second, the cost of new plants coming on-line today vary by as much as a factor of three. And, third, nuclear construction times often exceed the utilities prudent planning cycle. This paper describes how General Electric's Modular Reactor Plant addreses these issues through shop fabrication and assembly, rail shipment to the site for rapid installation of nuclear components and inherent reactor protection. In addition, it is expected the modular reactor plant will reduce the current cost of development and demonstration of liquid metal reactors to an affordable level

  2. New fission reactor designs

    International Nuclear Information System (INIS)

    A number of critical challenges to the expanded or continued use of nuclear power have developed. These can be categorized as: regulatory restrictions and complications; negative public attitudes; plant complexity; plant life, operations, and maintenance; uncertain load growth, financing; waste management. Solutions to these challenges through advanced reactor design centre around four key technical responses. Passive safety systems are being introduced which use the laws of physics to provide emergency reactor coding, control and shutdown thus eliminating the possibility of human error. Modular construction promises cuts in costs and construction time by shifting the major part of component manufacture from the site to the factory. Standardization also cuts capital costs and in addition operations and repair costs and expedites reactor licensing. Improvements to the fuel cycle include improved fuel types, designs and fabrication, and the reprocessing of and recycling spent fuel back into energy production, thus extending uranium resources and offering a partial solution to the problem of waste disposal. Examples of evolutionary and advanced water-cooled reactors, modular high temperature gas-cooled reactors, and advanced liquid metal cooled fast breeder reactors which are being developed round the world are presented. (author)

  3. OECD Halden reactor project

    International Nuclear Information System (INIS)

    This is the nineteenth annual Report on the OECD Halden Reactor Project, describing activities at the Project during 1978, the last year of the 1976-1978 Halden Agreement. Work continued in two main fields: test fuel irradiation and fuel research, and computer-based process supervision and control. Project research on water reactor fuel focusses on various aspects of fuel behavior under normal, and off-normal transient conditions. In 1978, participating organisations continued to submit test fuel for irradiation in the Halden boiling heavy-water reactor, in instrumented test assemblies designed and manufactured by the Project. Work included analysis of the impact of fuel design and reactor operating conditions on fuel cladding behavior. Fuel performance modelling included characterization of thermal and mechanical behavior at high burn-up, of fuel failure modes, and improvement of data qualification procedures to reduce and quantify error bands on in-reactor measurements. Instrument development yielded new or improved designs for measuring rod temperature, internal pressure, axial neutron flux shape determination, and for detecting cladding defects. Work on computer-based methods of reactor supervision and control included continued development of a system for predictive core surveillance, and of special mathematical methods for core power distribution control

  4. Reactor power measuring device

    International Nuclear Information System (INIS)

    The device of the present invention efficiently calibrates a fixed type gamma ray thermometer of a reactor power measuring device of a BWR type reactor. Namely, the device of the present invention calculates peripheral fuel rod power distribution by calibrating the reactor power distribution by heat generation amount, the reactor power distribution being obtained by a calculation based on a reactor model for converting the signals of a plurality of the gamma ray thermometers in the reactor core based on a conversion formula. In this case, the conversion formula is a relational formula between the power of a thermocouple of the gamma ray thermometer, gamma ray heat generation amount, thermocouple zero power sensitivity relative to a temperature coefficient. A conversion efficient calculation means makes a calibration heater to generate heat at a predetermined power, and the thermocouple zero power sensitivity and the temperature coefficient are obtained based on the output of the gamma ray thermometer in this case. The calibration means updates to conversion type thermocouple zero power sensitivity and temperature coefficient. A calibration execution means executes the operations described above successively, and when the thermocouple zero power sensitivity and the temperature coefficient are out of an allowable range, the means informs it and eliminates the corresponding gamma ray thermometer from the measuring meters. (I.S.)

  5. Reactor safety engineering

    International Nuclear Information System (INIS)

    The concept of the work is such that the basic safety philosophy for nuclear power plants as well as the safety features of both types of light water reactors, pressurized and boiling water reactors, and of the fast breeder reactor are dealt with. With the pressurized and boiling water reactors also variations, due to different supplies are mentioned. The state of development considered is characterized by the results of the American reactor safety study having very much influenced the way of presentation and the validity of the information contained. In the introduction the attentive reader is made familiar with the basic traits of safety engineering, the traditional deterministic way of proceeding being supplemented by a detailed illustration of probabilistic means used in the safety analysis. Added to this are comparative descriptions of the individual safety features, their design and mode of operation. There are, e.g., detailed discussion of the emergency core cooling systems, the power supply systems, the reactor protection system, and the containment. Special chapters are attributed to transients with and without the fast shutdown system working and to loss of coolant. The so-called external events are treated somewhat shortly whereas much space is given to core melting problems. The treatment of important events from the safety point of view, including the section on Harrisburg added for reasons of immediate interest, is limited to phenomenological description. (orig.)

  6. Regulations for RA reactor operation

    International Nuclear Information System (INIS)

    Regulations for RA reactor operation are written in accordance with the legal regulations defined by the Law about radiation protection and related legal acts, as well as technical standards according to the IAEA recommendations. The contents of this book include: fundamental data about the reactor; legal regulations for reactor operation; organizational scheme for reactor operation; general and detailed instructions for operation, behaviour in the reactor building, performing experiments; operating rules for operation under steady state and accidental conditions

  7. BUCHAREST HOTEL MARKET IN THE EUROPEAN CONTEXT

    OpenAIRE

    Ioana Cristiana PATRICHI

    2014-01-01

    The European hospitality industry currently sees an increase in all specific indicators, a fact that shows, on one hand, the ability of this sector to overcome the economic turbulences of recent years, but also the real perspectives for future growth. Today’s hotel industry can no longer rely on the traditional growth methods, and needs to prepare for the major confrontation with the next-generation technological developments that generate modern marketing channels but, by default, incur sign...

  8. The reactor Cabri

    International Nuclear Information System (INIS)

    It has become necessary to construct in France a reactor which would permit the investigation of the conditions of functioning of future installations, the choice, the testing and the development of safety devices to be adopted. A water reactor of a type corresponding to the latest CEA constructions in the field of laboratory or university reactors was decided upon: it appeared important to be able to evaluate the risks entailed and to study the possibilities of increasing the power, always demanded by the users; on the other hand, it is particularly interesting to clarify the phenomena of power oscillation and the risks of burn out. The work programme for CABRI will be associated with the work carried out on the American Sperts of the same type, during its construction, very useful contacts were made with the American specialists who designed the se reactors. A brief description of the reactor is given in the communication as well as the work programme for the first years with respect to the objectives up to now envisaged. Rough description of the reactor. CABRI is an open core swimming-pool reactor without any lateral protection, housed in a reinforced building with controlled leakage, in the Centre d'Etudes Nucleaires de Cadarache. It lies alone in the middle of an area whose radius is 300 meters long. Control and measurements equipment stand out on the edge of that zone. It consumes MTR fuel elements. The control-safety rods are propelled by compressed air. The maximum flow rate of cooling circuit is 1500 m3/h. Transient measurements are recorded in a RW330 unit. Aims and work programme. CABRI is meant for: - studies on the safety of water reactors - for the definition of the safety margins under working conditions: research of maximum power at which a swimming-pool reactor may operate with respect to a cooling accident, of local boiling effect on the nuclear behaviour of the reactor, performances of the control and safety instruments under exceptional

  9. REACTOR GROUT THERMAL PROPERTIES

    Energy Technology Data Exchange (ETDEWEB)

    Steimke, J.; Qureshi, Z.; Restivo, M.; Guerrero, H.

    2011-01-28

    Savannah River Site has five dormant nuclear production reactors. Long term disposition will require filling some reactor buildings with grout up to ground level. Portland cement based grout will be used to fill the buildings with the exception of some reactor tanks. Some reactor tanks contain significant quantities of aluminum which could react with Portland cement based grout to form hydrogen. Hydrogen production is a safety concern and gas generation could also compromise the structural integrity of the grout pour. Therefore, it was necessary to develop a non-Portland cement grout to fill reactors that contain significant quantities of aluminum. Grouts generate heat when they set, so the potential exists for large temperature increases in a large pour, which could compromise the integrity of the pour. The primary purpose of the testing reported here was to measure heat of hydration, specific heat, thermal conductivity and density of various reactor grouts under consideration so that these properties could be used to model transient heat transfer for different pouring strategies. A secondary purpose was to make qualitative judgments of grout pourability and hardened strength. Some reactor grout formulations were unacceptable because they generated too much heat, or started setting too fast, or required too long to harden or were too weak. The formulation called 102H had the best combination of characteristics. It is a Calcium Alumino-Sulfate grout that contains Ciment Fondu (calcium aluminate cement), Plaster of Paris (calcium sulfate hemihydrate), sand, Class F fly ash, boric acid and small quantities of additives. This composition afforded about ten hours of working time. Heat release began at 12 hours and was complete by 24 hours. The adiabatic temperature rise was 54 C which was within specification. The final product was hard and displayed no visible segregation. The density and maximum particle size were within specification.

  10. Materials for nuclear reactors

    International Nuclear Information System (INIS)

    The improved performance of present generation nuclear reactors and the realization of advanced reactor concepts, both, require development of better materials. Physical metallurgy/materials science principles which have been exploited in meeting the exacting requirements of nuclear reactor materials (fuels and structural materials), are outlined citing a few specific examples. While the incentive for improvement of traditional fuels (e.g., UO2 fuel) is primarily for increasing the average core burn up, the development of advanced fuels (e.g., MOX, mixed carbide, nitride, silicide and dispersion fuels) are directed towards better utilization of fissile and fertile inventories through adaptation of innovative fuel cycles. As the burn up of UO2 fuel reaches higher levels, a more detailed and quantitative understanding of the phenomena such as fission gas release, fuel restructuring induced by radiation and thermal gradients and pellet-clad interaction is being achieved. Development of zirconium based alloys for both cladding and pressure tube applications is discussed with reference to their physical metallurgy, fabrication techniques and in-reactor degradation mechanisms. The issue of radiation embrittlement of reactor pressure vessels (RPVs) is covered drawing a comparison between the western and eastern specifications of RPV steels. The search for new materials which can stand higher rates of atomic displacement due to radiation has led to the development of swelling resistant austenitic and ferritic stainless steels for fast reactor applications as exemplified by the development of the D-9 steel for Indian fast breeder reactor. The presentation will conclude by listing various materials related phenomena, which have a strong bearing on the successful development of future nuclear energy systems. (author)

  11. Reactor physics and economic aspects of the CANDU reactor system

    International Nuclear Information System (INIS)

    A history of the development of the CANDU system is given along with a fairly detailed description of the 600 MW(e) CANDU reactor. Reactor physics calculation methods are described, as well as comparisons between calculated reactor physics parameters and those measured in research and power reactors. An examination of the economics of CANDU in the Ontario Hydro system and a comparison between fossil fuelled and light water reactors is presented. Some physics, economics and resources aspects are given for both low enriched uranium and thorium-fuelled CANDU reactors. Finally the RβD program in Advanced Fuel Cycles is briefly described

  12. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    Energy Technology Data Exchange (ETDEWEB)

    P. Delmolino

    2005-05-06

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

  13. Fast breeder reactor research

    International Nuclear Information System (INIS)

    Full text: The meeting was attended by 15 participants from seven countries and two international organizations. The Eighth Annual Meeting of the International Working Group on Fast Reactors (IWGFR) was attended by representatives from France, Fed. Rep. Germany, Italy, Japan, United Kingdom, Union of Soviet Socialist Republics and the United States of America - countries that have made significant progress in developing the technology and physics of sodium cooled fast reactors and have extensive national programmes in this field - as well as by representatives of the Commission of the European Communities and the IAEA. The design of fast-reactor power plants is a more difficult task than developing facilities with thermal reactors. Different reactor kinetics and dynamics, a hard neutron spectrum, larger integral doses of fuel and structural material irradiation, higher core temperatures, the use of an essentially novel coolant, and, as a result of all these factors, the additional reliability and safety requirements that are imposed on the planning and operation of sodium cooled fast reactors - all these factors pose problems that can be solved comprehensively only by countries with a high level of scientific and technical development. The exchange of experience between these countries and their combined efforts in solving the fundamental problems that arise in planning, constructing and operating fast reactors are promoting technical progress and reducing the relative expenditure required for various studies on developing and introducing commercial fast reactors. For this reason, the meeting concentrated on reviewing and discussing national fast reactor programmes. The situation with regard to planning, constructing and operating fast experimental and demonstration reactors in the countries concerned, the experience accumulated in operating them, the difficulties arising during operation and ways of over-coming them, the search for optimal designs for the power

  14. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    The irradiations in the BR2 reactor are in collaboration with or at the request of third parties such as the European Commission, the IAEA, research centres and utilities, reactor vendors or fuel manufacturers. The reactor also contributes significantly to the production of radioisotopes for medical and industrial applications, to neutron silicon doping for the semiconductor industry and to scientific irradiations for universities. Along the ongoing programmes on fuel and materials development, several new irradiation devices are in use or in design. Amongst others a loop providing enhanced cooling for novel materials testing reactor fuel, a device for high temperature gas cooled fuel as well as a rig for the irradiation of metallurgical samples in a Pb-Bi environment. A full scale 3-D heterogeneous model of BR2 is available. The model describes the real hyperbolic arrangement of the reactor and includes the detailed 3-D space dependent distribution of the isotopic fuel depletion in the fuel elements. The model is validated on the reactivity measurements of several tens of BR2 operation cycles. The accurate calculations of the axial and radial distributions of the poisoning of the beryllium matrix by 3He, 6Li and 3T are verified on the measured reactivity losses used to predict the reactivity behavior for the coming decades. The model calculates the main functionals in reactor physics like: conventional thermal and equivalent fission neutron fluxes, number of displacements per atom, fission rate, thermal power characteristics as heat flux and linear power density, neutron/gamma heating, determination of the fission energy deposited in fuel plates/rods, neutron multiplication factor and fuel burn-up. For each reactor irradiation project, a detailed geometry model of the experimental device and of its neighborhood is developed. Neutron fluxes are predicted within approximately 10 percent in comparison with the dosimetry measurements. Fission rate, heat flux and

  15. Reactor coolant cleanup facility

    International Nuclear Information System (INIS)

    A depressurization device is disposed in pipelines upstream of recycling pumps of a reactor coolant cleanup facility to reduce a pressure between the pressurization device and the recycling pump at the downstream, thereby enabling high pressure coolant injection from other systems by way of the recycling pumps. Upon emergency, the recycling pumps of the coolant cleanup facility can be used in common to an emergency reactor core cooling facility and a reactor shutdown facility. Since existent pumps of the emergency reactor core cooling facility and the reactor shutdown facility which are usually in a stand-by state can be removed, operation confirmation test and maintenance for equipments in both of facilities can be saved, so that maintenance and reliability of the plant are improved and burdens on operators can also be mitigated. Moreover, low pressure design can be adopted for a non-regenerative heat exchanger and recycling coolant pumps, which enables to improve the reliability and economical property due to reduction of possibility of leakage. (N.H.)

  16. HTGR type reactor

    International Nuclear Information System (INIS)

    A reactor core is disposed at the center of a reactor container, a reflector is disposed on the outer side thereof, a steam generator is disposed further outer side thereof coaxially, and they are constituted as an integrated one container. A gas circulator and control rod drives are protruded at the outer side of the lower portion of the integrated container. Heat insulators are disposed on the inner side of the container wall in the upper portion of the reactor container. Helium gas risen in the reactor core and heated to a high temperature descends in a circular steam generator and undergoes heat exchange with water, and is then pressurized in the gas circulator after the lowering of the temperature, and returned to the inlet of the reactor core from the lower central portion of the container. With such procedures, the helium gas as primary coolants circulates only in the container to improve confinement. The device can be reduced in the size and the cost. (I.N.)

  17. Reactor container spray device

    International Nuclear Information System (INIS)

    Purpose: To enable decrease in the heat and the concentration of radioactive iodine released from the reactor vessel into the reactor container in the spray device of BWR type reactors. Constitution: A plurality of water receiving trays are disposed below the spray nozzle in the dry well and communicated to a pressure suppression chamber by way of drain pipeways passing through a diaphragm floor. When the recycling system is ruptured and coolants in the reactor vessel and radioactive iodine in the reactor core are released into the dry well, spray water is discharged from the spray nozzle to eliminate the heat and the radioactive iodine in the dry well. In this case, the receiving trays collect the portions of spray water whose absorption power for the heat and radioactive iodine is nearly saturated and falls them into the pool water of the pressure suppression chamber. Consequently, other portions of the spray water that still possess absorption power can be jetted with no hindrance, to increase the efficiency for the removal of the heat and iodine of the spray droplets. (Horiuchi, T.)

  18. PROTEUS research reactor

    International Nuclear Information System (INIS)

    The PROTEUS zero power reactor at the Paul Scherrer Institute (PSI) in Switzerland achieved first criticality in 1968 and since then has been operated as an experimental tool for reactor physics research on test lattices representative of a wide range of reactor concepts. Reactor design codes and their associated data libraries are validated on the basis of the experimental results obtained. PROTEUS is normally configured as a driven system, in which a subcritical test zone is made critical by the surrounding driver zones. The advantages of driven systems can be summarized as follows: - Smaller amount of test fuel is required; - Large range of test zone conditions (including k∞ < 1 states) can be investigated by changes in the driver loading alone, thus avoiding undesirable perturbations to the test zone which would influence the measurement conditions and thus affect the interpretability of the results; - Necessary reactor control and instrumentation equipment (usually perturbing from the experimental viewpoint) can be located in the outer driver regions, thereby avoiding disturbance of the test lattice

  19. Generalities about nuclear reactors

    International Nuclear Information System (INIS)

    From Zoe, the first nuclear reactor, till the current EPR, the French nuclear industry has always advanced by profiting from the feedback from dozens of years of experience and operations, in particular by drawing lessons from the most significant events in its history, such as the Fukushima accident. The new generations of reactors must improve safety and economic performance so that the industry maintain its legitimacy and its share in the production of electricity. This article draws the history of nuclear power in France, gives a brief description of the pressurized water reactor design, lists the technical features of the different versions of PWR that operate in France and compares them with other types of reactors. The feedback experience concerning safety, learnt from the major nuclear accidents Three Miles Island (1979), Chernobyl (1986) and Fukushima (2011) is also detailed. Today there are 26 third generation reactors being built in the world: 4 EPR (1 in Finland, 1 in France and 2 in China); 2 VVER-1200 in Russia, 8 AP-1000 (4 in China and 4 in the Usa), 8 APR-1400 (4 in Korea and 4 in UAE), and 4 ABWR (2 in Japan and 2 in Taiwan)

  20. China experimental fast reactor

    International Nuclear Information System (INIS)

    The Chinese experimental fast reactor (CEFR) is a pool-type sodium-cooled fast reactor whose short term purposes are: -) the validation of computer codes, -) the check of the relevance of standards, and -) the gathering of experimental data on fast reactors. On the long term the expectations will focus on: -) gaining experience in fast reactor operations, -) the testing of nuclear fuels and materials, and -) the study of sodium compounds. The main technical features of CEFR are: -) thermal power output: 65 MW (electrical power output: 20 MW), -) size of the core: height: 45 cm, diameter: 60 cm, -) maximal linear output: 430 W/cm, -) neutron flux: 3.7*1015 n/cm2/s, -) input/output sodium temperature: 360 / 530 Celsius degrees, -) 2 loops for the primary system and 2 loops for the secondary system. The temperature coefficient and the power coefficient are settled to stay negative for any change in the values of the core parameters. The installation of the reactor vessel will be completed by mid 2007. The first criticality of CEFR is expected during the first semester of 2010. (A.C.)

  1. EBT reactor analysis

    International Nuclear Information System (INIS)

    This report summarizes the results of a recent ELMO Bumpy Torus (EBT) reactor study that includes ring and core plasma properties with consistent treatment of coupled ring-core stability criteria and power balance requirements. The principal finding is that constraints imposed by these coupling and other physics and technology considerations permit a broad operating window for reactor design optimization. Within this operating window, physics and engineering systems analysis and cost sensitivity studies indicate that reactors with approx. 6 to 10%, P approx. 1200 to 1700 MW(e), wall loading approx. 1.0 to 2.5 MW/m2, and recirculating power fraction (including ring-sustaining power and all other reactors auxiliaries) approx. 10 to 15% are possible. A number of concept improvements are also proposed that are found to offer the potential for further improvement of the reactor size and parameters. These include, but are not limited to, the use of: (1) supplementary coils or noncircular mirror coils to improve magnetic geometry and reduce size, (2) energetic ion rings to improve ring power requirements, (3) positive potential to enhance confinement and reduce size, and (4) profile control to improve stability and overall fusion power density

  2. Modern research reactors in the world and RA research reactor

    International Nuclear Information System (INIS)

    This paper covers the following topics: fundamentals of research reactors, thermal neutron flux density, classification of research reactors in the world, properties of research reactors of higher power in the world according to IAEA data for 1995, their application, and trend of development, experimental feasibility and status of RA reactor. Trend of research reactors development in the world (after 1980) is directed towards increasing the neutron production quality factor, i.e. ratio between thermal neutron flux density and reactor power, which is achieved by designing compact reactor cores. With the aim of renewal of RA reactor (without analysis of reactor components and staff aging, possibility of restart and commercialization), according to the analysis in this paper, it can be concluded: there is very few reactors under construction in the world, all the important countries in Europe have research reactors; RA reactor is not very interesting for development of reactor physics; nowadays RA reactor is in the group of reactors which are 30-40 years old; its inventories of fuel and heavy water are enough for about 20 years of operation; it has achieved high quality factor of neutron production with low and highly enriched fuel; core transfer from low highly enriched to low enriched fuel should be carefully studies from operation, experimental and economical point of view; it is necessary to use the advantages of RA reactor (minimum investment): volume of the core and reflector which enables availability of neutron flux for the users (numerous experimental loops), fuel in shape of slugs enabling efficient fuel management and flexible neutron flux distribution in the core in the reflector, reactor operation should be directed towards commercial applications. Bibliography of more than 140 relevant papers used is included in this paper

  3. Sodium-cooled nuclear reactors

    International Nuclear Information System (INIS)

    This book first explains the choice of sodium-cooled reactors by outlining the reasons of the choice of fast neutron reactors (fast neutrons instead of thermal neutrons, recycling opportunity for plutonium, full use of natural uranium, nuclear waste optimization, flexibility of fast neutron reactors in nuclear material management, fast neutron reactors as complements of water-cooled reactors), and by outlining the reasons for the choice of sodium as heat-transfer material. Physical, chemical, and neutron properties of sodium are presented. The second part of the book first presents the main design principles for sodium-cooled fast neutron reactors and their core. The third part proposes an historical overview and an assessment of previously operated sodium-cooled fast neutron reactors (French reactors from Rapsodie to Superphenix, other reactors in the world), and an assessment of the main incidents which occurred in these reactors. It also reports the experience and lessons learned from the dismantling of various sodium-cooled fast breeder reactors in the world. The next chapter addresses safety issues (technical and safety aspects related to the use of sodium) and environmental issues (dosimetry, gaseous and liquid releases, solid wastes, and cooling water). Then, various technological aspects of these reactors are addressed: the energy conversion system, main components, sodium chemistry, sodium-related technology, advances in in-service inspection, materials used in reactors and their behaviour, and fuel system. The next chapter addresses the fuel cycle in these reactors: its integrated specific character, report of the French experience in fast neutron reactor fuel processing, description of the transmutation of minor actinides in these reactors. The last chapter proposes an overview of reactors currently projected or under construction in the world, presents the Astrid project, and gives an assessment of the economy of these reactors. A glossary and an index

  4. Scaleable, High Efficiency Microchannel Sabatier Reactor Project

    Data.gov (United States)

    National Aeronautics and Space Administration — A Microchannel Sabatier Reactor System (MSRS) consisting of cross connected arrays of isothermal or graded temperature reactors is proposed. The reactor array...

  5. Methanation assembly using multiple reactors

    Science.gov (United States)

    Jahnke, Fred C.; Parab, Sanjay C.

    2007-07-24

    A methanation assembly for use with a water supply and a gas supply containing gas to be methanated in which a reactor assembly has a plurality of methanation reactors each for methanating gas input to the assembly and a gas delivery and cooling assembly adapted to deliver gas from the gas supply to each of said methanation reactors and to combine water from the water supply with the output of each methanation reactor being conveyed to a next methanation reactor and carry the mixture to such next methanation reactor.

  6. Mimic of OSU research reactor

    International Nuclear Information System (INIS)

    The Ohio State University research reactor (OSURR) is undergoing improvements in its research and educational capabilities. A computer-based digital data acquisition system, including a reactor system mimic, will be installed as part of these improvements. The system will monitor the reactor system parameters available to the reactor operator either in digital parameters available to the reactor operator either in digital or analog form. The system includes two computers. All the signals are sent to computer 1, which processes the data and sends the data through a serial port to computer 2 with a video graphics array VGA monitor, which is utilized to display the mimic system of the reactor

  7. MINT research reactor safety program

    Energy Technology Data Exchange (ETDEWEB)

    Mohamad Idris bin Taib [Division of Special Project, Malaysian Institute for Nuclear Technology Research (MINT), Bangi (Malaysia)

    2000-11-01

    Malaysian Institute for Nuclear Technology Research (MINT) Research Reactor Safety Program has been done along with Reactor Power Upgrading Project, Reactor Safety Upgrading Project and Development of Expert System for On-Line Nuclear Process Control Project. From 1993 up to date, Neutronic and Thermal-hydraulics analysis, Probabilistic Safety Assessment as well as installation of New 2 MW Secondary Cooling System were done. Installations of New Reactor Building Ventilation System, Reactor Monitoring System, Updating of Safety Analysis Report and Upgrading Primary Cooling System are in progress. For future activities, Reactor Modeling will be included to add present activities. (author)

  8. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  9. Fusion reactor materials

    International Nuclear Information System (INIS)

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  10. Chernobyl reactor accident

    International Nuclear Information System (INIS)

    On April 26, 1986, an explosion occurred at the newest of four operating nuclear reactors at the Chernobyl site in the USSR. The accident initiated an international technical exchange of almost unprecedented magnitude; this exchange was climaxed with a meeting at the International Atomic Energy Agency in Vienna during the week of August 25, 1986. The meeting was attended by more than 540 official representatives from 51 countries and 20 international organizations. Information gleaned from that technical exchange is presented in this report. A description of the Chernobyl reactor, which differs significantly from commercial US reactors, is presented, the accident scenario advanced by the Russian delegation is discussed, and observations that have been made concerning fission product release are described

  11. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    An international design team comprised of members from Canada, Europe, Japan, the Soviet Union, and the United States of America, are designing an experimental fusion test reactor. The engineering and testing objectives of this International Thermonuclear Experimental Reactor (ITER) are to validate the design and to demonstrate controlled ignition, extended burn of a deuterium and tritium plasma, and achieve steady state using technology expected to be available by 1990. The concept maximizes flexibility while allowing for a variety of plasma configurations and operating scenarios. During physics phase operation, the machine produces a 22 MA plasma current. In the technology phase, the machine can be reconfigured with a thicker shield and a breeding blanket to operate with an 18 MA plasma current at a major radius of 5.5 meters. Canada's involvement in the areas of safety, facility design, reactor configuration and maintenance builds on our internationally recognized design and operational expertise in developing tritium processes and CANDU related technologies

  12. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  13. Licensed operating reactors

    International Nuclear Information System (INIS)

    THE OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

  14. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  15. Colliding Beam Fusion Reactors

    Science.gov (United States)

    Rostoker, Norman; Qerushi, Artan; Binderbauer, Michl

    2003-06-01

    The recirculating power for virtually all types of fusion reactors has previously been calculated [1] with the Fokker-Planck equation. The reactors involve non-Maxwellian plasmas. The calculations are generic in that they do not relate to specific confinement devices. In all cases except for a Tokamak with D-T fuel the recirculating power was found to exceed the fusion power by a large factor. In this paper we criticize the generality claimed for this calculation. The ratio of circulating power to fusion power is calculated for the Colliding Beam Reactor with fuels D-T, D-He3 and p-B11. The results are respectively, 0.070, 0.141 and 0.493.

  16. The MNSR reactor

    International Nuclear Information System (INIS)

    This tank-in-pool reactor is based on the same design concept as the Canadian Slowpoke. The core is a right circular cylinder, 24 cm diameter by 25 cm long, containing 411 fuel pin positions. The pins are HEU-Aluminium alloy, 0.5 cm in diameter. Critical mass is about 900 g. The reactor has a single cadmium control rod. The back-up shutdown system is the insertion of a cadmium capsule in a core position. Excess reactivity is limited to 3.5mk. In both the MNSR and Slowpoke, the insertion of the maximum excess reactivity results in a power transient limited by the coolant/moderator temperature to safe values, independent of any operator action. This reactor is used primarily in training and neutron activation analysis. Up to 64 elements have been analyzed in a great variety of different disciplines. (author)

  17. Welding and reactor safety

    International Nuclear Information System (INIS)

    The high safety requirements which must be demanded of the quality of the welded joints in reactor technique have so far not been fulfilled in all cases. The errors occuring have caused considerable loss of availability and high material costs. They were not, however, so serious that one need have feared any immediate danger to the personnel or to the environment. The safety devices of reactor plants were only called upon in a few cases and to these they responded perfectly. The intensive efforts to complete and improve the specifications are to contribute to that in future, the reactor plants can be counted even more so as one of the safest technical plants ever. (orig./LH)

  18. Reactor operation experience

    International Nuclear Information System (INIS)

    Since the TRIGA Users Conference in Helsinki 1970 the TRIGA reactor Vienna was in operation without any larger undesired shutdown. The integrated thermal power production by August 15 1972 accumulated to 110 MWd. The TRIGA reactor is manly used for training of students, for scientific courses and research work. Cooperation with industry increased in the last two years either in form of research or in performing training courses. Close cooperation is also maintained with the IAEA, samples are irradiated and courses on various fields are arranged. Maintenance work was performed on the heat exchanger and to replace the shim rod magnet. With the view on the future power upgrading nine fuel elements type 110 have been ordered recently. Experiments, performed currently on the reactor are presented in details

  19. Nuclear Rocket Engine Reactor

    CERN Document Server

    Lanin, Anatoly

    2013-01-01

    The development of a nuclear rocket engine reactor (NRER ) is presented in this book. The working capacity of an active zone NRER under mechanical and thermal load, intensive neutron fluxes, high energy generation (up to 30 MBT/l) in a working medium (hydrogen) at temperatures up to 3100 K is displayed. Design principles and bearing capacity of reactors area discussed on the basis of simulation experiments and test data of a prototype reactor. Property data of dense constructional, porous thermal insulating and fuel materials like carbide and uranium carbide compounds in the temperatures interval 300 - 3000 K are presented. Technological aspects of strength and thermal strength resistance of materials are considered. The design procedure of possible emergency processes in the NRER is developed and risks for their origination are evaluated. Prospects of the NRER development for pilotless space devices and piloted interplanetary ships are viewed.

  20. Reactor accidents in perspective

    International Nuclear Information System (INIS)

    In each of the three major reactor accidents which have led to significant releases to the environment, and discussed in outline in this note, the reactor has been essentially destroyed - certainly Windscale and Chernobyl reactors will never operate and the cleanup operation for Three Mile Island is currently estimated to have cost in excess of US Pound 500 000 000. In each of the accidents there has not been any fatality off site in the short term and any long-term health detriment is unlikely to be seen in comparison with the natural cancer incidence rate. At Chernobyl, early fatalities did occur amongst those concerned with fighting the incident on site and late effects are to be expected. The assumption of a linear non-threshold risk, and hence no level of zero risk is the main problem in communication with the public, and the author calls for simplification of the presentation of the concepts of radiological protection. (U.K.)

  1. Reactor safety equipments

    International Nuclear Information System (INIS)

    Purpose: To positively recover radioactive substances discharged in a dry well at the time of failure of a reactor. Constitution: In addition to the emergency gas treating system fitted to a reactor building, a purification system connected through a pipeline to the dry well is arranged in the reactor building. This purification system is connected through pipes fitted to the dry well to forced circulation device, heat exchanger, and purification device. The atmosphere of high pressure steam gases in the dry well is derived to the heat exchanger for cooling, and then radioactive substances which are contained in the gases are removed by filter sets charged with the HEPA filters and the HECA filters. At last, there gases are returned to dry well by circulation pump, repeat this process. (Kamimura, M.)

  2. Licensed operating reactors

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

  3. Reactor protection system

    International Nuclear Information System (INIS)

    The report describes the reactor protection system (RPS-II) designed for use on Babcock and Wilcox 145-, later 177-, and 205-fuel assembly pressurized water reactors. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low-pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, a description of the software programmed in the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W

  4. Backfitting swimming pool reactors

    International Nuclear Information System (INIS)

    Calculations based on measurements in a critical assembly, and experiments to disclose fuel element surface temperatures in case of accidents like stopping of primary coolant flow during full power operation, have shown that the power of the swimming pool type research reactor FRG-2 (15 MW, operating since 1967) might be raised to 21 MW within the present rules of science and technology, without major alterations of the pool buildings and the cooling systems. A backfitting program is carried through to adjust the reactor control systems of FRG-2 and FRG-1 (5 MW, housed in the same reactor hall) to the present safety rules and recommendations, to ensure FRG-2 operation at 21 MW for the next decade. (author)

  5. MERCHANT MARINE SHIP REACTOR

    Science.gov (United States)

    Mumm, J.F.; North, D.C. Jr.; Rock, H.R.; Geston, D.K.

    1961-05-01

    A nuclear reactor is described for use in a merchant marine ship. The reactor is of pressurized light water cooled and moderated design in which three passes of the water through the core in successive regions of low, intermediate, and high heat generation and downflow in a fuel region are made. The foregoing design makes a compact reactor construction with extended core life. The core has an egg-crate lattice containing the fuel elements confined between a lower flow baffle and upper grid plate, with the latter serving also as part of a turn- around manifold from which the entire coolant is distributed into the outer fuel elements for the second pass through the core. The inner fuel elements are cooled in the third pass.

  6. Safety systems of heavy water reactors and small power reactors

    International Nuclear Information System (INIS)

    After introductional descriptions of heavy water reactors and natural circulation boiling water reactors the safety philosophy and safety systems like ECCS, residual heat removal, protection systems etc., are described. (RW)

  7. Study of future reactors

    International Nuclear Information System (INIS)

    Today, more than 420 large reactors with a gross output of close to 350 GWe supply 20 percent of world electricity needs, accounting for less than 5 percent of primary energy consumption. These figures are not expected to change in the near future, due to suspended reactor construction in many countries. Nevertheless, world energy needs continue to grow: the planet's population already exceeds five billion and is forecast to reach ten billion by the middle of the next century. Most less developed countries have a very low rate of energy consumption and, even though some savings can be made in industrialized countries, it will become increasingly difficult to satisfy needs using fossil fuels only. Furthermore, there has been no recent breakthrough in the energy landscape. The physical feasibility of the other great hope of nuclear energy, fusion, has yet to be proved; once this has been done, it will be necessary to solve technological problems and to assess economic viability. Although it is more ever necessary to pursue fusion programs, there is little likelihood of industrial applications being achieved in the coming decades. Coal and fission are the only ways to produce massive amounts of energy for the next century. Coal must overcome the pollution problems inherent in its use; fission nuclear power has to gain better public acceptance, which is obviously colored by safety and waste concerns. Most existing reactors were commissioned in the 1970s; reactor lifetime is a parameter that has not been clearly established. It will certainly be possible to refurbish some to extend their operation beyond the initial target of 30 or 40 years. But normal advances in technology and safety requirements will make the operation of the oldest reactors increasingly difficult. It becomes necessary to develop new generations of nuclear reactors, both to replace older ones and to revive plant construction in their countries that are not yet equipped or that have halted their

  8. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    A reasonable assumption for the estimated new build market for the next 25 years is over 340 GWe net. The number of prospect countries is growing almost each day. To address this new build market, AREVA is developing a comprehensive portfolio of reactors intended to meet a wide range of power requirements and of technology choices. The EPR reactor is the flagship of the fleet. Intended for large power requirements, the four first EPRs are being built in Finland, France and China. Other countries and customers are in view, citing just two examples: the Usa where the U.S. EPR has been selected as the technology of choice by several U.S utilities; and the United Kingdom where the Generic Design Acceptance process of the EPR design submitted by AREVA and EDF is well under way, and where there is a strong will to have a plant on line in 2017. For medium power ranges, the AREVA portfolio includes a boiling water reactor and a pressurized water reactor which both offer all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation cost: -) KERENA (1250+ MWe), developed in collaboration with several European utilities, and in particular with Eon; -) ATMEA 1 (1100+ MWe), a 3-loop evolutionary PWR which is being developed by AREVA and Mitsubishi. AREVA is also preparing the future and is deeply involved into Gen IV concepts. It has developed the ANTARES modular HTR reactor (pre-conceptual design completed) and is building upon its vast Sodium Fast Reactor experience to take part into the development of the next prototype. (author)

  9. Operating US power reactors

    International Nuclear Information System (INIS)

    This update, which appears regularly in each issue of Nuclear Safety, surveys the operations of those power reactors in the US which have been issued operating licenses. Table 1 shows the number of such reactors and their net capacities as of Dec. 31, 1986, the end of the three-month period covered in this report. Table 2 lists the unit capacity and forced outage rate for each licensed reactor for each of the three months (October, November, and December 1986) covered in this report and the cumulative values of these parameters since the beginning of commercial operation. They are defined as follows: In addition to the tabular data, this article discusses significant occurrences and developments that affected licensed US power reactors during this reporting period. It includes, but is not limited to, changes in operating status, regulatory actions and decisions, and legal actions involving the status of power reactors. We do not have space here for routine problems of operation and maintenance, but such information is available at the Nuclear Regulatory Commission (NRC) Public Document Room, 1717 H Street, NW, Washington, DC 20555. Some significant operating events are summarized elsewhere in this section in the article ''Selected Safety-Related Events,'' and a report on activities relating to facilities still in the construction process is given in the article ''Status of Power-Reactor Projects Undergoing Licensing Review'' in the last section of each issue of this journal. The reader's attention is also called to the regular feature ''General Administrative Activities,'' which deals with more general aspects of regulatory and legal matters that are not covered elsewhere in the journal

  10. Oscillatory flow chemical reactors

    Directory of Open Access Journals (Sweden)

    Slavnić Danijela S.

    2014-01-01

    Full Text Available Global market competition, increase in energy and other production costs, demands for high quality products and reduction of waste are forcing pharmaceutical, fine chemicals and biochemical industries, to search for radical solutions. One of the most effective ways to improve the overall production (cost reduction and better control of reactions is a transition from batch to continuous processes. However, the reactions of interests for the mentioned industry sectors are often slow, thus continuous tubular reactors would be impractically long for flow regimes which provide sufficient heat and mass transfer and narrow residence time distribution. The oscillatory flow reactors (OFR are newer type of tube reactors which can offer solution by providing continuous operation with approximately plug flow pattern, low shear stress rates and enhanced mass and heat transfer. These benefits are the result of very good mixing in OFR achieved by vortex generation. OFR consists of cylindrical tube containing equally spaced orifice baffles. Fluid oscillations are superimposed on a net (laminar flow. Eddies are generated when oscillating fluid collides with baffles and passes through orifices. Generation and propagation of vortices create uniform mixing in each reactor cavity (between baffles, providing an overall flow pattern which is close to plug flow. Oscillations can be created by direct action of a piston or a diaphragm on fluid (or alternatively on baffles. This article provides an overview of oscillatory flow reactor technology, its operating principles and basic design and scale - up characteristics. Further, the article reviews the key research findings in heat and mass transfer, shear stress, residence time distribution in OFR, presenting their advantages over the conventional reactors. Finally, relevant process intensification examples from pharmaceutical, polymer and biofuels industries are presented.

  11. Nuclear reactor simulator

    International Nuclear Information System (INIS)

    The Nuclear Reactor Simulator was projected to help the basic training in the formation of the Nuclear Power Plants operators. It gives the trainee the opportunity to see the nuclear reactor dynamics. It's specially indicated to be used as the support tool to NPPT (Nuclear Power Preparatory Training) from NUS Corporation. The software was developed to Intel platform (80 x 86, Pentium and compatible ones) working under the Windows operational system from Microsoft. The program language used in development was Object Pascal and the compiler used was Delphi from Borland. During the development, computer algorithms were used, based in numeric methods, to the resolution of the differential equations involved in the process. (author)

  12. Experimental reactor physics

    International Nuclear Information System (INIS)

    Neutronic experiments in moderators, subcritical assemblies, critical assemblies, and nuclear reactors are described, as well as the techniques of radiation measurements necessary to perform these experiments. Previously dispersed data from government reports, journal articles, and specialized monographs are codified. Original information drawn from the author's experience is included, especially on the pulsed source technique, spectrum measurements, research reactors, and exponential assemblies. The book provides the essential information for carrying out, analyzing, and understanding the experiments. Theory is kept to a minimum. Emphasis is placed on the physics of the situation, and the importance of estimating error as well as the mean value of a measured quantity

  13. Diagnostics for hybrid reactors

    International Nuclear Information System (INIS)

    The Hybrid Reactor(HR) can be considered an attractive actinide-burner or a fusion assisted transmutation for destruction of transuranic(TRU) nuclear waste. The hybrid reactor has two important subsystems: the tokamak neutron source and the blanket which includes a fuel zone where the TRU are placed and a tritium breeding zone. The diagnostic system for a HR must be as simple and robust as possible to monitor and control the plasma scenario, guarantee the protection of the machine and monitor the transmutation.

  14. Perspectives on reactor safety

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  15. Clinch River Breeder Reactor

    International Nuclear Information System (INIS)

    Mr. Baron says the administration's effort to terminate the Clinch River Breeder Reactor (CRBR) project is symptomatic; they have also placed restrictions on fusion, coal, solar, and other areas of energy development in which technological advances are held back in order to force conservation. Because the breeder reactor, unlike solar and fusion energy, is both economically and technically feasible, a demonstration plant is needed. The contentions that the CRBR design is obsolete, that its proposed size is inappropriate, or that plutonium can be diverted for weapons proliferation are argued to be invalid. Failure to complete the CRBR will have both economic and national security repercussions

  16. Netherlands Interuniversity Reactor Institut

    International Nuclear Information System (INIS)

    This is the annual report of the Interuniversity Reactor Institute in the Netherlands for the Academic Year 1977-78. Activities of the general committee, the daily committee and the scientific advice board are presented. Detailed reports of the scientific studies performed are given under five subjects - radiation physics, reactor physics, radiation chemistry, radiochemistry and radiation hygiene and dosimetry. Summarised reports of the various industrial groups are also presented. Training and education, publications and reports, courses, visits and cooperation with other institutes in the area of scientific research are mentioned. (C.F.)

  17. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel

  18. Perspectives on reactor safety

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  19. Reactor neutron dosimetry

    International Nuclear Information System (INIS)

    An analysis of requirements and possibilities for experimental neutron spectrum determination during the reactor pressure vessel surveil lance programme is given. Fast neutron spectrum and neutron dose rate were measured in the Fast neutron irradiation facility of our TRIGA reactor. It was shown that the facility can be used for calibration of neutron dosimeters and for irradiation of samples sensitive to neutron radiation. The investigation of the unfolding algorithm ITER was continued. Based on this investigations are two specialized unfolding program packages ITERAD and ITERGS written this year. They are able to unfold data from activation detectors and NaI(T1) gamma spectrometer respectively

  20. Decay of reactor neutrinos

    OpenAIRE

    Vogel, P.

    1984-01-01

    We consider the decay of massive neutrinos which couple to electrons and are, therefore, produced in nuclear reactors. Lifetime limits for the γ and electron-positron decay modes of these neutrinos are deduced from the experimental limit on the singles count rate in the detector used to study neutrino oscillations at the Gösgen reactor. The dominantly coupled neutrinos are light, and their invariant-lifetime limit tc.m. / mν is 1-3 sec/eV. The subdominantly coupled heavy neutrinos with mass 1...

  1. Small mirror fusion reactors

    International Nuclear Information System (INIS)

    Basic requirements for the pilot plants are that they produce a net product and that they have a potential for commercial upgrade. We have investigated a small standard mirror fusion-fission hybrid, a two-component tandem mirror hybrid, and two versions of a field-reversed mirror fusion reactor--one a steady state, single cell reactor with a neutral beam-sustained plasma, the other a moving ring field-reversed mirror where the plasma passes through a reaction chamber with no energy addition

  2. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2002-04-01

    The activities of SCK-CEN's Reactor Materials Research Department for 2001 are summarised. The objectives of the department are: (1) to evaluate the integrity and behaviour of structural materials used in nuclear power industry; (2) to conduct research to unravel and understand the parameters that determine the material behaviour under or after irradiation; (3) to contribute to the interpretation, the modelling of the material behaviour and to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the department are focussed on studies concerning (1) Irradiation Assisted Stress Corrosion Cracking (IASCC); (2) nuclear fuel; and (3) Reactor Pressure Vessel Steel.

  3. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    A nuclear reactor construction comprising a reactor core submerged in a pool of liquid metal coolant in a primary vessel which is suspended from the roof structure of a containment vault. Control rods supported from the roof structure are insertable in the core which is carried on a support structure from the wall of the primary vessel. To prevent excessive relaxation of the support structure whereby the control rods would be displaced relative to the core, the support structure incorporates a normally inactive secondary structure designed to become effective in bracing the primary structure against further relaxation beyond a predetermined limit. (author)

  4. Reactor PIK construction

    International Nuclear Information System (INIS)

    The construction work at the 100 MW researches reactor PIK in year 2002 was in progress. The main activity was concentrated on mechanical, ventilation and electrical equipment. Some systems and subsystems are under adjustment. Hydraulic driving gear for beam shutters are finished in installation, rinsing, and adjusting. Regulating rods test assembling was done. On the critical assembly the first reactor fueling was tested to evaluate the starting neutron source intensity and a sufficiency of existing control and instrument board. Mainline of the PIK facility design and neutron parameters are presented. (author)

  5. Reactor pressure vessel materials

    International Nuclear Information System (INIS)

    As a result of the popularity of the Agencies report 'Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels' of 1975, it was decided that another report on this broad subject would be of use. In this report, background and contemporary views on specially identified areas of the subject are considered as self-contained chapters, written by experts. Chapter 3 offers a detailed treatment of the selection criteria and properties of reactor pressure vessel materials. The main attention is directed towards steel and ingot making and the subsequent material processing

  6. Reactor gamma spectrometry: status

    International Nuclear Information System (INIS)

    Current work is described for Compton Recoil Gamma-Ray Spectrometry including developments in experimental technique as well as recent reactor spectrometry measurements. The current status of the method is described concerning gamma spectromoetry probe design and response characteristics. Emphasis is given to gamma spectrometry work in US LWR and BR programs. Gamma spectrometry in BR environments are outlined by focussing on start-up plans for the Fast Test Reactor (FTR). Gamma spectrometry results are presented for a LWR pressure vessel mockup in the Poolside Critical Assembly (PCA) at Oak Ridge National Laboratory

  7. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    SCK-CEN's research and development programme on fusion reactor materials includes: (1) the study of the mechanical behaviour of structural materials under neutron irradiation (including steels, inconel, molybdenum, chromium); (2) the determination and modelling of the characteristics of irradiated first wall materials such as beryllium; (3) the detection of abrupt electrical degradation of insulating ceramics under high temperature and neutron irradiation; (4) the study of the dismantling and waste disposal strategy for fusion reactors.; (5) a feasibility study for the testing of blanket modules under neutron radiation. Main achievements in these topical areas in the year 1999 are summarised

  8. Space-time reactor kinetics for heterogeneous reactor structure

    International Nuclear Information System (INIS)

    An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods

  9. Risk prevention during reactor shutdown

    International Nuclear Information System (INIS)

    During reactor shutdown potential risks are issued of a number of maintenance operations. In this text we analyse these operations and give the modifications of technical specifications to ameliorate the reactor safety. 4 figs

  10. New fast-reactor approach

    International Nuclear Information System (INIS)

    The design parameters for a 1000 MW LMFBR type reactor are presented. The design requires the multiple primary coolant pumps and heat exchangers to be located around the core within the reactor vessel

  11. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1982 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Since fiscal 1982, Systematic research and development work on safeguards technology has been added to the activities of the Department. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  12. Reactor operation environmental information document

    Energy Technology Data Exchange (ETDEWEB)

    Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

    1989-12-01

    The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

  13. Operating reactors licensing actions summary

    International Nuclear Information System (INIS)

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors

  14. High Flux Isotope Reactor (HFIR)

    Data.gov (United States)

    Federal Laboratory Consortium — The HFIR at Oak Ridge National Laboratory is a light-water cooled and moderated reactor that is the United States’ highest flux reactor-based neutron source. HFIR...

  15. The IR-8 reactor operation

    Energy Technology Data Exchange (ETDEWEB)

    Ryazantsev, E.P.; Egorenkov, P.M.; Yashin, A.F. [Reactor Technology and Materials Research Inst. of RRC ' KI' , Moscow (Russian Federation)

    1997-07-01

    At the Russian Research Center 'Kurchatov Institute' (RRC 'KI') the IR-8 reactor commissioning was carried out in 1981. The reactor was developed in return for earlier existing at RRC 'KI' of the IRT-M reactor (modernized IRT reactor, constructed in 1957). The IRT-M reactor was used for investigations in nuclear physics, solid state physics, radiation chemistry, biology as well as to produce isotopes. Under developing the IR-8 reactor the IRT biological shielding with beam tubes and its process systems were used. The IR-8 reactor creation was founded on application developed by then new fuel assemblies (FA) of IRT-3M type, having two times as great surface of heat transfer and 1.75 times higher U-235 load than the FA of the IRT-2M type, which were used in IRT-M reactor. (author)

  16. Power calibrations for TRIGA reactors

    International Nuclear Information System (INIS)

    The purpose of this paper is to establish a framework for the calorimetric power calibration of TRIGA reactors so that reliable results can be obtained with a precision better than ± 5%. Careful application of the same procedures has produced power calibration results that have been reproducible to ± 1.5%. The procedures are equally applicable to the Mark I, Mark II and Mark III reactors as well as to reactors having much larger reactor tanks and to TRIGA reactors capable of forced cooling up to 3 MW in some cases and 15 MW in another case. In the case of forced cooled TRIGA reactors, the calorimetric power calibration is applicable in the natural convection mode for these reactors using exactly the same procedures as are discussed below for the smaller TRIGA reactors (< 2 MW)

  17. Reactor operation safety information document

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  18. Reactor safety in Eastern Europe

    International Nuclear Information System (INIS)

    The papers presented to the GRS colloquium refer to the cooperative activities for reactor accident analysis and modification of the GRS computer codes for their application to reactors of the Russian design types of WWER or RBMK. Another topic is the safety of RBMK reactors in particular, and the current status of investigations and studies addressing the containment of unit 4 of the Chernobyl reactor station. All papers are indexed separately in report GRS--117. (HP)

  19. VVER and RBMK reactors

    International Nuclear Information System (INIS)

    The safety of VVER and RBMK reactors has been discussed a lot after Chernobyl accident. Some improvements have been performed since that especially in RBMK-reactors and extensive programmes for backfitting have been planned and are partly underway. There are two different sizes of VVER reactors, 440 MW and 1000 MW. The design bases and designs itself vary inside the family of two size classes depending on the age of the plant. The oldest VVER-440 is called model 230 and the newest model 213. The oldest VVER-1000 units (two units) are prototypes that have some unique, nonfavorable features. The next stage of VVER-1000 developement (three units) is model V-302 and the remaining 15 plants in operation are model V-320, but even within this latest model there are some differences. The design bases and designs vary also inside the family of the RBMK reactors exactly the same way as in VVERs. The most important design bases of nuclear power plants designed in the former Soviet Union is presented in this paper. Also some safety advantages and disadvantages of these NPPs are discussed. (au). (5 figs.)

  20. Thermal Reactor Safety

    Energy Technology Data Exchange (ETDEWEB)

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  1. Studies on reactor physics

    International Nuclear Information System (INIS)

    Most of the peaceful applications of atomic energy are inherently dependent on advances in the science and technology of nuclear reactors, and aspects of this development are part of a major programme of the International Atomic Energy Agency. The most useful role that the Agency can play is as a co-ordinating body or central forum where the trends can be reviewed and the results assessed. Some of the basic studies are carried out by members of the Agency's own scientific staff. The Agency also convenes groups of experts from different countries to examine a particular problem in detail and make any necessary recommendations. Some of the important subjects are discussed at international scientific meetings held by the Agency. One of the subjects covered by such studies is the physics of nuclear reactors and a specific topic recently discussed was Codes for Reactor Computations, on which a seminar was held in Vienna in April this year. Another The members of the Panel described the development of heavy water reactors, the equipment and methods of research currently used, and plans for further development in their respective countries meeting of Panel of Experts on Heavy Water Lattices was held in Vienna in August 1959

  2. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    The purpose of this book is to explain the physical working conditions of nuclear reactors for the benefit of non-specialized engineers and engineering students. One of the leading ideas of this course is to distinguish between two fundamentally different concepts: - a science which could be called neutrodynamics (as distinct from neutron physics which covers the knowledge of the neutron considered as an elementary particle and the study of its interactions with nuclei); the aim of this science is to study the interaction of the neutron gas with real material media; the introduction will however be restricted to its simplified expression, the theory and equation of diffusion; - a special application: reactor physics, which is introduced when the diffusing and absorbing material medium is also multiplying. For this reason the chapter on fission is used to introduce this section. In practice the section on reactor physics is much longer than that devoted to neutrodynamics and it is developed in what seemed to be the most relevant direction: nuclear power reactors. Every effort was made to meet the following three requirements: to define the physical bases of neutron interaction with different materials, to give a correct mathematical treatment within the limit of necessary simplifying hypotheses clearly explained; to propose, whenever possible, numerical applications in order to fix orders of magnitude

  3. Nuclear Reactors and Technology

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. [eds.

    1992-01-01

    This publication Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency`s Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on the Energy Science and Technology Database and Nuclear Science Abstracts (NSA) database. Current information, added daily to the Energy Science and Technology Database, is available to DOE and its contractors through the DOE Integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user`s needs.

  4. Thermal Reactor Safety

    International Nuclear Information System (INIS)

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods

  5. Nuclear reactor container

    International Nuclear Information System (INIS)

    In a container of a BWR type reactor, spray water is stored in a pedestal cavity. A perforated hole is formed on the side wall of the pedestal, and a stirrer is disposed in the pedestal cavity to stir the stored spray water. During reactor operation, the door on the side wall of the pedestal is closed to prevent discharge of fission products to the dry well when a severe accident should occur. During periodical inspection for the plant, the door is opened to enable an operator to access to the inside of the pedestal. When a molten reactor core should drop to the pedestal cavity, fission products generated from the failed reactor core left in a pressure vessel pass through the spray water in the pedestal cavity. Then, most of the fission products are held in the spray water by a scrubbing effect when they pass through the spray water. In addition, the stored spray water is stirred by the stirrer to enhance the scrubbing effect thereby enabling to further decrease the amount of the fission products discharged to the dry well. (N.H.)

  6. ICF tritium production reactor

    International Nuclear Information System (INIS)

    The conceptual design of an ICF tritium production reactor is described. The chamber design uses a beryllium multiplier and a liquid lithium breeder to achieve a tritium breeding ratio of 2.08. The annual net tritium production of this 532 MW/sub t/ plant is 16.9 kg, and the estimated cost of tritium is $8100/g

  7. Fusion reactor materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1989-01-01

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics.

  8. Nuclear reactor building

    Science.gov (United States)

    Gou, Perng-Fei; Townsend, Harold E.; Barbanti, Giancarlo

    1994-01-01

    A reactor building for enclosing a nuclear reactor includes a containment vessel having a wetwell disposed therein. The wetwell includes inner and outer walls, a floor, and a roof defining a wetwell pool and a suppression chamber disposed thereabove. The wetwell and containment vessel define a drywell surrounding the reactor. A plurality of vents are disposed in the wetwell pool in flow communication with the drywell for channeling into the wetwell pool steam released in the drywell from the reactor during a LOCA for example, for condensing the steam. A shell is disposed inside the wetwell and extends into the wetwell pool to define a dry gap devoid of wetwell water and disposed in flow communication with the suppression chamber. In a preferred embodiment, the wetwell roof is in the form of a slab disposed on spaced apart support beams which define therebetween an auxiliary chamber. The dry gap, and additionally the auxiliary chamber, provide increased volume to the suppression chamber for improving pressure margin.

  9. Nuclear reactor constructions

    International Nuclear Information System (INIS)

    A method of constructing a radiation shielding plug for use in the roof of the coolant containment vault of liquid metal cooled fast breeder reactors is described. The construction allows relative movement of that part of service cables and pipes which are carried by the fixed roof and that part which is carried by the rotatable plug. (U.K.)

  10. Fast reactor programme

    International Nuclear Information System (INIS)

    This progress report summarizes the fast reactor research carried out by ECN during the period covering the year 1980. This research is mainly concerned with the cores of sodium-cooled breeders, in particular the SNR-300, and its related safety aspects. It comprises six items: A programme to determine relevant nuclear data of fission- and corrosion-products; A fuel performance programme comprising in-pile cladding failure experiments and a study of the consequences of loss-of-cooling and overpower; Basic research on fuel; Investigation of the changes in the mechanical properties of austenitic stainless steel DIN 1.4948 due to fast neutron doses, this material has been used in the manufacture of the reactor vessel and its internal components; Study of aerosols which could be formed at the time of a fast reactor accident and their progressive behaviour on leaking through cracks in the concrete containment; Studies on heat transfer in a sodium-cooled fast reactor core. As fast breeders operate at high power densities, an accurate knowledge of the heat transfer phenomena under single-phase and two-phase conditions is sought. (Auth.)

  11. Fusion reactor materials

    International Nuclear Information System (INIS)

    At the Belgian Nuclear Research Centre SCK-CEN, activities related to fusion focus on environmental tolerance of opto-electronic components. The objective of this program is to contribute to the knowledge on the behaviour, during and after neutron irradiation, of fusion-reactor materials and components. The main scientific activities for 1997 are summarized

  12. Reactors. Nuclear propulsion ships

    International Nuclear Information System (INIS)

    This article has for object the development of nuclear-powered ships and the conception of the nuclear-powered ship. The technology of the naval propulsion P.W.R. type reactor is described in the article B.N.3 141 'Nuclear Boilers ships'. (N.C.)

  13. Cermet fuel reactors

    Energy Technology Data Exchange (ETDEWEB)

    Cowan, C.L.; Palmer, R.S.; Van Hoomissen, J.E.; Bhattacharyya, S.K.; Barner, J.O.

    1987-09-01

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs.

  14. Cermet fuel reactors

    International Nuclear Information System (INIS)

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. Key features of the cermet fueled reactor design are (1) the ability to achieve very high coolant exit temperatures, and (2) thermal shock resistance during rapid power changes, and (3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, thre is a potential for achieving a long operating life because of (1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and (2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core. In addition, the neutronic properties of the refractory materials assure that the reactor remains substantially subcritical under conditions of water immersion. It is concluded that cermet fueled reactors can be utilized to meet the power requirements for a broad range of advanced space applications. 4 refs., 4 figs., 3 tabs

  15. Integral Fast Reactor Program

    International Nuclear Information System (INIS)

    This report summarizes highlights of the technical progress made in the Integral Fast Reactor (IFR) Program in FY 1992. Technical accomplishments are presented in the following areas of the IFR technology development activities: (1) metal fuel performance, (2) pyroprocess development, (3) safety experiments and analyses, (4) core design development, (5) fuel cycle demonstration, and (6) LMR technology R ampersand D

  16. Stabilized Spheromak Fusion Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, T

    2007-04-03

    The U.S. fusion energy program is focused on research with the potential for studying plasmas at thermonuclear temperatures, currently epitomized by the tokamak-based International Thermonuclear Experimental Reactor (ITER) but also continuing exploratory work on other plasma confinement concepts. Among the latter is the spheromak pursued on the SSPX facility at LLNL. Experiments in SSPX using electrostatic current drive by coaxial guns have now demonstrated stable spheromaks with good heat confinement, if the plasma is maintained near a Taylor state, but the anticipated high current amplification by gun injection has not yet been achieved. In future experiments and reactors, creating and maintaining a stable spheromak configuration at high magnetic field strength may require auxiliary current drive using neutral beams or RF power. Here we show that neutral beam current drive soon to be explored on SSPX could yield a compact spheromak reactor with current drive efficiency comparable to that of steady state tokamaks. Thus, while more will be learned about electrostatic current drive in coming months, results already achieved in SSPX could point to a productive parallel development path pursuing auxiliary current drive, consistent with plans to install neutral beams on SSPX in the near future. Among possible outcomes, spheromak research could also yield pulsed fusion reactors at lower capital cost than any fusion concept yet proposed.

  17. SRP reactor safety evolution

    International Nuclear Information System (INIS)

    The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

  18. Fusion reactor materials

    International Nuclear Information System (INIS)

    This paper discuses the following topics on fusion reactor materials: irradiation, facilities, test matrices, and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; fundamental mechanical behavior; radiation effects; development of structural alloys; solid breeding materials; and ceramics

  19. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1980 are described. The work is presented in three chapters: General Information on the Department, Summary of the Department's Development during 1980, and Activities of the Department. Lists of staff, publications, computer programs, and test facilities are included. (author)

  20. The AP1000 reactor

    International Nuclear Information System (INIS)

    The design of the AP1000 reactor began 20 years ago when Westinghouse launched the AP600 reactor project. In fact by re-assessing AP600's safety margins Westinghouse realized that the its power output could be raised without putting at risk its safety standard. The AP1000 was born, it yields 1100 MWe. The main AP1000's design features is its passive safety (particularly after the Fukushima accident) and its modularity. The passive safety of the AP1000 implies: -) no humane intervention needed for 72 hours at least after the incident; -) no necessity for redundant complex safety systems. The modularity means that the plant, the reactor and other buildings are constructed from a choice of 300 modular units. These units can be built off-site and fit together on site. The modularity allows more construction activities to be led simultaneously and more chances to cope with the construction schedule. The NRC has approved the operation license for 30 years of the first AP1000 being built in the Usa (Vogtle plant in Georgia). 4 AP1000 are being built in China (Sanmen and Haiyang sites) and 6 others are planned in the Usa. Westinghouse is convinced that the AP1000's passive safety makes it more attractive. Let us not forget that Westinghouse was at the origin of the concept of pressurized water reactors, an idea adopted for half the nuclear power stations in the world and for all the plants now active in France. (A.C.)