WorldWideScience

Sample records for mm za wwer-1000

  1. WWER-1000 Burnup Credit Benchmark (CB5)

    International Nuclear Information System (INIS)

    Manolova, M.A.

    2002-01-01

    In the paper the specification of WWER-1000 Burnup Credit Benchmark first phase (depletion calculations), given. The second phase - criticality calculations for the WWER-1000 fuel pin cell, will be given after the evaluation of the results, obtained at the first phase. The proposed benchmark is a continuation of the WWER benchmark activities in this field (Author)

  2. WWER-1000 fuel cycles: current situation and outlook

    International Nuclear Information System (INIS)

    Kosourov, E.; Pavlov, V.; Pavlovichev, A.; Spirkin, E.; Shcherenko, A.

    2013-01-01

    Usage mode of nuclear fuel in WWER type reactor has been changed significantly till the moment of the first WWER-1000 commissioning. There are a lot of improvements, having an impact on the fuel cycle, have been implemented for units with WWER-1000. FA design and its constructional materials, FA fuel weight, burnable poison, usage mode of units and etc have been modified. As the result of development it has been designed a modern FA with rigid skeleton. As a whole it allows to use more efficient configurations of the core, to extend range of fuel cycle lengths and to provide good flexibility in the operation. In recent years there were in progress works on increasing FA uranium capacity. As the result there were developed two designs of the fuel rod: 1) the fuel column height of 3680 mm, diameters of the fuel pellet and its central hole of 7.6 and 1.2 mm respectively and 2) the fuel column height of 3530 mm, the fuel pellet diameter of 7.8 mm without the central hole. Such fuel rods have operating experience as a part of different FA designs. Positive operating experience was a base of new FA (TVS-4) development with the fuel column height of 3680 mm and the fuel pellet diameter of 7.8 mm without the central hole. The paper presents the overview of WWER-1000, AES-2006 and WWER-TOI fuel cycles based on FAs with fuel rod designs described above. There are demonstrated fuel cycle possibilities and its technical and economic characteristics. There are discussed problems of further fuel cycle improvements (fuel enrichment increase above 5 %, use of erbium as alternative burnable poison) and their impact on neutronics characteristics. (authors)

  3. Advanced fuel cycles for WWER-1000 reactors

    International Nuclear Information System (INIS)

    Semchenkov, Y. M.; Pavlovichev, A. M.; Pavlov, V. I.; Spirkin, E. I.; Styrin, Y. A.; Kosourov, E. K.

    2007-01-01

    Main stages of Russian uranium fuel development regarding improvement of safety and economics of fuel load operation are presented. Intervals of possible changes in fuel cycle duration have been demonstrated for the use of current and perspective fuel. Examples of equilibrium fuel load patterns have been demonstrated and main core neutronics parameters have been presented. Problems on the use of axial blankets with reduced enrichment in WWER-1000 fuel assemblies are considered. Some results are presented regarding core neutronic characteristics of WWER-1000 at the use of regenerated uranium and uranium-plutonium fuel. Examples of equilibrium fuel cycles for the core partially loaded with MOX fuel from weapon-grade plutonium are also considered (Authors)

  4. Experience and prospects of WWER-1000 reactor spent fuel transport

    International Nuclear Information System (INIS)

    Kondratyev, A.N.; Yershov, V.N.; Kozlov, Yu.V.; Kosarev, Yu.A.; Ilyin, Yu.V.; Pavlov, M.S.

    1989-01-01

    The paper deals with the USSR experience in shipping the commercial WWER-1000 reactor spent fuel in TK-10 and TK-13 casks. The cask designs, their basic characteristics and the WWER-1000 spent fuel features are described. An example of calculational/experimental approach in the design of a basket (one of the most important components) for spent fuel assembly (SFA) accommodation in a cask is given. The main problems of future development works are presented in brief. A concept of development of nuclear power industry with the closed fuel cycle is assumed in the Soviet Union, hence the spent nuclear fuel is to be transported from NPPs to reprocessing plants. To transport WWER-1000 spent fuel, the casks of two types were developed. These are: a pilot TK-10 cask of 3t capacity in fuel; a commercial TK-13 cask of ∼6t capacity in fuel. The pilot TK-10 cask is thick-walled (360mm) cylindrical vessel manufactured of steel shells and a bottom welded to each other. The material of the body is carbon steel. There is a steel jacket on the outer side of the cask body and at 120 mm distance off the bottom. On its cylindrical part between the jacket and the body there are T-shaped circular ribs acting as shock-absorbers. The space between the jacket and the body is filled with ethylene glycol solution of 65 degree C crystallization temperature, which functions as a neutron shielding. The TK-10 cask coolant is water or air (nitrogen) at minor excess pressure resulted from FA heatup after the cask sealing

  5. Thermohydraulic model of WWER-1000 core

    International Nuclear Information System (INIS)

    Maroti, L.; Szabados, L.

    1987-11-01

    Safe and economic operation of the WWER-1000 type reactor requires more accurate calculation of the thermohydraulic processes than the one satisfactory for the 440 type cores. The high degree of accuracy is needed both for reactor physics calculations and for the determination of the operational safety limits of the core. The paper illustrates the most important differences between the 1000 and 440 type reactors and presents the main fields of the development work necessary to reach the required accuracy. A prediction for the capability of the computer programs after the proposed development is also given and some suggestions for the further improvement is outlined. (author) 7 refs

  6. Modernization of WWER-1000 radiation monitoring systems

    International Nuclear Information System (INIS)

    Smith, T.

    1995-01-01

    A modernization scheme of the radiation monitoring system for WWER-1000 is proposed. It has a purpose to comply with international standards and to reduce operational and maintenance cost by deleting obsolete components and reducing the number of detector channels. Detailed layouts of I/C system architecture, digital radiation monitoring system (DRAMS) architecture and LRP block diagram are presented. If planned and implemented properly, this program can provide cost savings by reducing time required to access and display data and maintenance cost by deleting obsolete parts and decreasing the number of detector channels. 3 figs

  7. Modernization of WWER-1000 radiation monitoring systems

    Energy Technology Data Exchange (ETDEWEB)

    Smith, T [General Atomics, San Diego, CA (United States)

    1996-12-31

    A modernization scheme of the radiation monitoring system for WWER-1000 is proposed. It has a purpose to comply with international standards and to reduce operational and maintenance cost by deleting obsolete components and reducing the number of detector channels. Detailed layouts of I/C system architecture, digital radiation monitoring system (DRAMS) architecture and LRP block diagram are presented. If planned and implemented properly, this program can provide cost savings by reducing time required to access and display data and maintenance cost by deleting obsolete parts and decreasing the number of detector channels. 3 figs.

  8. Advanced fuel cycles of WWER-1000 reactors

    International Nuclear Information System (INIS)

    Lunin, G.; Novikov, A.; Pavlov, V.; Pavlovichev, A.

    2003-01-01

    The present paper considers characteristics of fuel cycles for the WWER-1000 reactor satisfying the following conditions: duration of the campaign at the nominal power is extended from 250 EFPD up to 470 and more ones; fuel enrichment does not exceed 5 wt.%; fuel assemblies maximum burnup does not exceed 55 MWd/kgHM. Along with uranium fuel, the use of mixed Uranium-Plutonium fuel is considered. Calculations were conducted by codes TVS-M, BIPR-7A and PERMAK-A developed in the RRC Kurchatov Institute, verified for the calculations of uranium fuel and certified by GAN RF

  9. Radiation embrittlement of WWER-1000 reactor vessel steels

    International Nuclear Information System (INIS)

    Nikolaeva, A.V.; Nikolaev, Yu.A.; Kevorkyan, Yu.R.

    2001-01-01

    Results obtained on the blank samples of materials of the WWER-1000 vessels irradiated by low density neutron flux are discussed. Chemical composition of the materials is characterized by the low content of the impurities (copper and phosphorus) and high content of nickel. Dependence of the radiation embrittlement of the WWER-1000 vessel materials on metallurgic variables and damage dose is treated. The research showed that nickel largely enhanced the radiation embrittlement. New dependences for determination of the radiation embrittlement real rate of the WWER-1000 vessel materials and its conservative estimation were developed [ru

  10. WWER-1000 reactor simulator. Workshop material

    International Nuclear Information System (INIS)

    2003-01-01

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

  11. Fuel improvement and WWER-1000 FA main operational results

    International Nuclear Information System (INIS)

    Rozhkov, V.; Enin, A.; Bezborodov, Y.; Petrov, V.

    2003-01-01

    The JSC NCCP experience of WWER-1000 Fuel Assemblies (FAs) fabrication and operation confirms the adequate feasibility and efficiency of fuel operation in 3-4-x fuel cycles, high operating reliability and competitive capacity as compared with foreign analogues. The work on fuel improvement is aimed at an improvement of the operating reliability and an enhancement of the fuel use efficiency in WWER-1000 advanced FAs

  12. Concentration of WWER-1000 unit power on one site

    International Nuclear Information System (INIS)

    Rousek, J.; Kysel, J.; Sladek, V.

    1987-01-01

    The problem of a suitable number of nuclear power plant units built on one site is discussed. Using an example of three sites being prepared now in Czechoslovakia, two alternatives - one with two WWER-1000 units, the other with four WWER-1000 units on one site - are evaluated from the viewpoint of long-range nuclear power development program in Czechoslovakia, costs, transmission of electric power and heat supply. (author). 10 tabs., 13 refs

  13. Analysis of operating reliability of WWER-1000 unit

    International Nuclear Information System (INIS)

    Bortlik, J.

    1985-01-01

    The nuclear power unit was divided into 33 technological units. Input data for reliability analysis were surveys of operating results obtained from the IAEA information system and certain indexes of the reliability of technological equipment determined using the Bayes formula. The missing reliability data for technological equipment were used from the basic variant. The fault tree of the WWER-1000 unit was determined for the peak event defined as the impossibility of reaching 100%, 75% and 50% of rated power. The period was observed of the nuclear power plant operation with reduced output owing to defect and the respective time needed for a repair of the equipment. The calculation of the availability of the WWER-1000 unit was made for different variant situations. Certain indexes of the operating reliability of the WWER-1000 unit which are the result of a detailed reliability analysis are tabulated for selected variants. (E.S.)

  14. Extended analysis of WWER-1000 Charpy test data

    International Nuclear Information System (INIS)

    Vodenicharov, St.; Kamenova, Tz.

    2001-01-01

    The aim of this work is to study the embrittlement rate of WWER-1000 RPV weld metal with high Ni content and to determine influence of neutron irradiation on partial energies of ductile crack initiation, stable and unstable crack propagation and post crack arrest. (author)

  15. WWER-1000 nuclear fuel manufacturing process at PJSC MSZ

    International Nuclear Information System (INIS)

    Morylev, A.; Bagdatyeva, E.; Aksenov, P.

    2015-01-01

    In this report a brief description of WWER-1000 fuel manufacturing process steps at PJSC MSZ as: uranium dioxide powder fabrication; fuel pellet manufacture fuel rod manufacture working assembly and fuel assembly manufacture is given. The implemented innovations are also presented

  16. Performance of the Westinghouse WWER-1000 fuel design

    International Nuclear Information System (INIS)

    Hoglund, J.; Riznychenko, O.; Latorre, R.; Lashevych, P.

    2011-01-01

    In 2005 six (6) Westinghouse WWER-1000 Lead Test Assemblies (LTAs) were loaded in the South Ukraine Unit 3. This design has demonstrated full compatibility with resident fuel designs and all associated fuel handling and reactor components. Operations have further demonstrated adequacy of performance margins and the reliability requirements for multiple cycles of operation. The LTA's have now been discharged after completing the planned four cycles of operation and having reached an average assembly burnup in excess of 43 MWd/kgU. Post Irradiation Examinations were performed after completion of each cycle. The final LTA inspection program at end of Cycle 20 in 2010 yielded satisfactory results on all counts, and it was concluded that the 6 Westinghouse LTA's performed as expected during their operational regimes. Very good performance was demonstrated in the WWER-1000 reactor environment for the Zr-1%Nb as grid material, and ZIRLO fuel cladding and structural components. Control Rod Assemblies drop times and drag forces were all within the accepted values. The LTA program demonstrated that this fuel design is suitable for full core applications. However, the topic of fuel assembly distortion resistance was re-visited and Westinghouse therefore considered operational experience and design features from multiple development programs to enhance the basic Westinghouse WWER-1000 fuel design for Ukrainian reactors. The design now includes features that further mitigate assembly bow while at the same time improving the fuel cycle economy. This paper describes briefly the development of the Westinghouse WWER-1000 fuel design and how test results and operational experiences from multiple sources have been utilized to produce a most suitable fuel design. Early in 2011 a full region of the Westinghouse WWER-1000 design completed another full cycle of operation at South Ukraine Unit 3, all with excellent results. All 42 fuel assemblies were examined for visible damage or non

  17. Determination of fast neutron fluence at WWER-1000 pressure vessel

    International Nuclear Information System (INIS)

    Valenta, V. et al.

    1989-01-01

    The influence function method is an effective tool making it possible, by means of tabulated values to rapidly perform three-dimensional calculations of fast neutron fluences for various reactor core loadings and for various nuclear power plant units. The procedure for determining the spatial dependence of the fast neutron fluences in a WWER-1000 pressure vessel is described. For this, the reactor core is divided into sufficiently fine volume elements within which the neutron source can be regarded as coordinate-independent. The influence functions point to a substantial role of sources lying at the reactor core periphery. In WWER-1000 reactors, only 1 or 2 rows of peripheral assemblies are important. The influence function method makes possible a rapid and easy determination of preconditions for the assessment of the residual lifetime of the pressure vessel based on the actual reactor core loadings. (Z.M.). 7 figs., 8 refs

  18. Modelling of WWER-1000 fuel: state and prospects

    International Nuclear Information System (INIS)

    Medvedev, A.; Bibilashvili, Yu.; Bogatyr, S.; Khvostov, G.

    1994-01-01

    The role of START-3 code in studying and computerized modelling of post-irradiation behaviour of standard fuel rods in real operation conditions of WWER-1000 reactors is described. The models used in the code are based on experimental study of material properties, processes and post irradiation research on standard and experimental fuel pins. The code capability is verified by comparison with data from experiments on WWER test rods performed in MR reactor, the Russia-Finland tests SOFIT and the international program FUMEX. The comparison performed and the results thus obtained demonstrate the satisfactory ability of START-3 code to simulate fuel rod behaviour in normal operation condition. The calculations confirm the experimentally observed evidence of an essential margin on serviceability of WWER-1000 fuel pin with three year operation cycle permitting an increase in design fuel burnup. 2 tabs., 18 figs

  19. Operational indices of WWER-1000 fuel assemblies and their improvements

    International Nuclear Information System (INIS)

    Vasilchenko, I.; Demin, E.

    1994-01-01

    The most general design features of WWER-1000 fuel assembly are discussed. The following advantages of design are stated as well as their operational confirmation and occurrences: 1) 'packing' density (tight-lattice) of fuel rods within the fuel assemblies; 2) simple handling of fuel assemblies and its small vulnerability; 3) good conditions for coolant mixing; 4) protection of the absorber rods against coolant effect; 5) adaptability to manufacture that provides stable quality. The main operational indices gathered during a ten-year period (1982-1992) at 17 WWER-1000 units in Russia and Ukraine are outlined. Provisions for emergency protection reliability are described. Future directions to improve fuel economy and control rod operability are discussed. 1 fig

  20. Modelling of WWER-1000 fuel: state and prospects

    Energy Technology Data Exchange (ETDEWEB)

    Medvedev, A; Bibilashvili, Yu; Bogatyr, S; Khvostov, G [Vsesoyuznyj Nauchno-Issledovatel` skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)

    1994-12-31

    The role of START-3 code in studying and computerized modelling of post-irradiation behaviour of standard fuel rods in real operation conditions of WWER-1000 reactors is described. The models used in the code are based on experimental study of material properties, processes and post irradiation research on standard and experimental fuel pins. The code capability is verified by comparison with data from experiments on WWER test rods performed in MR reactor, the Russia-Finland tests SOFIT and the international program FUMEX. The comparison performed and the results thus obtained demonstrate the satisfactory ability of START-3 code to simulate fuel rod behaviour in normal operation condition. The calculations confirm the experimentally observed evidence of an essential margin on serviceability of WWER-1000 fuel pin with three year operation cycle permitting an increase in design fuel burnup. 2 tabs., 18 figs.

  1. Operational indices of WWER-1000 fuel assemblies and their improvements

    Energy Technology Data Exchange (ETDEWEB)

    Vasilchenko, I; Demin, E [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation)

    1994-12-31

    The most general design features of WWER-1000 fuel assembly are discussed. The following advantages of design are stated as well as their operational confirmation and occurrences: (1) `packing` density (tight-lattice) of fuel rods within the fuel assemblies; (2) simple handling of fuel assemblies and its small vulnerability; (3) good conditions for coolant mixing; (4) protection of the absorber rods against coolant effect; (5) adaptability to manufacture that provides stable quality. The main operational indices gathered during a ten-year period (1982-1992) at 17 WWER-1000 units in Russia and Ukraine are outlined. Provisions for emergency protection reliability are described. Future directions to improve fuel economy and control rod operability are discussed. 1 fig.

  2. Safety of NPP with WWER-440 and WWER-1000 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Balabanov, E [Energoproekt, Sofia (Bulgaria); Gledachev, J; Angelov, D [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1996-12-31

    The WWER-440 and WWER-1000 reactors used at the Kozloduy NPP have been analyzed in terms of safety. There are currently 4 reactors WWER-440/230 and 2 reactors WWER-1000/320. The former do not comply completely with the modern safety requirements due to the regulations acted in the sixties when they have been designed. The main features of these reactors are: low power density in the core; three levels of reactor control and protection; six primary loops; horizontal steam generators; two turbines; large number of cross-unit connections. The low thermal density in the core, the low specific thermal loading in the rods and the large coolant inventory enhance the safety, while the major deficiencies are identified as follows: insufficient capabilities for emergency core cooling; low diversification and physical separation of the safety systems; old fashioned control systems; inadequate fire protection; lack of full containment. It is pointed out that several design and operation actions have been completed in the Kozloduy NPP in order to enhance their safety. The WWER-1000 units are 320 model and feature a high safety level, complying completely with OPB-82 regulations and with all current international safety standards. 3 refs., 7 figs., 1 tab.

  3. Safety of NPP with WWER-440 and WWER-1000 reactors

    International Nuclear Information System (INIS)

    Balabanov, E.; Gledachev, J.; Angelov, D.

    1995-01-01

    The WWER-440 and WWER-1000 reactors used at the Kozloduy NPP have been analyzed in terms of safety. There are currently 4 reactors WWER-440/230 and 2 reactors WWER-1000/320. The former do not comply completely with the modern safety requirements due to the regulations acted in the sixties when they have been designed. The main features of these reactors are: low power density in the core; three levels of reactor control and protection; six primary loops; horizontal steam generators; two turbines; large number of cross-unit connections. The low thermal density in the core, the low specific thermal loading in the rods and the large coolant inventory enhance the safety, while the major deficiencies are identified as follows: insufficient capabilities for emergency core cooling; low diversification and physical separation of the safety systems; old fashioned control systems; inadequate fire protection; lack of full containment. It is pointed out that several design and operation actions have been completed in the Kozloduy NPP in order to enhance their safety. The WWER-1000 units are 320 model and feature a high safety level, complying completely with OPB-82 regulations and with all current international safety standards. 3 refs., 7 figs., 1 tab

  4. The summary of WWER-1000 fuel utilization in Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Afanasyev, A [Ukrainian State Committee on Nuclear Power Utilization, Kiev (Ukraine)

    1997-12-01

    The report discusses the status of the fuel and fuel cycles of WWER-1000 reactors in Ukraine. The major reasons that caused the Ukrainian utilities to overcome the conservative design solutions in order to improve fuel utilization and extend fuel burnup are shown. At the same time the sufficient fuel reliability and fuel cycle flexibility are ensured. The burnup distribution in the unloaded fuel assemblies and average fuel rod failure rate are presented. The questions of reactor core operation safety and the economical problems of the front end of the fuel cycle are also considered. (author). 2 refs, 3 figs, 4 tabs.

  5. Control rod drive WWER 1000 – tuning of input parameters

    Directory of Open Access Journals (Sweden)

    Markov P.

    2007-10-01

    Full Text Available The article picks up on the contributions presented at the conferences Computational Mechanics 2005 and 2006, in which a calculational model of an upgraded control rod linear stepping drive for the reactors WWER 1000 (LKP-M/3 was described and results of analysis of dynamical response of its individual parts when moving up- and downwards were included. The contribution deals with the tuning of input parameters of the 3rd generation drive with the objective of reaching its running as smooth as possible so as to get a minimum wear of its parts as a result and hence to achieve maximum life-time.

  6. Neutron physics calculation for WWER-1000 absorber element lifetime determination

    International Nuclear Information System (INIS)

    Kurakin, K.Yu.; Kushmanov, S.A.

    2009-01-01

    Absorber element with compound absorber has been operating in WWER-1000 power units since 1995. AE design meets operating organizations requirements for reliability, service life (to 10 years) and safety functions. Extension of AE service life up to 20 - 30 years by the complex of calculation and experimental work is an important problem of WWER new designs development. The paper deals with the issues related to calculation determination of main factors that influence AE service life limitation - neutron flux and fluence onto absorbing and structural materials during extended service life. (Authors)

  7. Enhanced Westinghouse WWER-1000 fuel design for Ukraine reactors

    International Nuclear Information System (INIS)

    Dye, M.; Shah, H.

    2015-01-01

    Westinghouse has completed design, development, and region quantity delivery of an enhanced Westinghouse fuel assembly for WWER-1000 reactors to support continued safe reactor operations. The enhanced design builds on the successful performance of an earlier generation design which has operated in the South Ukraine 3 reactor for multiple cycles without any fuel rod failures. Incorporated design enhancements include a thicker spacer grid outer strap, an enhanced spacer grid outer strap profile to limit the risk for, and impact of, mechanical interaction/interference with coresident fuel, an all Alloy 718 grid structure for improved stability and strength, and improvements to the top and bottom nozzles. Capable of meeting increased lateral loads generated from using a higher axial trip limit for the refueling machine crane, the design was verified by extensive mechanical and thermalhydraulic testing, which included a newly developed fuel assembly-to-fuel assembly handling test rig to assess performance during bounding core loading and unloading conditions. Through these extensive design enhancements and comprehensive testing program, the enhanced WWER-1000 design provides additional performance, handling, and reliability margins for safe reactor operation. (authors)

  8. Evaluation of WWER-1000 vessel materials fracture toughness

    International Nuclear Information System (INIS)

    Grinik, Eh.U.; Revka, V.N.; Chirko, L.I.; Chajkovskij, Yu.V.

    2007-01-01

    The lifetime of WWER-1000-type reactor vessels is finally conditioned by the fracture toughness (crack growth resistance) of RPV materials. Up to now in line with the regulations the fracture toughness is characterized by the critical temperature of brittleness determined by the results of the Charpy specimen impact testing. Such approach is typical for all countries operating the water pressure reactors. However, regulatory approach is known from the western specialists not always to characterize adequately the crack growth resistance of the vessel materials and in some cases to underestimate their characteristics in the reference state that leads to unreasonably high conservatism. Excessive conservatism may lead to the invalid restrictions in the operating modes and the service life of the reactor vessel. Therefore there appeared the necessity to apply another approaches based on the state-of-the-art experimental methods of the fracture mechanics and allowing evaluating the fracture toughness parameters sufficiently. The paper presents the results of the comparison of the regulatory approach and the Master curve approach from the point of view of the adequate determination of the vessel material crack growth resistance parameters. Analysis of the experimental data of the surveillance specimens illustrated the potential possibility of applying the new statistical method for the WWER-1000- type reactor vessel lifetime extension

  9. Nuclear power plants with reactors WWER-1000 type: today and tomorrow; AEhS s WWER-1000: nastoyashchee i budushchee

    Energy Technology Data Exchange (ETDEWEB)

    Molchanov, V; Biryukov, G; Novak, K [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation)

    1996-12-31

    There are currently 19 NPP units based on WWER-1000 reactors working in Russia, Ukraine and Bulgaria. They are of four types: V-187, V-302, V-338, V-320. The design principles of these reactors comply with regulations of the eighties, and it is necessary to introduce improvements according to the new regulations and to the operation experience gained. Two approaches for safety and efficiency enhancement are described: AS-91 and AS-92. AS-91 implies gradual improvement of the base WWER-1000/V-320 design by incorporation of new design solutions avoiding the need of building large scale models. AS-92 refers to entirely new design which require experimental research by building a full scale models or by using natural stands. The latter approach will be used for NPP projects to be built after year 2000. The main new feature of AS-92 is the addition of passive safety systems to the active ones in order to protect the fuel from damage.

  10. Consistent Code Qualification Process and Application to WWER-1000 NPP

    International Nuclear Information System (INIS)

    Berthon, A.; Petruzzi, A.; Giannotti, W.; D'Auria, F.; Reventos, F.

    2006-01-01

    Calculation analysis by application of the system codes are performed to evaluate the NPP or the facility behavior during a postulated transient or to evaluate the code capability. The calculation analysis constitutes a process that involves the code itself, the data of the reference plant, the data about the transient, the nodalization, and the user. All these elements affect one each other and affect the results. A major issue in the use of mathematical model is constituted by the model capability to reproduce the plant or facility behavior under steady state and transient conditions. These aspects constitute two main checks that must be satisfied during the qualification process. The first of them is related to the realization of a scheme of the reference plant; the second one is related to the capability to reproduce the transient behavior. The aim of this paper is to describe the UMAE (Uncertainty Method based on Accuracy Extrapolation) methodology developed at University of Pisa for qualifying a nodalization and analysing the calculated results and to perform the uncertainty evaluation of the system code by the CIAU code (Code with the capability of Internal Assessment of Uncertainty). The activity consists with the re-analysis of the Experiment BL-44 (SBLOCA) performed in the LOBI facility and the analysis of a Kv-scaling calculation of the WWER-1000 NPP nodalization taking as reference the test BL-44. Relap5/Mod3.3 has been used as thermal-hydraulic system code and the standard procedure adopted at University of Pisa has been applied to show the capability of the code to predict the significant aspects of the transient and to obtain a qualified nodalization of the WWER-1000 through a systematic qualitative and quantitative accuracy evaluation. The qualitative accuracy evaluation is based on the selection of Relevant Thermal-hydraulic Aspects (RTAs) and is a prerequisite to the application of the Fast Fourier Transform Based Method (FFTBM) which quantifies

  11. Fuel cycles of WWER-1000 based on assemblies with increased fuel mass

    International Nuclear Information System (INIS)

    Kosourov, E.; Pavlovichev, A.; Shcherenko, A.

    2011-01-01

    Modern WWER-1000 fuel cycles are based on FAs with the fuel column height of 3680 mm, diameters of the fuel pellet and its central hole of 7.6 and 1.2 mm respectively. The highest possible fuel enrichment has reached its license limit that is 4.95 %. Research in the field of modernization, safety justification and licensing of equipment for fuel manufacture, storage and transportation are required for further fuel enrichment increase (above 5 %). So in the nearest future an improvement of technical and economic characteristics of fuel cycles is possible if assembly fuel mass is increased. The available technology of the cladding thinning makes it possible. If the fuel rod outer diameter is constant and the clad inner diameter is increased to 7.93 mm, the diameter of the fuel pellet can be increased to 7.8 mm. So the suppression of the pellet central hole allows increasing assembly fuel weight by about 8 %. In this paper we analyze how technical and economic characteristics of WWER-1000 fuel cycle change when an advanced FA is applied instead of standard one. Comparison is made between FAs with equal time interval between refueling. This method of comparison makes it possible to eliminate the parameters that constitute the operation component of electricity generation cost, taking into account only the following technical and economic characteristics: 1)cycle length; 2) average burnup of spent FAs; 3) specific natural uranium consumption; 4)specific quantity of separative work units; 5) specific enriched uranium consumption; 6) specific assembly consumption. Collected data allow estimating the efficiency of assembly fuel weight increase and verifying fuel cycle characteristics that may be obtained in the advanced FAs. (authors)

  12. Methodology of thermalhydraulic tests of fuel assemblies for WWER-1000

    International Nuclear Information System (INIS)

    Archipov, A.; Kolochko, V.N.

    2001-01-01

    At present 11 units with WWER-1000 are in operation in Ukraine. The NPPs are provided with nuclear fuel from Russia. The fuel assemblies are fabricated and delivered to Ukrainian NPPs from Russia. However the contemporary tendencies of nuclear energy development in the world assume a diversification of nuclear fuel vendors. Therefore the creation of the own nuclear fuel cycle of Ukraine is in mind in the strategy of nuclear energy development of Ukraine. As a part of the fuel assemblies fabrication process complex of the thermalhydraulic tests should be carried out to confirm design characteristics of the fuel assemblies before they are loaded in the reactor facility. The experimental basis and scientific infrastructure for the thermalhydraulic tests arrangement and realization of the programs and procedures for the core equipment examination are under consideration. (author)

  13. Performance of the Westinghouse WWER-1000 fuel design

    International Nuclear Information System (INIS)

    Höglund, J.; Jansson, A.; Latorre, R.; Davis, D.

    2015-01-01

    In 2005, six (6) Westinghouse WWER-1000 Lead Test Assemblies (LTAs) were loaded in South Ukraine Unit 3 (SU3). The LTAs completed the planned four cycles of operation and reached an average assembly burnup in excess of 43 MWd/ kgU. Post Irradiation Examination (PIE) inspections were performed after completion of each cycle and it was concluded that the 6 Westinghouse LTAs performed as expected during their operational regimes. In 2010, a full region of 42 assemblies of an enhanced WWER-1000 fuel design for Ukrainian reactors, designated WFA, was loaded in SU3. The WFA includes features that further mitigate assembly bow while at the same time improving the fuel cycle economy. In 2015, 26 WFAs completed their planned four cycles of operation reaching an average assembly burnup in excess of 42 MWd/ kgU. Currently 36 WFAs continue operating their fourth cycle in SU3. In addition, South Ukraine Unit 2 (SU2) has been loaded with WFAs and 27 assemblies have completed two cycles of operation reaching an average assembly burnup above 24 MWd/kgU. PIE for the WFAs has been completed after each cycle of operation. All assemblies have been examined for visible damage or non-standard position of fuel assembly components during unloading and reloading. All WFAs have also been subject to the standard leak testing process, with all fuel rods found to be hermetically sealed and non-leaking. Each outage, six WFAs have been subject to a more extensive inspection program. In 2012, 2013, and 2015, the Westinghouse Fuel Inspection and Repair Equipment (FIRE) workstation were used for the SU3 inspections. Excellent irradiation fuel performance has been observed and measured on all WFAs. The fuel assembly growth, rod cluster control assembly (RCCA) drag forces, oxide thickness, total fuel rod-to-nozzle gap channel closure, and fuel assembly bow data were within the bounds of the Westinghouse experience database. Results and concluding remarks from the PIEs are provided in this paper. In

  14. Analysis of WWER 1000 SG cold collector cracking

    International Nuclear Information System (INIS)

    Matocha, K.; Wozniak, J.

    2000-01-01

    Following the recommendations of the 1993 consultants' meeting on 'Steam Generator Collector Integrity of WWER 1000 Reactors', an extensive experimental program was started with the aim of finding the dominant damage mechanism responsible for cold collector cracking in steam generators, and of determining whether proper operating conditions can make the operation of VITKOVICE-produced steam generators safe throughout their lifetime. The experiments consisted of: a study of the effect of strain and thermal ageing and dissolved oxygen content on subcritical crack growth in 10GN2MFA steel; a study of the effect of high temperature water and tube expansion technology on the fracture behaviour of ligaments between holes for heat exchange tubes; a study of the effect of drilling, tube expansion technology and heat treatment on residual stresses on the surface of holes for heat exchange tubes. Details of the experimental techniques used are given as well as a discussion of the results obtained and presented in tables and graphs. (A.K.)

  15. Upgrading of WWER-1000 NPP safety on spent fuel transportation

    International Nuclear Information System (INIS)

    Kostarev, V.; Shchukin, A.; Petrenya, Yu.; Nikitin, V.; Romanovskij-Romanko, A.; Shevchenko, V.

    2003-01-01

    Transportation process for the WWER-1000 spent fuel assemblies consists of three main steps: (i) lifting of unloaded cask on the elevation of +38.05 m; (ii) loading of spent fuel assemblies into the cask; (iii) loaded cask lowering to the conveyer located in the transport corridor on the elevation 0.00 m. The most hazardous situation within described process for the cask itself and reactor building structures is an accidental drop of the cask from the height of 38.05 m to the transport corridor floor due to failure of traverse or crane's cable break. According to international practice and standards' requirements the cask shall be designed for the drop from 9 meters height to a rigid plate. However, preliminary analyses have shown that in case of 38 m drop the value of g-loads are several times larger than allowable limits. Additionally, strength capacity of the foundation slab of the reactor building is not guaranteed. Using of special damping device that is capable to bring dynamic loads to allowable limits could mitigate the catastrophic consequences of cask's 38.05 meters drop. The paper presents a basic design of the special damping platform and discusses results of analyses of different modes of cask drops and efficiency of the proposed solution. (author)

  16. Fuel assembly leak tightness control on WWER-1000 reactor

    International Nuclear Information System (INIS)

    Ivanova, R.; Gerchev, N.; Mateev, A.

    2001-01-01

    The main index for integrity of the fuel rods cladding is the specific activity value of the primary coolant. This value determines the safe operation of the reactor. The limit for safe operation of WWER-1000 reactor is the value of the total activity of Iodine isotopes in the primary coolant 5.0x10 -3 Ci/l. The paper briefly describes the methodology for performing a fuel tightness test (sipping test) and shows the results from these tests performed during the period 1987 -1999 in units 5 and 6 at the Kozloduy NPP. An additional index related to the safe operation is defined to characterize the fuel cladding integrity Fuel Reliability Index (FRI). The FRI is defined as value of the average activity of 131 I in the primary coolant, corrected with a part of precipitated 235 U migration and fixed to the general permanent purification frequency. Two criteria (quantitative and statistic) are determined to qualify the fuel cladding integrity. The results from sipping tests show good reliability of the fuel irradiated in unit 5 and 6 at the Kozloduy NPP

  17. Dynamic analysis of WWER-1000 nuclear power plants

    International Nuclear Information System (INIS)

    Asfura, A.P.; Jordanov, M.J.

    1995-01-01

    As part of the effort to assess the seismic vulnerability of nuclear power plants in Eastern Europe, a series of dynamic analyses have been carried out for several plants. These analyses were performed using modern analysis techniques, current local seismic parameters, and local soil profiles. This paper presents a compilation of some of the seismic analyses performed for the WWER-1000 reactor buildings at the nuclear power plants of Belene and Kozloduy in Bulgaria, and Temelin in the Czech Republic. The reactor buildings at these three plants are practically identical and correspond to the standard building design for this type of reactors. The series of analyses performed for these buildings encompasses various soil profiles, seismic ground motions, and different soil-structure interaction analysis techniques and modelling. The analysis of a common structure under different conditions gives the opportunity to assess the relative importance that each of the analysis elements has in the structural responses. The use of different SSI computer programs and foundation modeling was studied for Kozloduy, and the effects of different soil conditions and site-specific seismicity were studied by comparing the responses for the three plants. In-structure acceleration response spectra were selected as the structural responses for comparison purposes

  18. Modal analysis of spent fuel cask for WWER-1000 reactors

    International Nuclear Information System (INIS)

    Azimfar, S. A.; Kazemi, A.

    2011-01-01

    The Spent Fuel Assemblies of WWER-1000 reactors are planned to be transported by special containers which are supposed to be designed in a manner to stand against vibrations and impacts in order to protect the spent fuel from any possible damage. The vibration opposition of these containers shall be far beyond the critical resonance, because the resonances about the natural frequency of the structure will cause the enhancement of its oscillation range and may end with its disintegration. Determination of the amounts of natural frequencies and their mode shape can be achieved by vibration analyzing methods. The amount of the natural frequency of any structure crucially depends on its shape, material and lean points as well as the amount of the loads and the type of these loads. Due to the fact that the Spent Fuel Casks used for transportation in nuclear power plants in Russian Federation are TK-13 type and the pieces of information released are negligible, the scientists in Russia are working on the design and analysis of a new type made up of composite Material. In the presented paper the cask of spent fuel of TK-13 is modeled by ANSYS at 10.0 and ten natural frequency modes have been calculated, followed by the comparison of this result with the composite cask.

  19. Accidents during shutdown conditions for NPP with WWER-1000/428

    International Nuclear Information System (INIS)

    Antropov, H.A.

    1996-01-01

    This paper considers the effect of such internal initiating events upon safety of the NPP with WWER-1000/428 as boron dilution and loss of residual heat removal at the reduced coolant inventory in the primary circuit. 2 refs

  20. Comparative severe accident analysis of WWER 1000/B 320 LOCA DN100 computed by computer codes ASTEC V1.1 and SCDAP/RELAP5

    International Nuclear Information System (INIS)

    Kalchev, B.; Dimov, D.; Tusheva, P.; Mladenov, I.

    2005-01-01

    This paper presents the modelling approach for LOCA 100 mm sequence for WWER 1000-B 320 type of reactor with the integral ASTEC computer code and SCDAP/RELAP5 computer code. As a basic input deck the reference input file for Balakovo NPP from the released ASTEC CD has been applied. As a first part of the calculations for the SBLOCA sequence the ASTEC v1.1 modules CESAR, DIVA and CPA have been activated in a coupled mode. For SCDAP/RELAP5 calculation input deck for WWER 1000-B 320 has been applied which meant to be closer to the initial boundary conditions applied for ASTEC WWER 1000 input deck. A SBLOCA 100 mm comparison between ASTEC v1.1 and SCADAP/RELAP5 has been presented. ASTEC predicts vessel failure at 15620 s. ASTEC and SCDAP/RELAP5 give close but not similar results - this could be observed on the trends. The comparison of 100 mm-break shows that SCDAP/RELAP5 predicts clear phenomenological changes in primary pressure evolution and molten pool formation. Similar hydrogen production mass for both codes around 5000 s is detected

  1. Experimental assessment of welded joints brittle fracture on the crack arrest criterion for WWER-1000 RPV

    International Nuclear Information System (INIS)

    Blumin, A.A.; Timofeev, B.T.

    2000-01-01

    The crack arrest fracture toughness in a vessel steel used in WWER-1000 reactor, namely in steel 15Kh2NMFA and its submerged arc welded joints, produced with Sv-08KhGNMTA, Sv-12 Kh2NMFA welding wires and NF-18 M, FZ-16 A welding fluxes, is under study. Experimental studies are carried out using three heats with the chemical composition meeting the specifications. Weld specimens 100-200 mm thick are subjected to tempering according various regimes to induce the embrittlement and simulate mechanical properties (yield strength and ductile-brittle transition temperature) corresponding to those at the end of service life under neutron radiation effect. Base metal and weld properties are compared. The wide scatter is noted for experimental data on fracture toughness temperature dependences. A possibility to use the dependence of K Ia = f (T-T k ) for determining the crack arrest fracture toughness is discussed taking in account that K Ia is a stress intensity factor calculated within the frame of static fracture mechanics [ru

  2. Solution of the 'MIDICORE' WWER-1000 core periphery power distribution benchmark by KARATE and MCNP

    International Nuclear Information System (INIS)

    Temesvari, E.; Hegyi, G.; Hordosy, G.; Maraczy, C.

    2011-01-01

    The 'MIDICORE' WWER-1000 core periphery power distribution benchmark was proposed by Mr. Mikolas on the twentieth Symposium of AER in Finland in 2010. This MIDICORE benchmark is a two-dimensional calculation benchmark based on the WWER-1000 reactor core cold state geometry with taking into account the geometry of explicit radial reflector. The main task of the benchmark is to test the pin by pin power distribution in selected fuel assemblies at the periphery of the WWER-1000 core. In this paper we present our results (k eff , integral fission power) calculated by MCNP and the KARATE code system in KFKI-AEKI and the comparison to the preliminary reference Monte Carlo calculation results made by NRI, Rez. (Authors)

  3. An investigation of axial xenon stability in WWER-1000 reactor designs

    International Nuclear Information System (INIS)

    Doshi, P.K.; Miller, R.W.

    1993-01-01

    The nuclear power plants of the WWER-1000 design have experienced frequent xenon oscillation control problems. In most PWRs, xenon oscillations are largely a problem in the axial direction. An one dimensional core model representative of the WWER-1000 design was set up to examine the controllability of the current design. An investigation of possible improvements to this design was made. There was no indication that xenon oscillations were an inherent problem in WWER-1000 core design. Simple changes to the control rod system coupled with a sound power distribution control strategy that has been proven to be an effective but simple procedure to follow, eliminate xenon control problems. The changes proposed can be implemented in a very cost effective manner. There are no equipment changes needed, existing control rods can be used. Only software changes are required. (Z.S.) 1 tab., 2 figs., 7 refs

  4. Improvement of operational performance and increase of safety of WWER-1000/V-392

    International Nuclear Information System (INIS)

    Kurakov, Y.A.; Dragunov, Y.G.; Podshibiakin, A.K.; Fil, N.S.; Krushelnitsky, V.N.; Berkovich, V.M.

    2001-01-01

    The national programme of nuclear power development approved by the Russian Federation Government in 1998 considers the design of WWER-1000/V-392 power unit as a priority project of the new generation NPP with improved operational performances and increased safety. The pilot unit of this design (NVAES-2) is licensed for construction at the Novovoronezh NPP site. The NVAES-2 design is developed on the basis of standard power unit with reactor plant V-320. Twenty units of this type are in operation at the nuclear power plants in Russia, Ukraine and Bulgaria having totally about 270 reactor-years of operation. Two more V-320 units are being commissioned this year at Rostov NPP and Temelin NPP. So, the WWER-1000/V-392 design is as a whole an evolutionary development of the operating standard unit WWER-1000/V-320. Many technical solutions aimed at increase of safety and improvement of operational performance of the plant are implemented in the NVAES-2 design, such as advanced reactor WWER-1000, passive system of residual power removal, passive system of the core flooding under loss-of-coolant accidents, and others. NVAES-2 design refers to a class of advanced light water reactors and corresponds to the international requirements imposed to the nuclear power plants to be put into operation after the year 2000. New V-392 power unit has a good perspective from the view point of extensive implementation in the framework of the nuclear electricity production in Russia. Design decisions on NVAES-2 power unit with WWER-1000/V-392 reactor plant which assure significantly higher safety level and improve economical performance as compared to the operating WWER-1000 units are briefly considered in the present paper. (author)

  5. Systems required during and after an earthquake. Summary report. WWER-1000 nuclear power plants

    International Nuclear Information System (INIS)

    Monette, P.

    1995-01-01

    The scope of this document is to list the mechanical, instrumentation and electrical components required during and after earthquake, in order to achieve and maintain safe shutdown conditions of a WWER-1000 type nuclear power plant. The main objective pursued in establishing the systems and equipment list is to provide guidance for the design and implementation of the backfits which are necessary to increase seismic resistance of the components required after earthquake. The presented list is established on generic basis, i.e. it is applicable to any specific WWER-1000

  6. ACT-1000. Group activation cross-section library for WWER-1000 type reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zolotarev, K I; Pashchenko, A B [National Research Centre - A.I. Leipunsky Institute for Physics and Power Engineering, Obninsk (Russian Federation)

    2001-10-01

    The ACT-1000, a problem-oriented library of group-averaged activation cross-sections for WWER-1000 type reactors, is based on evaluated microscopic cross-section data files. The ACT-1000 data library was designed for calculating induced activity for the main dose-generated nuclides contained in WWER-1000 structural materials. In preparing the ACT-1000 library, 47 group-averaged cross-section data for the 10{sup -9}-17.33 MeV energy range were used to calculate the spatial-energy neutron flux distribution. (author)

  7. Electroerosion cutting of low-sized templets from WWER-1000 type reactor vessel

    International Nuclear Information System (INIS)

    Neklyudov, I.M.; Ozhigov, L.S.; Gozhenko, S.V.

    2012-01-01

    The article presents the results of developed method of electroerosion cutting of low-sized templets for the reactor vessel metal composition and structure control in laboratory environment. The article describes the equipment for the remote electroerosive cutting of templets from WWER-1000 type reactor vessel by rigid electrode. The testing results are also shown.

  8. Steam generator and condenser design of WWER-1000 type of nuclear power plant

    International Nuclear Information System (INIS)

    Zare Shahneh, Abolghasem.

    1995-03-01

    Design process of steam generator and condenser at Russian nuclear power plant type WWER-1000 is identified. The four chapter of the books are organized as nuclear power plant, types of steam generators specially horizontal steam generator, process of steam generator design and the description of condenser and its process design

  9. The solution of the LEU and MOX WWER-1000 calculation benchmark with the CARATE - multicell code

    International Nuclear Information System (INIS)

    Hordosy, G.; Maraczy, Cs.

    2000-01-01

    Preparations for disposition of weapons grade plutonium in WWER-1000 reactors are in progress. Benchmark: Defined by the Kurchatov Institute (S. Bychkov, M. Kalugin, A. Lazarenko) to assess the applicability of computer codes for weapons grade MOX assembly calculations. Framework: 'Task force on reactor-based plutonium disposition' of OECD Nuclear Energy Agency. (Authors)

  10. Technological problems connected with execution of the protection sheets for nuclear power sets WWER-1000

    International Nuclear Information System (INIS)

    Hajutin, J.G.; Kriczewskij, A.Z.

    1977-01-01

    The choice of the structure and the prestressing system of the R.C. protection sheet for nuclear power sets WWER-1000 is motivated. The technological problems arised during the execution stage, as well as the technological line producing the tendons to prestress the structure by up winding are presented. (author)

  11. Draft report of a consultants meeting on core control and protection strategy of WWER-1000 reactors. Extrabudgetary programme on the safety of WWER-1000 NPPs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-07

    At the consultants' meeting on the 'Safety of WWER-1000 Model 320 Nuclear Power Plants' organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of core control and protection strategy was identified as an issue of safety concern. Considering the safety importance of this issue, a consultants' meeting on 'Core Control and Protection Strategy for WWER-1000 Reactors' was convened in Vienna in April 1994 attended by 20 international experts in the area of core control and protection in order to review control and protection system design, to compare them with western practices and to recommend corrective measures. The first WWER-1000 NPP was put into operation in 1980 and there are currently 19 units operating. The accumulated operational experience is more than 130 reactor-years. In addition, there are 8 units under various stages of construction. The previous general observations in the area of core control and protection strategy was focused on core design objectives, core design and fuel management, fuel assembly and core component designs, including burnable absorber and control rod designs, core power distribution control strategy, core control and protection system designs and in-core and ex-core instrumentation systems. While core design objectives of WWER-1000 plants are similar to western practices in general, there are important differences on the design limits and regulatory practices followed for the compliance with the design limits. As a result of previous general observations and specific concerns on core control and protection system design, three working groups were formed to further investigate the specific issues and to compile information on safety issues based on design differences between these plants and similar western plants, to identify areas which need further analysis and make recommendations for short-term and long-term corrective

  12. Draft report of a consultants meeting on core control and protection strategy of WWER-1000 reactors. Extrabudgetary programme on the safety of WWER-1000 NPPs

    International Nuclear Information System (INIS)

    1994-01-01

    At the consultants' meeting on the 'Safety of WWER-1000 Model 320 Nuclear Power Plants' organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of core control and protection strategy was identified as an issue of safety concern. Considering the safety importance of this issue, a consultants' meeting on 'Core Control and Protection Strategy for WWER-1000 Reactors' was convened in Vienna in April 1994 attended by 20 international experts in the area of core control and protection in order to review control and protection system design, to compare them with western practices and to recommend corrective measures. The first WWER-1000 NPP was put into operation in 1980 and there are currently 19 units operating. The accumulated operational experience is more than 130 reactor-years. In addition, there are 8 units under various stages of construction. The previous general observations in the area of core control and protection strategy was focused on core design objectives, core design and fuel management, fuel assembly and core component designs, including burnable absorber and control rod designs, core power distribution control strategy, core control and protection system designs and in-core and ex-core instrumentation systems. While core design objectives of WWER-1000 plants are similar to western practices in general, there are important differences on the design limits and regulatory practices followed for the compliance with the design limits. As a result of previous general observations and specific concerns on core control and protection system design, three working groups were formed to further investigate the specific issues and to compile information on safety issues based on design differences between these plants and similar western plants, to identify areas which need further analysis and make recommendations for short-term and long-term corrective

  13. Substantiation of operation limits of reactivity insertion during WWER-1000 reactors start-up; Obosnovanie ehkspluatatsionnykh predelov vvoda reaktivnosti pri puske reaktorov WWER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Boev, I; Sabitov, A; Sal` kov, V; Sudarev, O; Yakovlev, A [ATOMTECHENERGO RF, Novovoronezh (Russian Federation)

    1996-12-31

    The methods and programmes used to define the tolerable rate of reactivity insertion during WWER-1000 start-up are presented. They include calculation of the neutron source power in the core during the sub-critical stage and calculation of the relative neutron density and reactor period during the critical stage. The need for optimisation and regulation of tolerable rates is discussed along with the tool parameters affecting the reactivity during start-up. The possibility of increasing the feed rate of pure condensate into the first loop during the time needed to reach critical stage is justified. 4 refs., 3 tabs.

  14. Methodology for the evaluation of tolerability of defects in WWER-1000/V-320 reactor pressure vessels

    International Nuclear Information System (INIS)

    Brumovsky, M.; Horacek, L.; Ruscak, M.

    1996-05-01

    The methodology provides guidelines for the assessment of tolerability of defects found during in-service inspection of the base material and overlay of WWER-1000/V-320 type reactor pressure vessels. With regard to the method of calculating the tolerability of defects and rules for the preparation and implementation of repairs, this methodology can also find use in the assessment of tolerability of defects in selected facilities of WWER-1000/V-320 type nuclear power plants provided that adequate input data concerning the materials, manufacturing technology, and operating load regime are available and that the facilities are made of ferrite/bainite type steels. This methodology should serve as a binding document underlying the development of a technical approach to provisions for a further operation of facilities in which intolerable defects have been found by nondestructive testing. (author)

  15. Stainless steel corrosion in conditions simulating WWER-1000 primary coolant. Corrosion behaviour in mixed core

    International Nuclear Information System (INIS)

    Krasnorutskij, V.S.; Petel'guzov, I.A.; Gritsina, V.M.; Zuek, V.A.; Tret'yakov, M.V.; Rud', R.A.; Svichkar', N.V.; Slabospitskaya, E.A.; Ishchenko, N.I.

    2011-01-01

    Research into corrosion kinetics of austenitic stainless steels (06Cr18Ni10Ti, 08Cr18Ni10Ti, 12Cr18Ni10Ti) in medium which corresponds to composition and parameters of WWER-1000 primary coolant with different pH values in autoclave out-pile conditions during 14000 hours is given. Surface of oxide films on stainless steels is investigated. Visual inspection of Westinghouse and TVEL fuel was carried out after 4 cycles in WWER-1000 primary water chemistry conditions at South Ukraine NPP. Westinghouse and TVEL fuel cladding materials possess high corrosion resistance. Blushing of weldments was observed. No visual corrosion defects or deposits were observed on fuel rods.

  16. Vibrodynamical tests of RP equipment with application of imitation area of WWER-1000 reactor

    International Nuclear Information System (INIS)

    Khajretdinov, V.U.; Tarkhanov, V.V.; Rodionova, I.N.

    2015-01-01

    Performance of preoperational tests and measurements with application of imitation area of the reactor is a distinctive characteristic of putting into operation of NPP Units with WWER-1000/1200. The imitation area consists of 163 full-scale FA models, where fuel matrixes made of nuclear-fissionable material, are replaced by leaden simulators. Vibrodynamic tests involve inspection of hydrodynamic disturbances in the primary circuit (dynamic impact on the inspected elements), characteristics of vibration response of the main equipment stress-deformed state of bearing structure, and also parameters of moving and geometry of the inspected objects (boundary conditions at process simulation). Preoperational tests and measurements on the simulated area of WWER-1000/1200 are obligatory and performed at every unit of NPP of this type [ru

  17. Application of the LBB regulatory approach to the steamlines of advanced WWER 1000 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kiselyov, V.A.; Sokov, L.M.

    1997-04-01

    The LBB regulatory approach adopted in Russia in 1993 as an extra safety barrier is described for advanced WWER 1000 reactor steamline. The application of LBB concept requires the following additional protections. First, the steamline should be a highly qualified piping, performed in accordance with the applicable regulations and guidelines, carefully screened to verify that it is not subjected to any disqualifying failure mechanism. Second, a deterministic fracture mechanics analysis and leak rate evaluation have been performed to demonstrate that postulated through-wall crack that yields 95 1/min at normal operation conditions is stable even under seismic loads. Finally, it has been verified that the leak detection systems are sufficiently reliable, diverse and sensitive, and that adequate margins exist to detect a through wall crack smaller than the critical size. The obtained results are encouraging and show the possibility of the application of the LBB case to the steamline of advanced WWER 1000 reactor.

  18. Application of the LBB regulatory approach to the steamlines of advanced WWER 1000 reactor

    International Nuclear Information System (INIS)

    Kiselyov, V.A.; Sokov, L.M.

    1997-01-01

    The LBB regulatory approach adopted in Russia in 1993 as an extra safety barrier is described for advanced WWER 1000 reactor steamline. The application of LBB concept requires the following additional protections. First, the steamline should be a highly qualified piping, performed in accordance with the applicable regulations and guidelines, carefully screened to verify that it is not subjected to any disqualifying failure mechanism. Second, a deterministic fracture mechanics analysis and leak rate evaluation have been performed to demonstrate that postulated through-wall crack that yields 95 1/min at normal operation conditions is stable even under seismic loads. Finally, it has been verified that the leak detection systems are sufficiently reliable, diverse and sensitive, and that adequate margins exist to detect a through wall crack smaller than the critical size. The obtained results are encouraging and show the possibility of the application of the LBB case to the steamline of advanced WWER 1000 reactor

  19. Modeling of coherent heat and mass-exchange phenomena for a specter of primary circuit leaks in a NPP with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Stanev, I.; Mladenova, S.; Hadjiev, V.

    2004-01-01

    Subject of study are the inter-relations between the primary leak parameters, the containment pressure and the functioning of the WWER-1000/V320 plant systems. The model includes systems for normal operation and safety systems, which are actuated in the initial stage of the accident. The studied specter of primary leaks includes diameters from 10 to 60 mm. The model is based on the design features of unit 5 in NPP Kozloduy. This paper presents a fragment of the work, performed jointly by Atoma Consult Ltd and NPP Kozloduy Plc on the validation of the symptom oriented emergency operation procedures for units 5 and 6 in NPP Kozloduy. (authors)

  20. Analyses of steam generator collector rupture for WWER-1000 using Relap5 code

    Energy Technology Data Exchange (ETDEWEB)

    Balabanov, E.; Ivanova, A. [Energoproekt, Sofia (Bulgaria)

    1995-12-31

    The paper presents some of the results of analyses of an accident with a LOCA from the primary to the secondary side of a WWER-1000/320 unit. The objective of the analyses is to estimate the primary coolant to the atmosphere, to point out the necessity of a well defined operator strategy for this type of accident as well as to evaluate the possibility to diagnose the accident and to minimize the radiological impact on the environment.

  1. Analyses of steam generator collector rupture for WWER-1000 using Relap5 code

    Energy Technology Data Exchange (ETDEWEB)

    Balabanov, E; Ivanova, A [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    The paper presents some of the results of analyses of an accident with a LOCA from the primary to the secondary side of a WWER-1000/320 unit. The objective of the analyses is to estimate the primary coolant to the atmosphere, to point out the necessity of a well defined operator strategy for this type of accident as well as to evaluate the possibility to diagnose the accident and to minimize the radiological impact on the environment.

  2. Analyses of steam generator collector rupture for WWER-1000 using Relap5 code

    International Nuclear Information System (INIS)

    Balabanov, E.; Ivanova, A.

    1995-01-01

    The paper presents some of the results of analyses of an accident with a LOCA from the primary to the secondary side of a WWER-1000/320 unit. The objective of the analyses is to estimate the primary coolant to the atmosphere, to point out the necessity of a well defined operator strategy for this type of accident as well as to evaluate the possibility to diagnose the accident and to minimize the radiological impact on the environment

  3. Application of the LBB concept to nuclear power plants with WWER 440 and WWER 1000 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zdarek, J.; Pecinka, L. [Nuclear Research Institute Rez (Czech Republic)

    1997-04-01

    Leak-before-break (LBB) analysis of WWER type reactors in the Czech and Sloval Republics is summarized in this paper. Legislative bases, required procedures, and validation and verification of procedures are discussed. A list of significant issues identified during the application of LBB analysis is presented. The results of statistical evaluation of crack length characteristics are presented and compared for the WWER 440 Type 230 and 213 reactors and for the WWER 1000 Type 302, 320 and 338 reactors.

  4. Application of the LBB concept to nuclear power plants with WWER 440 and WWER 1000 reactors

    International Nuclear Information System (INIS)

    Zdarek, J.; Pecinka, L.

    1997-01-01

    Leak-before-break (LBB) analysis of WWER type reactors in the Czech and Sloval Republics is summarized in this paper. Legislative bases, required procedures, and validation and verification of procedures are discussed. A list of significant issues identified during the application of LBB analysis is presented. The results of statistical evaluation of crack length characteristics are presented and compared for the WWER 440 Type 230 and 213 reactors and for the WWER 1000 Type 302, 320 and 338 reactors

  5. Best estimate modeling of fuel thermomechanical behaviour in WWER 1000 LB LOCA

    International Nuclear Information System (INIS)

    Valach, M.; Klouzal, J.; Zymak, J.; Dostal, M.

    2009-01-01

    The paper summarizes our calculations of the performance of the WWER 1000 NPP fuel rods during postulated LB LOCA. The thermomechanical modeling was performed by FRAPTRAN using the FRACAS-I mechanical model using the boundary conditions calculated by the ATHLET code. The results and their statistical evaluation are presented, the process of the generalization of gained insight into the best-estimate thermal-hydraulic analyses (BE TM) predictions in order to define a generic BE TM methodology is outlined (authors)

  6. Experimental study of the passive flooding system in the WWER-1000 reactor

    International Nuclear Information System (INIS)

    Malyshev, A.B.; Efanov, A.D.; Kalyakin, S.G.

    2002-01-01

    The design solution of the passive flooding system in the WWER-1000 reactor core with the V-392 reactor facility and the scheme of the GE-2 large-scale thermohydraulic stand for substantiation of its functions are presented. The proposals, improving the efficiency of the system are developed on the basis of the experimental studies on the equipment input-output operational characteristics and the recommendations on the substantiation of the function of the reactor core flooding system are given [ru

  7. Status and prospects of activities on algorithms and methods in WWER-1000 core control

    International Nuclear Information System (INIS)

    Filimonov, P.; Krainov, Y.; Proselkov, V.

    1994-01-01

    On the basis of long-term operational experience and investigations the problems of WWER-1000 reactor control are discussed. Such control is needed for WWER-1000, as well as for its Western analog PWR, for suppressing the axially instable power density field resulted from non-equilibrium redistribution of Xe-135 nuclei in the reactor core. It has been found that an adequate assessment of the reactor state and the prediction of its response to various control actions is essential for the control of power density distribution. For this purpose a computerized operator's adviser with a reactor simulator realizing a physical reactor model based on BIPR-7 code is used. The operation experience of WWER-1000 shows that the available control algorithms allow, with a fair degree of assurance, the prevention of intensive xenon oscillations and the stabilization of the axial offset. But in connection with the renunciation of half-length control rods a new algorithm is under development which makes use of full-length control rods for suppressing the intensive xenon oscillations in the descending phase. A new method based on BIPR-7 and PERMAK codes is also being developed for estimating the value and rate of linear power rating change of the fuel elements in power cycling. 12 figs., 7 refs

  8. Status and prospects of activities on algorithms and methods in WWER-1000 core control

    Energy Technology Data Exchange (ETDEWEB)

    Filimonov, P; Krainov, Y; Proselkov, V [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    1994-12-31

    On the basis of long-term operational experience and investigations the problems of WWER-1000 reactor control are discussed. Such control is needed for WWER-1000, as well as for its Western analog PWR, for suppressing the axially instable power density field resulted from non-equilibrium redistribution of Xe-135 nuclei in the reactor core. It has been found that an adequate assessment of the reactor state and the prediction of its response to various control actions is essential for the control of power density distribution. For this purpose a computerized operator`s adviser with a reactor simulator realizing a physical reactor model based on BIPR-7 code is used. The operation experience of WWER-1000 shows that the available control algorithms allow, with a fair degree of assurance, the prevention of intensive xenon oscillations and the stabilization of the axial offset. But in connection with the renunciation of half-length control rods a new algorithm is under development which makes use of full-length control rods for suppressing the intensive xenon oscillations in the descending phase. A new method based on BIPR-7 and PERMAK codes is also being developed for estimating the value and rate of linear power rating change of the fuel elements in power cycling. 12 figs., 7 refs.

  9. A procedure for temperature-stress fields calculation of WWER-1000 primary circuit in PTS event

    Energy Technology Data Exchange (ETDEWEB)

    Petkov, G [Technical Univ., Dept. Thermal and Nuclear Power Engineering, Sofia (Bulgaria); Groudev, P; Argirov, J [Bulgarian Academy of Science, Inst. for Nuclear Research and Nuclear Energy, Sofia (Bulgaria)

    1997-09-01

    The paper presents the procedure of an investigation of WWER-1000 primary circuit temperature-stress field by the use of thermohydraulic computation data for a pressurized thermal shock event ``Core overcooling``. The procedure is based on a model of the plane stress state with ideal contact between wall and medium for the calculation. The computation data are calculated on the base of WWER-1000 thermohydraulic model by the RELAP5/MOD3 codes. This model was developed jointly by the Bulgarian and BNL/USA staff to provide an analytical tool for performing safety analysis. As a result of calculations by codes the computation data for temperature field law (linear laws of a few distinguished parts) and pressure of coolant at points on inner surface of WWER-1000 primary circuit equipment are received. Such calculations can be used as a base for determination of all-important load-carrying sections of the primary circuit pipes and vessels, which need further consideration. (author). 7 refs, 2 figs, 2 tabs.

  10. Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Lin, C.; Strupczewski, A. [International Atomic Energy Agency, Vienna (Austria)

    1995-12-31

    At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

  11. Steam generator collector integrity of WWER-1000 reactors. IAEA extrabudgetary programme on the safety of WWER NPPs

    Energy Technology Data Exchange (ETDEWEB)

    Lin, C; Strupczewski, A [International Atomic Energy Agency, Vienna (Austria)

    1996-12-31

    At the Consultants` Meeting on `The Safety of WWER-1000 Model 320 Nuclear Power Plants` organized by the IAEA within the framework of its Extrabudgetary Programme on the Safety of WWER-1000 NPPs, which was held in Vienna, 1-5 June 1992, the problem of WWER-1000 steam generator integrity was identified as an important issue of safety concern. Considering the safety importance of this issue, a Consultants` Meeting on `The Steam Generator Integrity of WWER-1000 Nuclear Power Plants` was convened in Vienna in May 1993, attended by 15 international experts in the area to compile information on the steam generator operating experience, deficiencies and corrective measures implemented and planned. In order to also include information from the main designer OKB Gidropress and to finalize the meeting report the IAEA convened a second meeting on the issue on 23-27 November 1993. The present paper summarizes the information and conclusions from those meetings.

  12. Experience of CR and RCCA operation in Ukrainian WWER-1000: Aspects of reliability, safety and economic efficiency

    International Nuclear Information System (INIS)

    Afanasyev, A.

    2000-01-01

    The next topics are represented in the paper: A brief history of WWER-1000 control rod (CR) and WWER-1000 rod cluster control assembly (RCCA) design; Evolution of WWER-1000 CR manufacturing technology and design; Experience of RCCA operation; Lifetime extension of WWER-1000 boron carbide CR; WWER-1000 reactor core operation problems due to partial RCCA insertion; Designing and licensing procedures and first operational experience of WWER-1000 RCCA (CR) with a combined absorber 'boron carbide-hafnium' and a chromium-nickel alloy cladding. The main conclusions are: Fuel assembly (FA) bow is the main reason of partial RCCA insertion during reactor core operation. However, the use of the RCCA and its driver bar with increased dead load, alongside with other measures, allow to reduce the probability of incomplete RCCA insertion; The materials used in CRs of RCCA in existing reactor operating modes have been working reliably; The use of hafnium under an appropriate price policy can give certain economic advantages for the Ukrainian NPPs, however, additional research is needed in order to confirm the specific CR physical characteristics and reliability. (author)

  13. Structural capacity assessment of WWER-1000 MW reactor containment. Progress report

    International Nuclear Information System (INIS)

    Jordanov, M.

    1999-01-01

    The objective of the project is to provide assessment of the structural behaviour and safety capacity of the WWER-1000 MW Reactor Building Containment at Kozloduy NPP under critical combination of loads according to the current international requirements. The analysis is focused on a realistic assessment of the Containment taking into account the non-linear shell behaviour of the pre-stressed reinforced concrete structure. Previous assessments of the status of pre stressing cables pointed out that the efficiency of the Containment as a final defence barrier for internal and external events depends on their reliability. Due to this, the experimental data obtained from embedded sensors (gauges) at pre-stressed shell structure is to be compared with the results from analytical investigations. The reliability of the WWER-1000 MW accident prevention system is under evaluation in the project. The Soviet standard design WWER-1000 MW type units installed in Kozloduy NPP were originally designed for a Safe Shutdown Earthquake (SSE) with a peak ground acceleration (PGA) of 0.1g. The new site seismicity studies revealed that the seismic hazard for the site significantly exceeds the originally estimated and a Review Level Earthquake (RLE) anchored to PGA=0.20g was proposed for re-assessment of the structures and equipment at Kozloduy NPP. The scope of the study is a re-assessment of the Containment structure under critical combination of loads according to the current safety and reliability requirements, including comparison between the Russian design requirements and the international regulations. Additionally, an investigation of the pre-stressing technology and the annual control of the cables' pre-stressing of the Containment is to be made. The crane influence on the dynamic behaviour of the Containment will be done as well as a study of the integrity of the Containment as a final defence barrier

  14. Experience running in and improvement of secondary circuit water chemistry of Kalinin NPP WWER-1000

    International Nuclear Information System (INIS)

    Noev, V.V.; Kukharev, N.D.; Otchenashev, G.D.; Guzeeva, G.I.; Kochetova, G.G.

    1991-01-01

    Basic characteristics of the secondary circuit water-chemical conditions at the Kalinin 1 and 2 reactors are presented. These are the WWER-1000 reactors with K-1000-1500 turbines. The analysis conducted makes it possible to conclude that all indicated values can meet the standards by introducing the hydrazine-ammonium regime in the secondary circuit with feedwater pH value equal to 9±0.2. Realization of design scheme for condensate-feeding circuit washing is necessary for acceleration of the water-chemical mode stabilization. Moreover the units should be equipped with automated chemical control instrumentation of a new generation

  15. Approach to normalization of the secondary circuit water chemistry of NPP with WWER-1000

    International Nuclear Information System (INIS)

    Mamet, V.A.; Erpyleva, S.F.; Banyuk, G.F.

    1998-01-01

    The approach to normalization if indices of water-chemical regime of the secondary circuit of the NPP with WWER-1000 reactor, based on pH calculational values at the coolant working temperature in dependence on the normalized admixtures concentration is considered. The possibility for conducting the water regime of steam generators by the ratio of sodium concentration and electrical conductivity of H-cation sample of blow-through water is shown. The limitations (os action level) by deviation of normalized indices from recommended ones for normal operational conditions are described

  16. Results of developing and problems of further improvements for WWER-1000 FA of alternative design

    International Nuclear Information System (INIS)

    Molchanov, V.L.; Panyushkin, A.K.; Zheleznyak, V.M.; Samojlov, O.B.; Kuul', V.S.; Kurylev, V.I.

    2001-01-01

    A new fuel assembly of alternative design (FAA) is created for a WWER-1000 reactor which is characteristic of dimensional stability on operation. The FAA includes a frame of 15 alloy Eh-110 spacer grids spot welded to 6 alloy Eh-635 angle sections. In-core tests show that the FAA is stable to form changing. It is concluded that the FAA can serve as a basis for development of promising fuel cycle with high burnups, specifically, for a 4 year cycle with the use of uranium-gadolinium fuel [ru

  17. Measuring neutron flux density in near-vessel space of a commercial WWER-1000 reactor

    International Nuclear Information System (INIS)

    Borodkin, G.I.; Eremin, A.N.; Lomakin, S.S.; Morozov, A.G.

    1987-01-01

    Distribution of neutron flux density in two experimental channels on the reactor vessel external surface and in ionization chamber channel of a commercial WWER-1000 reactor, is measured by the activation detector technique. Azimuthal distributions of fast and thermal neutron fluxes and height distributions of fast neutron flux density within energy range >1.2 and 2.3 MeV are obtained. Conclusion is made, that reactor core state and its structural peculiarities in the measurement range essentially affect space and energy distribution of neutron field near the vessel. It should be taken into account when determining permissible neutron fluence for the reactor vessel

  18. Recommended reactor coolant water chemistry requirements for WWER-1000 units with 235U higher enriched fuel

    International Nuclear Information System (INIS)

    Dobrevski, I.; Zaharieva, N.

    2011-01-01

    The last decade worldwide experience of PWRs and WWERs confirms the trends for the improvement of the nuclear power industry electricity production through the implementation of high burn-up or high fuel duty, which are usually accompanied with the usage of UO 2 fuel with higher content of 235 U - 4.0% - 4.5% (5.0%). It was concluded that the onset of sub-cooled nucleate boiling (SNB) on the fuel cladding surfaces and the initial excess reactivity of the core are the primary and basic factors accompanying the implementation of uranium fuel with higher 235 U content, aiming extended fuel cycles and higher burn-up of the fuel in Pressurized Water Reactors. As main consequences of the presence of these factors the modifications of chemical / electrochemical environments of nuclear fuel cladding- and reactor coolant system- surfaces are evaluated. These conclusions are the reason for: 1) The determination of the choices of the type of fuel cladding materials in respect with their enough corrosion resistance to the specific fuel cladding environment, created by the presence of SNB; 2) The development and implementation of primary circuit water chemistry guidelines ensuring the necessary low corrosion rates of primary circuit materials and limitation of cladding deposition and out-of-core radioactivity buildup; 3) Implementation of additional neutron absorbers which allow enough decrease of the initial concentration of H 3 BO 3 in coolant, so that its neutralization will be possible with the permitted alkalising agent concentrations. In this paper the specific features of WWER-1000 units in Bulgarian Nuclear Power Plant; use of 235 U higher enriched fuel in the WWER-1000 reactors in the Kozloduy NPP; coolant water chemistry and radiochemistry plant data during the power operation period of the Kozloduy NPP Unit 5, 15 th fuel cycle; evaluation of the approaches and results by the conversion of the WWER-1000 Units at the Kozloduy NPP to the uranium fuel with 4.3% 235 U as

  19. Characteristics of WWER-1000 fuel rod claddings and FA components from E635 alloy at burnups up to 72 MWd/kgU

    International Nuclear Information System (INIS)

    Nikulin, A.; Novikov, A.; Peregud, M.; Shishov, V.; Shevyakov, A.; Volkova, I.; Novoselov, A.; Kobylyansky, G.

    2011-01-01

    In this paper operation experience, results of investigated E365 alloy components of Balakovo NPP Unit 1 and Kalinin NPP unit 1 fuel assemblies are presented. Appearance, shape changes and geometric size, corrosion state of guide thimbles, angles and fuel rods, corrosion of fuel claddings are studied. At the end authors concluded that: I) E635 alloy corroborated its high operation reliability as fuel claddings and WWER-1000 FA components during 6 year service to the fuel burnup of 72MWd/kgU; II) Based on the results from the post-irradiation investigations of the fuel rods and other structural elements of WWER-1000 FAA, fabricated from E635 alloy, in terms of the basic operational characteristics, their resources after the 6 year operation cycle have not been exhausted; III) The geometrical parameters, corrosion states, tensile properties of items fabricated from fuel alloy did not attain the values that would prevent their further operation: 1) the elongations of the fuel rods at the mean burnups up to 66.2 MWd/kgU do not exceed 15 mm or 4.9%; 8) the amount of the oxide coat at surface of GT and CT does not exceed 45 μm, the hydrogen content is <0.03% mass; 9) the oxide coat at the surfaces of the frame angles does not exceed 50 μm, the hydrogen content is <0.04% mass

  20. Evaluation of the PTS potential in a WWER-1000 following a steam line break

    International Nuclear Information System (INIS)

    Beghini, M.; D'Auria, F.; Galassi, G.M.; Vitale, E.

    1997-01-01

    A qualified nodalization for WWER-1000 is available at DCMN (Dipartimento di Costruzioni Meccaniche e Nucleari) of University of Pisa that is suitable for running with the thermohydraulic system code Relap5/mod3.2. The nodalization consists of about 1400 hydraulic nodes and more than 5000 mesh points for conduction heat transfer. The four loops of the NPP are separately modelled. Detailed information about the plant hardware has been gotten from contacts with Eastern Organizations in Bulgaria, Russia and Ukraine. The qualification of the nodalization has been achieved at a steady state level utilizing a procedure available at DCMN and at a transient level on the basis of operational (planned) transients performed in the Bulgarian Kozloduy-5 NPP and of the unplanned transient occurred at the Ukrainian Zaporosche NPP (April 1995). Data measured in steam generators have also been utilized. The nodalization has been widely applied to the analysis of accident scenarios in WWER-1000, including Large Break LOCA, Small Break LOCA, ATWS, Loss of Feedwater and Station Blackout. The present activity aims at evaluating the potential for PTS (Pressurized Thermal Shock) following a steam line break accident. The thermalhydraulic results were employed as input for a parametric Fracture Mechanics analysis based on conservative hypothesis of the shape and localization of a pre-existing defect. Stress analysis evidenced the effect of partial cooling of the vessel and gave some general indications of the risk for unstable crack propagation under the simulated PTS conditions. (author). 30 refs, 17 figs, 4 tabs

  1. Electromagnetism Mechanism for Enhancing the Refueling Cycle Length of a WWER-1000

    Directory of Open Access Journals (Sweden)

    Navid Poursalehi

    2017-02-01

    Full Text Available Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM, is applied to the fuel arrangement design of the Bushehr WWER-1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation. The first results of the prepared package, along with the cycle for the original pattern of Bushehr WWER-1000, are compared and verified according to the Final Safety Analysis Report and then the results of exploited EM linked with Purdue Advanced Reactor Core Simulator (PARCS and Winfrith Improved Multigroup Scheme (WIMS codes are reported for the loading pattern optimization. Totally, the numerical results of our loading pattern optimization indicate the power of the EM for this problem and also show the effective improvement of desired parameters for the gained semi-optimized core pattern in comparison to the designer scheme.

  2. Electromagnetism mechanism for enhancing the refueling cycle length of a WWER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Poursalehi, Navid; Nejati-Zadeh, Mostafa; Minuchehr, Abdolhamid [Dept. of Nuclear Engineering, Shahid Beheshti University, Tehran (Iran, Islamic Republic of)

    2017-02-15

    Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM), is applied to the fuel arrangement design of the Bushehr WWER-1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation. The first results of the prepared package, along with the cycle for the original pattern of Bushehr WWER-1000, are compared and verified according to the Final Safety Analysis Report and then the results of exploited EM linked with Purdue Advanced Reactor Core Simulator (PARCS) and Winfrith Improved Multigroup Scheme (WIMS) codes are reported for the loading pattern optimization. Totally, the numerical results of our loading pattern optimization indicate the power of the EM for this problem and also show the effective improvement of desired parameters for the gained semi-optimized core pattern in comparison to the designer scheme.

  3. Analysis of an accident with the main circulation tube rupture at the WWER-1000

    International Nuclear Information System (INIS)

    Boyadzhiev, A.I.; Stefanova, S.J.

    1984-01-01

    In connection with the forthcoming construction of a npp with the wwer-1000 reactor the loss of coolant accident associated with the main circulation tube rupture at the inlet near the reactor is analyzed. The relap4/mod6 program is used for the analysis. The data obtained show that the coolant outflow stage continues for about 25s. On the average the pressure in the circuits varies from 16 to 10 mpa per 0.1s and then it continues to decrease slowly. The pressure in the steam generator at the secondary circuits end increases approximately up to 6.9 MPa as a result of steam generator blocking and remaining coolant heating and then somewhat decreases owing to the primary circuit cooling. By the end of the fuel and can temperatures are equalized and the heat transfer coefficient is stabilized at the level of 100 w/1 (m 2 xK). It is concluded that during a loss of coolant accident at the wwer-1000 reactor in procesess of coolant blowdown in the medium power fuel elemets neither the fuel, melting temperature (3000 k), nor the critical temperature (1000 k) of plastic deformation zirconiu can initiation are attained

  4. Main examination results of WWER-1000 fuel after its irradiation in power reactors

    International Nuclear Information System (INIS)

    Bibiliashvili, Yu.; Dubrovin, K.; Vasilchenko, I.; Yenin, A.; Kushmanov, A.; Smirnov, A.; Smirnov, V.

    1994-01-01

    WWER-1000 fuel examination has been undertaken to specify the properties of fuel assembly members by defining the parameters of their materials and their interconnection in power reactor operation conditions. Nine fuel assemblies are examined. The examination program includes: visual inspection, measurement of overall dimensions, eddy-current test, gamma-scanning, X-ray and neutron radiography, analysis of gas pressure and composition inside fuel rods, ceramography/metallography, mass spectrometry, microanalysis and electron microscopy of fuel and fuel claddings. The examination results suggest that WWER-1000 fuel spent at steady-state operation conditions up to 50 Mwd/kg U of burnup is in satisfactory condition. The examination of all types of fuel cladding failures indicates that the reason lies in the interaction of cladding with coolant solid impurities. The nodular cladding corrosion of fuel assembly discharged from the South-Ukrainian NPP is caused by the graphite compounds deposited on the fuel rod. Those deposits are a result of the circulating pump damage and had accidental, non-typical character. Some of the rods were found to have a small cladding 'fretting' of the spacer grid cell material. The values of the majority of parameters determining the fuel efficiency allow to assume that there is a potential for further extension of fuel burnup and operation length. 1 tab., 11 figs

  5. Main examination results of WWER-1000 fuel after its irradiation in power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bibiliashvili, Yu [Vsesoyuznyj Nauchno-Issledovatel` skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation); Dubrovin, K [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation); Vasilchenko, I [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation); Yenin, A; Kushmanov, A [AO Novosibirskij Zavod Khimcontsentratov, Novosibirsk (Russian Federation); Smirnov, A; Smirnov, V [Nauchno-Issledovatel` skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation)

    1994-12-31

    WWER-1000 fuel examination has been undertaken to specify the properties of fuel assembly members by defining the parameters of their materials and their interconnection in power reactor operation conditions. Nine fuel assemblies are examined. The examination program includes: visual inspection, measurement of overall dimensions, eddy-current test, gamma-scanning, X-ray and neutron radiography, analysis of gas pressure and composition inside fuel rods, ceramography/metallography, mass spectrometry, microanalysis and electron microscopy of fuel and fuel claddings. The examination results suggest that WWER-1000 fuel spent at steady-state operation conditions up to 50 Mwd/kg U of burnup is in satisfactory condition. The examination of all types of fuel cladding failures indicates that the reason lies in the interaction of cladding with coolant solid impurities. The nodular cladding corrosion of fuel assembly discharged from the South-Ukrainian NPP is caused by the graphite compounds deposited on the fuel rod. Those deposits are a result of the circulating pump damage and had accidental, non-typical character. Some of the rods were found to have a small cladding `fretting` of the spacer grid cell material. The values of the majority of parameters determining the fuel efficiency allow to assume that there is a potential for further extension of fuel burnup and operation length. 1 tab., 11 figs.

  6. Evaluation of the PTS potential in a WWER-1000 following a steam line break

    Energy Technology Data Exchange (ETDEWEB)

    Beghini, M; D` Auria, F; Galassi, G M; Vitale, E [Universita degli Studi di Pisa, Dipt. di Costruzioni Meccaniche e Nucleari, Pisa (Italy)

    1997-09-01

    A qualified nodalization for WWER-1000 is available at DCMN (Dipartimento di Costruzioni Meccaniche e Nucleari) of University of Pisa that is suitable for running with the thermohydraulic system code Relap5/mod3.2. The nodalization consists of about 1400 hydraulic nodes and more than 5000 mesh points for conduction heat transfer. The four loops of the NPP are separately modelled. Detailed information about the plant hardware has been gotten from contacts with Eastern Organizations in Bulgaria, Russia and Ukraine. The qualification of the nodalization has been achieved at a steady state level utilizing a procedure available at DCMN and at a transient level on the basis of operational (planned) transients performed in the Bulgarian Kozloduy-5 NPP and of the unplanned transient occurred at the Ukrainian Zaporosche NPP (April 1995). Data measured in steam generators have also been utilized. The nodalization has been widely applied to the analysis of accident scenarios in WWER-1000, including Large Break LOCA, Small Break LOCA, ATWS, Loss of Feedwater and Station Blackout. The present activity aims at evaluating the potential for PTS (Pressurized Thermal Shock) following a steam line break accident. The thermalhydraulic results were employed as input for a parametric Fracture Mechanics analysis based on conservative hypothesis of the shape and localization of a pre-existing defect. Stress analysis evidenced the effect of partial cooling of the vessel and gave some general indications of the risk for unstable crack propagation under the simulated PTS conditions. (author). 30 refs, 17 figs, 4 tabs.

  7. On steady-state concentrations of ammonia and molecular hydrogen in the primary circuit of the WWER-1000 reactors

    International Nuclear Information System (INIS)

    Arkhipov, O.P.; Bugaenko, V.L.; Kamakchi, S.A.

    1997-01-01

    It is shown that the MORAVA-N2 software package describes well the coolant state in the primary circuit of an actual reactor facility with the WWER-1000 during on-load operation. It permits using the package for analysis of process perturbation effect on the coolant composition. Specific feature of ammonia radiation chemistry in the primary circuit of a reactor facility with the WWER-1000, assuring the rates hydrogen concentration in the coolant with ammonia concentration variation in the coolant within wide limits, when reactor operates on power, can be mentioned by way of example, the fact being ascertained in this study

  8. Fuel element cladding state change mathematical model for a WWER-1000 plant operated in the mode of varying loading

    Directory of Open Access Journals (Sweden)

    S. N. Pelykh

    2010-09-01

    Full Text Available Main features of a fuel element cladding state change mathematical model for a WWER-1000 reactor plant operated in the mode of varying loading are listed. The integrated model is based on the energy creep theory, uses the finite element method for imultaneous solution of the fuel element heat conduction and mechanical deformation equa-tions. Proposed mathematical model allows us to determine the influence of the WWER-1000 regime parameters and fuel assembly design characteristics on the change of cladding properties under different loading conditions of normal operation, as well as the cladding limiting state at variable loading depending on the length, depth and number of cycles.

  9. Determination and elimination of the reasons for increased control rod insertion time of the Kozloduy NPP WWER-1000

    International Nuclear Information System (INIS)

    Nikolov, K.

    1996-01-01

    The emergency insertion speed of the control rod upon reactor shutdown is of crucial importance for reactor safety. The designed insertion time for WWER-1000 reactors should be in the limits 1,5 to 4 s. Having in mind some data about increased insertion times of WWER-1000 type reactors in Russia and Ukraine, a practice of measuring this parameters during each planned outage of the Kozloduy NPP Unit 6 is introduced. Some technical improvements of the fuel assembly are made in order to reach the nominal parameters of the unit

  10. Determination of in-service change in the geometry of WWER-1000 core baffle: Calculations and measurements

    International Nuclear Information System (INIS)

    Margolin, B.Z.; Varovin, A.Y.; Minkin, A.J.; Sorokin, A.A.; Piminov, V.A.; Evdokimenko, V.V.; Fedosovsky, M.E.; Sherstobitov, A.E.; Ovchinnikov, A.G.; Pikulik, S.S.; Erak, D.Y.; Bobkov, A.V.; Timofeev, A.M.; Timokhin, V.I.; Yakushev, S.V.; Vasiliev, V.G.

    2015-01-01

    The paper gives the basic constitutive equations describing radiation swelling and creep depending on neutron dose, irradiation temperature and triaxial stress state, and justifies these equations experimentally. The WWER-1000 core baffle change in geometry was calculated by different models describing the effect of stresses on radiation swelling. The calculated results are compared with the measured ones for the operating WWER-1000 core baffle at the Balakovo NPP, Unit 1. A method of individual prediction of core baffle geometry change on the basis of the measurement results has been proposed. (authors)

  11. Examples for cost reduction in the design of a WWER-1000 nuclear power plant

    International Nuclear Information System (INIS)

    Kukkola, T.

    1991-01-01

    In a design project during recent years, a version for Finnish conditions has been and is being developed based on the Soviet WWER-1000 PWR plant with four horizontal steam generators. The plant will have a double containment. The inner containment will be a dry full pressure prestressed concrete containment with liner and the secondary containment will be made of ordinary concrete. Four train safety approach is adopted. It is supposed that the plant is to be designed according to the present Finnish safety requirements, e.g. severe reactor accidents are considered. When striving at an economic plant no compromises are made as far as safety is concerned. This paper describes possible cost reduction by redesigning the main technical equipment. (author). 1 ref

  12. Calculated and experimental research of WWER-1000 assembly vibration and fretting damage

    International Nuclear Information System (INIS)

    Drozdov, Y.; Afanasyev, A.; Makarov, V.; Tutnov, A.; Tutnov, A.; Alekseev, E.

    2008-01-01

    The report covers the methods and results of the latest analytical and experimental studies of fretting corrosion and natural vibrations of a WWER-1000 reactor fuel assemblies (FA). The process of fretting-corrosion was investigated using a multi-specimen facility that simulated fragments of fuel rod-to-spacer grid and lower support grid mating units. A computational model was developed for vibrations in the mechanical system of a fuel rod fragment and a spacer grid fragment. A calculational and experimental modal analysis of a FA was performed. Natural frequencies, modes and decrements of FA vibrations were determined and a satisfactory coincidence of analytical and experimental results was obtained. The assessment of fretting-corrosion process dynamics was made and its dependences on operational factors were obtained. (authors)

  13. Neutron flux uncertainty and covariances for spectrum adjustment and estimation of WWER-1000 pressure vessel fluences

    International Nuclear Information System (INIS)

    Boehmer, Bertram

    2000-01-01

    Results of estimation of the covariance matrix of the neutron spectrum in the WWER-1000 reactor cavity and pressure vessel positions are presented. Two-dimensional calculations with the discrete ordinates transport code DORT in r-theta and r-z-geometry used to determine the neutron group spectrum covariances including gross-correlations between interesting positions. The new Russian ABBN-93 data set and CONSYST code used to supply all transport calculations with group neutron data. All possible sources of uncertainties namely caused by the neutron gross sections, fission sources, geometrical dimensions and material densities considered, whereas the uncertainty of the calculation method was considered negligible in view of the available precision of Monte Carlo simulation used for more precise evaluation of the neutron fluence. (Authors)

  14. Experimental verification of FA for WWER-1000. Investigations of TVS - 2M

    International Nuclear Information System (INIS)

    Vasilchenko, I.; Seleznev, A.; Kobelev, S.; Makarov, V.; Afanasjev, A.; Matvienko, I.; Enin, A.; Ustimenko, A.; Volkov, S.

    2008-01-01

    During development of TVS-2M design for WWER-1000 and within the scope of its pre-reactor verification there was performed a complex of bench tests of FA for operational impacts. These tests were carried out with the use of the full-scale non-irradiated FA dummy and the models of units. The present report presents the methods and the results of tests of the full-scale dummy for static concentrated loads, impact of thermal cycling and vibration under separate and simultaneous impact of the listed loads. The results of tests carried out indicate that the solutions implemented in TVS-2M, first of all, a rigid welded skeleton, provide much higher resistance to distortion due to thermomechanical loads in comparison with zirconium AFA of the previous generation. This work was organized by JSC TVEL. (authors)

  15. Data base and postirradiation examination results of spent WWER-1000 fuel elements and assemblies

    International Nuclear Information System (INIS)

    Kanashov, B.A.; Polenok, V.S.; Smirnov, A.V.; Zhitelev, V.A.

    1995-01-01

    The report presents the results of the postirradiation shape change examination of standard fuel elements and fuel assemblies irradiated in standard conditions in Russian power reactors of the WWER-1000 type. The information is based on the results obtained at the Fuel Research Department of the Federal Scientific Centre Research Institute of Atomic Reactors (FSC RIAR, Dimitrovgrad, Russian Federation) within the period from 1987 to 1994. Emphasis is placed on such experimental and calculational data as: length, cross-section dimensions and shape of FAs with wrapper; change of standard FA skeleton members dimensions; fuel bundle elongation; change of the fuel cladding outer diameter; and elongation and change of the fuel stack outer diameter. (author)

  16. Status and trends in nuclear technology for power plants with WWER-1000 reactors. Review

    Energy Technology Data Exchange (ETDEWEB)

    Zorev, N N

    1977-04-01

    The problems of improving quality of nuclear equipment for WWER-1000 power plants and associated nuclear technology automation are surveyed. Examples of technological innovations are presented which significantly reduce labour intensity, time consumption and increase quality standards of the products. Some new automated equipments for materials welding, working, machining and quality control are described. The discussion is centering around heavy-section steel technologies. Some mechanical properties of new-developed nuclear grade steels designed for producing reactor vessels and steamgenerators, volume compensators and pipes, as well as steam separators and steamsuperheaters are also presented. Their properties (impact strength and radiation resistance) are pointed out to be superior to that of steels used abroad. The basic trend in nuclear structural material developments is towards integrated optimization of strength, performance and workability.

  17. Modelling of WWER-1000 steam generators by REALP5/MOD3.2 code

    Energy Technology Data Exchange (ETDEWEB)

    D`Auria, F.; Galassi, G.M. [Univ. of Pisa (Italy); Frogheri, M. [Univ. of Genova (Italy)

    1997-12-31

    The presentation summarises the results of best estimate calculations carried out with reference to the WWER-1000 Nuclear Power Plant, utilizing a qualified nodalization set-up for the Relap5/Mod3.2 code. The nodalization development has been based on the data of the Kozloduy Bulgarian Plant. The geometry of the steam generator imposed drastic changes in noding philosophy with respect to what is suitable for the U-tubes steam generators. For the secondary side a symmetry axis was chosen to separate (in the nodalization) the hot and the cold sides of the tubes. In this way the secondary side of the steam generators was divided into three zones: (a) the hot zone including the hot collector and the hot l/2 parts of the tubes; (b) the cold zone including the cold collector and the cold 1/2 parts of the tubes; (c) the downcomer region, where down flow is assumed. As a consequence of above in the primary side more nodes are placed on the hot side of the tubes. Steady state and transient qualification has been achieved, considering the criteria proposed at the University of Pisa, utilizing plant transient data from the Kozloduy and the Ukrainian Zaporosche Plants. The results of the application of the qualified WWER-1000 Relap5/Mod3.2 nodalization to various transients including large break LOCA, small break LOCA and steam generator tube rupture, together with a sensitivity analysis on the steam generators, are reported in the presentation. Emphasis is given to the prediction of the steam generators performances. 23 refs.

  18. Modelling of WWER-1000 steam generators by REALP5/MOD3.2 code

    Energy Technology Data Exchange (ETDEWEB)

    D` Auria, F; Galassi, G M [Univ. of Pisa (Italy); Frogheri, M [Univ. of Genova (Italy)

    1998-12-31

    The presentation summarises the results of best estimate calculations carried out with reference to the WWER-1000 Nuclear Power Plant, utilizing a qualified nodalization set-up for the Relap5/Mod3.2 code. The nodalization development has been based on the data of the Kozloduy Bulgarian Plant. The geometry of the steam generator imposed drastic changes in noding philosophy with respect to what is suitable for the U-tubes steam generators. For the secondary side a symmetry axis was chosen to separate (in the nodalization) the hot and the cold sides of the tubes. In this way the secondary side of the steam generators was divided into three zones: (a) the hot zone including the hot collector and the hot l/2 parts of the tubes; (b) the cold zone including the cold collector and the cold 1/2 parts of the tubes; (c) the downcomer region, where down flow is assumed. As a consequence of above in the primary side more nodes are placed on the hot side of the tubes. Steady state and transient qualification has been achieved, considering the criteria proposed at the University of Pisa, utilizing plant transient data from the Kozloduy and the Ukrainian Zaporosche Plants. The results of the application of the qualified WWER-1000 Relap5/Mod3.2 nodalization to various transients including large break LOCA, small break LOCA and steam generator tube rupture, together with a sensitivity analysis on the steam generators, are reported in the presentation. Emphasis is given to the prediction of the steam generators performances. 23 refs.

  19. Analysis of expediency to set regulators of high-pressure emergency core cooling system of WWER 1000 (B-320)

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Komarov, Yu.A.; Tikhonova, G.G.; Nikiforov, S.N.; Bogodist, V.V.; Fol'tov, I.M.; Khadzh Faradzhallakh Dabbakh, A.

    2011-01-01

    The work shows that setting regulative valves in high-pressure emergency core cooling system of WWER 1000/B-320 can be effective only involving the additional tuning to account traverse speed of operating elements of regulator and configuration of the systems providing cooling of primary loop.

  20. Structural optimization of static power control programs of nuclear power plants with WWER-1000

    International Nuclear Information System (INIS)

    Kokol, E.O.

    2015-01-01

    The question of possibility the power control programs switching for WWER-1000 is considered. The aim of this research is to determine the best program for the power control of nuclear reactor under cyclic diurnal behavior of electrical generation, as well as the switching implementation. The considered problem of finding the best control program refers to the multicriteria optimization class of problems. Operation of the nuclear power generation system simulated using the following power control programs: with constant average temperature of transfer fluid, with constant pressure in the reactor secondary circuit, with constant temperature in input of the nuclear reactor. The target function was proposed. It consists of three normalized criteria: the burn up fraction, the damage level of fuel rod array shells, as well as changes in the power values. When simulation of the nuclear power generation system operation within the life was done, the values of the selected criteria were obtained and inserted in the target function. The minimum of three values of the target function depending on the control program at current time defined the criterion of switching of considered static power control programs for nuclear power generation system

  1. Fuel Management of WWER-1000 Reactors of Kudankulam Nuclear Power Plant, India

    International Nuclear Information System (INIS)

    Pandey, Y.; Chauhan, A.

    2008-01-01

    Two units of WWER-1000 reactors of Russian design are under construction at Kudankulam site in India. These reactors are expected to be commissioned in 2008. The fuel management services for these reactors shall be carried out using Russian Computer codes. This paper includes a brief description of the core, fuel assembly lattice and physics modeling of the lattice and core for these reactors. Presented in this paper are the salient features of the core load pattern designs and fuel performance for 8 operating cycles of these reactors. The paper describes key improvements in the core load pattern designs to enhance the fuel utilization and its thermal behaviour. Presented in the paper are also the on site fuel management strategies with regard to fuel inventory and nuclear material accounting. A computer code for Fuel Inventory and Nuclear Material Accounting (FINMAC) has been developed for this purpose. The code FINMAC takes care of receipt of fresh fuel, flow between various accounting sub areas (ASAs), burnup or production of nuclear isotopes in the reactor cores and discharge from the reactor core. The code generates Material Balance Reports (MBRs) and Composition of Ending Inventory Reports (COEIs) as per the IAEA standards. (authors)

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

    International Nuclear Information System (INIS)

    2005-01-01

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

  3. Burnup influence on the WWER-1000 reactor vessel neutron fluence evaluation

    International Nuclear Information System (INIS)

    Panayotov, I.; Mihaylov, N.; Ilieva, K.; Kirilova, D.; Manolova, M.

    2009-01-01

    The neutron fluence of the vessels of the reactors is determined regularly accordingly the RPV Surveillance Program of Kozloduy NPP Unit 5 and 6 in order to assess the state of the metal vessel and their radiation damaging. The calculations are carried out by the method of discrete ordinates used in the TORT program for operated reactor cycles. An average reactor spectrum corresponding to fresh U-235 fuel is used as an input neutron source. The impact of the burn up of the fuel on the neutron fluence of WWER-1000 reactor vessel is evaluated. The calculations of isotopic concentrations of U-235 and Pu-239 corresponding to 4 years burn up were performed by the module SAS2H of the code system SCALE 4.4. Since fresh fuel or 4 years burn up fuel assembly are placed in periphery of reactor core the contribution of Pu-239 of first year burn up and of 4 years burn up is taken in consideration. Calculations of neutron fluence were performed with neutron spectrum for fresh fuel, for 1 year and for 4 years burn up fuel. Correction factors for neutron fluence at the inner surface of the reactor vessel, in ? depth of the vessel and in the air behind the vessel were obtained. The correction coefficient could be used when the neutron fluence is assessed so in verification when the measured activity of ex-vessel detectors is compared with calculated ones. (Authors)

  4. Effect of burnup history by moderator density on neutron-physical characteristics of WWER-1000 core

    International Nuclear Information System (INIS)

    Ovdiienko, I.; Kuchin, A.; Khalimonchuk, V.; Ieremenko, M.

    2011-01-01

    Results of assessment of burnup history effect by moderator density on neutron physical characteristics of WWER-1000 core are presented on example of stationary fuel loading with Russian design fuel assembly TWSA and AER benchmark for Khmelnitsky NPP that was proposed by TUV and SSTC NRC at nineteenth symposium. Assessment was performed by DYN3D code and cross section library sets generated by HELIOS code. Burnup history was taken into account by preparing of numerous cross section sets with different isotopic composition each of which was obtained by burning under different moderator density. For analysis of history effect 20 cross section sets were prepared for each fuel assembly corresponded to each of 20 axial layers of reactor core model for DYN3D code. Four fuel cycles were modeled both for stationary fuel loading with TWSA and AER benchmark for Khmelnitsky NPP to obtain steady value of error due to neglect of burnup history effect. Main attention of study was paid to effect of burnup history by moderator density to axial power distribution. Results of study for AER benchmark were compared with experimental values of axial power distribution for fuel assemblies of first, second, third and fourth year operation. (Authors)

  5. Comparison of HRA methods based on WWER-1000 NPP real and simulated accident scenarios

    International Nuclear Information System (INIS)

    Petkov, Gueorgui

    2010-01-01

    Full text: Adequate treatment of human interactions in probabilistic safety analysis (PSA) studies is a key to the understanding of accident sequences and their relative importance in overall risk. Human interactions with machines have long been recognized as important contributors to the safe operation of nuclear power plants (NPP). Human interactions affect the ordering of dominant accident sequences and hence have a significant effect on the risk of NPP. By virtue of the ability to combine the treatment of both human and hardware reliability in real accidents, NPP fullscope, multifunctional and computer-based simulators provide a unique way of developing an understanding of the importance of specific human actions for overall plant safety. Context dependent human reliability assessment (HRA) models, such as the holistic decision tree (HDT) and performance evaluation of teamwork (PET) methods, are the so-called second generation HRA techniques. The HDT model has been used for a number of PSA studies. The PET method reflects promising prospects for dealing with dynamic aspects of human performance. The paper presents a comparison of the two HRA techniques for calculation of post-accident human error probability in the PSA. The real and simulated event training scenario 'turbine's stop after loss of feedwater' based on standard PSA model assumptions is designed for WWER-1000 computer simulator and their detailed boundary conditions are described and analyzed. The error probability of post-accident individual actions will be calculated by means of each investigated technique based on student's computer simulator training archives

  6. Study of transient connected with WWER-1000 cluster drop with subsequent working of automatic power controller

    International Nuclear Information System (INIS)

    Kuchin, A.; Ovdiienko, I.; Khalimonchuk, V.

    2010-01-01

    Results of calculation study of transient connected with drop of WWER-1000 cluster of working group are presented. Transient was considered in the mode of automatic power control without forming of warning protection signal due to reaching of dropped cluster of core bottom. Calculations are shown that given transient can cause valuable distortion of power distribution in axial direction. At that main increase of pin power is occurred in upper part of the core, whereas power in lower part is almost not changed. The additional increase of power in the upper part of core makes conditions for initiation of DNB. This effect can be observed if in initial state axial power distribution is displaced in upper part of core nearby to rest of supported power clusters of working group. It is necessary to define conservatively with taking into account assumed working group efficiency-in which row from extracted clusters of working group the displacement of axial power in the upper part is possible. Probability of such displacement and its localization in plane of core must be properly analyzed. The work was performed in framework of orders BMU SR 2511 and BMU R0801504 (SR2611). The report describes the opinion and view of the contractor-State Scientific and Technical Centre on Nuclear and Radiation Safety-and does not necessarily represent the opinion of the ordering party - BMU-BfS/GRS and TUEV SUED. (Authors)

  7. WWER-1000 unit reliability problems from the point of view of the main supplier of technological equipment

    International Nuclear Information System (INIS)

    Bursa, V.; Holousova, M.; Turnik, S.

    1990-01-01

    At Skoda Works in Plzen, data from the period of construction of nuclear power plants are processed on an ICL DRS 300 computer. The database systems DBASE II and DATAFLEX are available for creating reliability information systems. The information system that is being developed for WWER-1000 units is tested at the WWER-440 units of the Dukovany and Mochovce nuclear power plants. Activities in the field of evaluation of structure reliability of WWER-1000 nuclear power plants are aimed at two major goals, viz., developing a methodology for testing the reliability of the whole unit and its subsystems, and performing reliability analysis and calculations of reliability indices of the secondary circuit of a WWER-1000 nuclear power plant. The reason for the latter concern is the fact that in 1984-1986, secondary circuits contributed 46% to failures of Czechoslovak WWER-440 nuclear power plants. According to existing analyses, the time fluctuations of reliability indices obey no rule that could be employed for inferring indices expected in steady-state operating conditions from indices established in the starting stage of operation. (Z.M.). 10 refs

  8. The procedure for determination of special margin factors to account for a bow of the WWER-1000 fuel assemblies

    International Nuclear Information System (INIS)

    Tsyganov, S. V.; Marin, S. V.; Shishkov, L. K.

    2008-01-01

    Starting from 1980s, the problem of bow of the WWER-1000 reactor fuel assemblies and the effect of that on the operational safety is being discussed. At the initial period of time, the extension of time for dropping control rods of the control and protection system associated with this bow posed the highest threat. Later on, new more rigid structures were developed for fuel assemblies that eliminated the problems of control rods. However, bow of the WWER-1000 reactor fuel assemblies is observed up to now. The scale of this bow reduced significantly but it still effects safety. Even a minor bow available may lead to the noticeable increase of power of individual fuel pins associated with the local variation of the coolant amount. This effect must be taken into account on designing fuel loadings to eliminate the exceeding of set limitations. The introduction of additional special margins is the standard method for taking this effect into account. The present paper describes the conservative technique for the assessment of additional margins for bow of fuel assemblies of state-of-the-art designs. This technique is employed in the WWER-1000 reactor designing. The chosen conservatism degree is discussed as well as the method for its assurance and acceptable ways for its slackening. The example of the margin evaluation for the up-to-date fuel loading is given. (authors)

  9. Dynamic behavior structural response and capacity evaluation of the standardized WWER-1000 nuclear power plants subjected to severe loading conditions

    International Nuclear Information System (INIS)

    Ambriashvili, Y.K.; Krutzik, N.J.

    1993-01-01

    In order to verify the structural capacity of standardized WWER-1000 MW nuclear power plants, comprehensive static and dynamic analyses were performed in cooperation between Siemens and Atomenergoprojekt. The main goal of these investigations was to perform of a number of seismic analyses of standardized WWER-1000 reactor buildings on the basis of 13 given seismological inputs, taking into account the local soil conditions at 17 different sites defined by in-situ investigations. The analyses were based on appropriate mathematical models (equivalent beam models as well as detailed spatial surface element models) of the coupled vibrating structures (base structure, outer structure, containment, inner structure) and of the layered soil. The analyses were mainly performed using the indirect method (substructure method). Based on the results of the seismic analysis as well as the results of static analysis (pressure and temperature due to LOCA, dead weight, prestressing) an assessment was made of the seismic safety of the containment and the reactor building. Using a complex 3-dimensional model of the structure and the soil, the influence of the flexibility of the basement structure on the structural response was also studied. The structural analyses of the WWER-1000 reactor building led to the conclusion that its design accounts well for the main factors governing the dynamic behavior of the building. The assessment of the forces acting in the structures shows that the bearing capacity of the analyzed building structure corresponds to an earthquake intensity of about 0.2 g to 0.25 g

  10. An approach to stability analysis of spatial xenon oscillations in WWER-1000 reactors

    International Nuclear Information System (INIS)

    Parhizkari, H.; Aghaie, M.; Zolfaghari, A.; Minuchehr, A.

    2015-01-01

    Highlights: • The multipoint methodology is developed for xenon oscillation in the BNPP. • The axial, radial and azimuthal offsets are calculated in the BOC and EOC. • It is shown that the all of oscillation modes are safe in the BOC. • The axial oscillation is not safe in the EOC and needs governor control system. • The multipoint kinetics show good agreement for spatial oscillations. - Abstract: Spatial power oscillations due to spatial distribution of xenon transient are well known as xenon oscillation in large reactors. Xenon-induced spatial power oscillations occur as a result of rapid perturbations to power distribution that cause the xenon and iodine distribution to be out of phase with the perturbed power distribution. This results in a shift in xenon and iodine distributions that causes the power distribution to change in an opposite direction from the initial perturbation. In this paper xenon-induced power oscillation is described by a system of differential equations with non-linearity between xenon and flux distributions; the dynamics of process is described by a discrete distributed parameter model, with the neutron flux, the delayed neutrons, the core temperature and the xenon and iodine concentrations as the “states” of the system. It is shown that it is possible to describe the discrete distributed-parameter as a set of coupled point-reactor models. It is also shown that using this scheme it is possible to analyze the control aspects of a multi-section large core reactor by treating only two adjacent sections of the core. To illustrate the capability and efficiency of the proposed scheme Bushehr Nuclear Power Plant, BNPP, which is a WWER-1000 reactor, is chosen to show the performance of the methodology. The axial, azimuthal and radial power oscillation at the beginning of cycle, BOC, and the end of cycle, EOC, for BNPP are investigated; the results are in good agreement with safety analysis report of the reference plant

  11. Seismic strengthening of overhead roads between reactor buildings of WWER-1000 MW type NPP

    International Nuclear Information System (INIS)

    Stoyanov, G.; Jordanov, M.

    2005-01-01

    This paper presents results obtained during the upgrading design of overhead roads (OHR) between WWER-1000 MW Reactor Units at Kozloduy NPP. In order to avoid the deficiencies of OHR seismic capacity different approaches were developed based on the site and structure specifics. Overhead roads are precasted RC structures. They consist of pedestrian gallery and pipeline RC box, connecting reactor buildings with auxiliary building. They are mounted at approximately 10 m above ground level. The overhead roads are evaluated at their as-is status and a seismic upgrading of the structure is designed. The analysis of the upgraded structure is performed for Review Level Earthquake (RLE). Soil-Structure Interaction (SSI) effects are taken into account through equivalent soil springs with frequency adjusted stiffnesses. The upgraded structure is checked for conformance with the specially developed technical design specification based on International, US and Bulgarian standards and codes, taking into account site specific conditions. The general approach is consistent with up-to-date practice for evaluation and upgrade of nuclear power plant facilities. The existing site conditions and Owner's requirements are taken into account during development of the upgrading. The proposed upgrading measures can be divided in two major categories global and local. Special attention is paid to improvement of the ductile behavior of the structure through new detailing and upgrading of existing connection. These measures are grouped in two final design concepts and after a comparative study one of them is chosen for implementation. For the upgraded structure response spectra are derived at locations where equipment is attached. (authors)

  12. Study on severe accidents and countermeasures for WWER-1000 reactors using the integral code ASTEC

    International Nuclear Information System (INIS)

    Tusheva, P.; Schaefer, F.; Altstadt, E.; Kliem, S.; Reinke, N.

    2011-01-01

    The research field focussing on the investigations and the analyses of severe accidents is an important part of the nuclear safety. To maintain the safety barriers as long as possible and to retain the radioactivity within the airtight premises or the containment, to avoid or mitigate the consequences of such events and to assess the risk, thorough studies are needed. On the one side, it is the aim of the severe accident research to understand the complex phenomena during the in- and ex-vessel phase, involving reactor-physics, thermal-hydraulics, physicochemical and mechanical processes. On the other side the investigations strive for effective severe accident management measures. This paper is focused on the possibilities for accident management measures in case of severe accidents. The reactor pressure vessel is the last barrier to keep the molten materials inside the reactor, and thus to prevent higher loads to the containment. To assess the behaviour of a nuclear power plant during transient or accident conditions, computer codes are widely used, which have to be validated against experiments or benchmarked against other codes. The analyses performed with the integral code ASTEC cover two accident sequences which could lead to a severe accident: a small break loss of coolant accident and a station blackout. The results have shown that in case of unavailability of major active safety systems the reactor pressure vessel would ultimately fail. The discussed issues concern the main phenomena during the early and late in-vessel phase of the accident, the time to core heat-up, the hydrogen production, the mass of corium in the reactor pressure vessel lower plenum and the failure of the reactor pressure vessel. Additionally, possible operator's actions and countermeasures in the preventive or mitigative domain are addressed. The presented investigations contribute to the validation of the European integral severe accidents code ASTEC for WWER-1000 type of reactors

  13. Comparative analysis of exercise 2 results of the OECD WWER-1000 MSLB benchmark

    International Nuclear Information System (INIS)

    Kolev, N.; Petrov, N.; Royer, E.; Ivanov, B.; Ivanov, K.

    2006-01-01

    In the framework of joint effort between OECD/NEA, US DOE and CEA France a coupled three-dimensional (3D) thermal-hydraulic/neutron kinetics benchmark for WWER-1000 was defined. Phase 2 of this benchmark is labeled W1000CT-2 and consists of calculation of a vessel mixing experiment and main steam line break (MSLB) transients. The reference plant is Kozloduy-6 in Bulgaria. Plant data are available for code validation consisting of one experiment of pump start-up (W1000CT-1) and one experiment of steam generator isolation (W1000CT-2). The validated codes can be used to calculate asymmetric MSLB transients involving similar mixing patterns. This paper summarizes a comparison of the available results for W1000CT-2 Exercise 2 devoted to core-vessel calculation with imposed MSLB vessel boundary conditions. Because of the recent re-calculation of the cross-section libraries, core physics results from PARCS and CRONOS codes could be compared only. The comparison is code-to-code (including BIPR7A/TVS-M lib) and code vs. plant measured data in a steady state close to the MSLB initial state. The results provide a test of the cross-section libraries and show a good agreement of plant measured and computed data. The comparison of full vessel calculations was made from the point of view of vessel mixing, considering mainly the coarse-mesh features of the flow. The FZR and INRNE results from multi-1D calculations with different mixing models are similar, while the FZK calculations with a coarse-3D vessel model show deviations from the others. These deviations seem to be due to an error in the use of a boundary condition after flow reversal (Authors)

  14. The main conditions ensured problemless implementation of 235U high enriched fuel in Kozloduy NPP (Bulgaria) - WWER-1000 Units

    International Nuclear Information System (INIS)

    Dobrevski, I.; Zaharieva, N.; Minkova, K.; Michaylov, G.; Penev, P.; Gerchev, N.

    2009-01-01

    The collected water chemistry and radiochemistry data during the operation of the Kozloduy NPP Unit 5 for the period 2006-2009 (12-th, 13-th 14-th and 15-th fuel cycles) undoubtedly indicate for WWER-1000 Units (whose specific features are: Steam generators with austenitic stainless steel 08Cr18N10T tubing; Steam generators are with horizontal straight tubing and Fuel elements cladding material is Zr-1%Nb (Zr1Nb) alloy), that one realistic way for problemless implementation of 235 U high enriched fuel have been found. The main feature characteristics of this way are: Implementation of solid neutron burnable absorbers together with the dissolved in coolant neutron absorber - natural boric acid; Application of fuel cladding materials with enough corrosion resistance by the specific fuel cladding environment created by presence of SNB; Keeping of suitable coolant water chemistry which ensures low corrosion rates of core- and out-of-core- materials and limits in core (cladding) depositions and restricts out-of-core radioactivity buildup. The realization of this way in WWER-1000 Units in Kozloduy NPP was practically carried out through: 1) Implementation of Russian fuel assemblies TVSA which have as fuel cladding material E-110 alloy (Zr1Nb) with enough high corrosion resistance by presence of sub-cooled nucleate boiling (SNB) and use burnable absorber (Gd) integrated in the uranium-gadolinium (U-Gd 2 O 3 ) fuel (fuel rod with 5.0% Gd 2 O 3 ); 2) Development and implementation of water chemistry primary circuit guidelines, which require the relation between boric acid concentration and total alkalising agent concentrations to ensure coolant pH 300 = 7.0 - 7.2 values during the whole operation period. The above mentioned conditions by the passing of WWER-1000 Units in NPP Kozloduy to uranium fuel with 4.4% 235 U (TVSA fuel assemblies) practically ensured avoidance of the creation of the necessary conditions for AOA onset. The operational experience (2006-2009) of the

  15. Calculational modeling of fuel assemblies of WWER-1000 type with the use of burnable absorber Gadolinum; comparative analysis

    International Nuclear Information System (INIS)

    Yeremenko, M.L.; Kovbasenko, Yu.P.; Loetsch, T.

    2001-01-01

    In connection with the beginning of the use of fuel assemblies with burnable absorbers by integration of Gadolinum into the nuclear fuel at Ukrainian NPP the task of testing the code systems and the pertinent neutron cross section libraries for the new fuel arose. Taking into account the long term experience of German experts with calculations and evaluation of nuclear fuel containing Gadolinum it was decided to carry out a series of test calculations for fuel assembly lattices of PWR, WWER-440 and WWER-1000 types using the NESSEL/PYTHIA and CASMO/SIMULATE code systems (Authors)

  16. Evolution of ASTEC V1.2 rev.1 code for WWER-1000 reactors/SBO sequence

    International Nuclear Information System (INIS)

    Georgieva, J.; Stefanova, A.; Groudev, P.; Tusheva, P.; Kalchev, B.; Passalacqua, R.

    2006-01-01

    In this paper a comparison between calculations of severe accidents occurred from WWER-1000 with ASTEC code specified for an event of full unloading with relief valves stuck opened with no hydroaccumulators intervention is presented. The purpose of the analyses provided is to present the relationship between the improvements of the actual version (ASTEC Vl.2 rev. 1) and ASTEC V1.1 p2 like: code modifications, incoming data improvements. Such discrepancies are to be examined. Case by case suggestions for ASTEC improvements are to be provided

  17. Quantum behaved Particle Swarm Optimization with Differential Mutation operator applied to WWER-1000 in-core fuel management optimization

    International Nuclear Information System (INIS)

    Jamalipour, Mostafa; Sayareh, Reza; Gharib, Morteza; Khoshahval, Farrokh; Karimi, Mahmood Reza

    2013-01-01

    Highlights: ► A new method called QPSO-DM is applied to BNPP in-core fuel management optimization. ► It is found that QPSO-DM performs better than PSO and QPSO. ► This method provides a permissible arrangement for optimum loading pattern. - Abstract: This paper presents a new method using Quantum Particle Swarm Optimization with Differential Mutation operator (QPSO-DM) for optimizing WWER-1000 core fuel management. Genetic Algorithm (GA) and Particle Swarm Optimization (PSO) have shown good performance on in-core fuel management optimization (ICFMO). The objective of this paper is to show that QPSO-DM performs very well and is comparable to PSO and Quantum Particle Swarm Optimization (QPSO). Most of the strategies for ICFMO are based on maximizing multiplication factor (k eff ) to increase cycle length and minimizing power peaking factor (P q ) in order to improve fuel integrity. PSO, QPSO and QPSO-DM have been implemented to fulfill these requirements for the first operating cycle of WWER-1000 Bushehr Nuclear Power Plant (BNPP). The results show that QPSO-DM performs better than the others. A program has been written in MATLAB to map PSO, QPSO and QPSO-DM for loading pattern optimization. WIMS and CITATION have been used to simulate reactor core for neutronic calculations

  18. Transient simulations in WWER-1000-comparison between DYN3D-ATHLET and DYN3D-RELAP5

    International Nuclear Information System (INIS)

    Grundmann, U.; Kliem, S.; Kozmenkov, Y.; Mittag, S.; Rohde, U.; Weiss, F.P.

    2003-01-01

    Simulations of a real transient of an operating WWER-1000 power plant have been performed using DYN3D-ATHLET (Gru95) and DYN3D-RELAP5 (Koy01) code systems in the frame of activities aimed at a validation of the neutronic / thermal-hydraulic coupled codes. The transient initiated by a main coolant pump switching off, when three of the four main coolant pumps of the plant are in operation (scenario of the VALCO project) is chosen for the simulation. The same models of the plant (except the core nodalization) but two different libraries of macroscopic cross-sections have been used in compared calculations. Additionally, the compared code systems are based on the different / external and internal / coupling techniques. This paper contains a brief description of the coupled codes and the plant model as well as a comparison between the results from simulations (Authors)

  19. Study of accelerated unit unloading mode initiated by turbine feed pump trip with TVSA fuel assemblies operation in WWER-1000

    International Nuclear Information System (INIS)

    Borysenko, V.I.; Kadenko, I.N.; Samoilenko, D.V.

    2012-01-01

    This paper provides the study results of accelerated unit unloading mode (AUU) initiated at WWER-1000 unit operated at 100 % power and its expediency in the event of single Turbo Feed Pump (TFP) failure. Modeling was performed using an advanced calculation code RELAP/SCDAPSIM/Mod3.4 and relevant model for KhNPP Unit No. 2. As the study shows, SCRAM cannot be prevented in case of failure of 3 main circulation pumps due to steam generators (SG) level drop. Based on the results obtained, it is reasonably justified to allow SCRAM signal instead of AUU activation in case of single TFP failure at power level more than 90 % of N n om. This will provide more sparing temperature modes for fuel assemblies and equipment, as well as prevent additional thermal cycling loads and violation of safe operation limits as SG water levels

  20. Development of new chemical and electrochemical decontamination methods for selected equipment of WWER-440 and WWER-1000 reactor primary circuit

    International Nuclear Information System (INIS)

    Solcanyi, M.; Majersky, D.

    1998-01-01

    Special devices for in-situ application of decontamination technologies assigned for Steam Generator, Pressurizer and Main Circulating Casing of WWER-1000 type were designed, manufactured and tested in real conditions of their use in above Primary Circuit components. New decontamination technologies like low-concentration process NP-NHN for the decontamination of the Steam Generator, combined chemico-mechanical treatment for the Pressurizer and semi-dry electrolysis for the Main Circulating Pump Casing were developed and approved for their safe plant application from point of view of decontamination efficiency, corrosion influence and processing of secondary wastes. Main technological parameters were defined to achieve high decontamination efficiency and corrosion-safe application of all decontamination technologies. (author)

  1. Problem Oriented Neutron-Gamma Cross Sections Libraries for WWER-440 and WWER-1000 Shielding and Reactor Vessel Dosimetry Application

    International Nuclear Information System (INIS)

    Belousov, S.; Antonov, S.; Ilieva, K.

    1997-01-01

    The 47 neutron and 20 gamma group libraries BGL-440 and BGL-1000 for the shielding and reactor vessel dosimetry application have been generated for WWER-440 and WWER-1000 by collapsing the VITAMIN-B6 library (199 neutron and 42 gamma groups on the base of ENDF/B-6). The first parts of the libraries for neutron-gamma transport calculation, BGL-440-1 (150 nuclides) and BGL-1000-1 (140 nuclides), have been generated by a modified version of SAS1X control module of the SCALE system. The appropriate zone-average neutron flux had been used for these sub-libraries collapsing. The BGL-440-2 and BGL-1000-2 sub-libraries consist of cross sections for all 120 nuclides of VITAMIN-B6, for calculation of the transport through non-reactor materials of dosimeters, capsules, specimens which may be placed in the cavity behind the reactor vessel. The neutron spectrum just beyond the RPV had been used for this collapsing. As the first test the comparative calculations of the neutron flux on/behind the WWER-1000 reactor vessel have been realised using the libraries BGL-1000 and BUGLE, intended for the American PWR reactors. The integral neutron flux values by BGL-1000 and BUGLE differ by 3% onto the vessel, and 5% behind the vessel. This result shows that the calculations of the neutron flux responses for the WWER vessel surveillance, especially in locations behind the WWER vessel have to be done by the appropriate BGL library. Key words: neutron transport, multigroup neutron cross section libraries

  2. Effect of high-temperature filtration on impurity composition in the primary circuit coolant of power units with WWER-1000 reactors

    International Nuclear Information System (INIS)

    Efimov, A.A.; Moskvin, L.N.; Gusev, B.A.; Leont'ev, G.G.; Nekrest'yanov, S.N.

    1992-01-01

    The effects of high-temperature filtration on changes in dispersive, chemical, radioisotope and phase compositions of impurities in primary circuit coolant of NPP with the WWER-1000 reactor are studied. Special filters are used for the studies. The data obtained confirm the applicability of high-temperature filtration for purification of WWER reactor water and steam separators at NPPs with RBMK reactors

  3. WWER identification and analysis of dominant factors affecting the fuel failure rates in WWER-1000 units in Czech Republic, Bulgaria, Ukraine and Russia

    International Nuclear Information System (INIS)

    Evdokimov, I.; Likhanskii, V.; Afanasieva, E.; Kanukova, V.; Kozhakin, A.; Maslova, L.; Chernetskiy, M.; Zborovskii, V.; Sorokin, A.

    2015-01-01

    The paper reviews the major findings of the study in the frame of the “Zero Failure Rate” project for WWER. The study included analysis and systematization of available data on leaking fuel assemblies found in 2003 through 2014 in WWER-1000 nuclear units in Russia, Ukraine, Czech Republic and Bulgaria. The study was intended to be used in preparation of recommendations and elaboration of corrective measures for enhancement of reliability and decrease of the failure rates for the WWER-1000 fuel. One of the key areas in successful implementation of the industry ‘zero failure’ goal is a challenge of significant increase of inspections of WWER-1000 fuel assemblies. It may be reasonable (with account taken for international experience) to think of development of more effective equipment for prompt fuel inspections & repair in WWER-1000 spent fuel pool. Another challenge is the elaboration of unified fuel inspection guidelines to ensure that limited industry resources are spent in the most productive way. In the frame of this work it may be helpful to implement in practice the criteria for safe removal of defective fuel rods from the leaking FA under repair

  4. Determination of neutron fluence and radiation brittleness temperature of WWER-440 and WWER-1000 pressure vessels in Kozloduy NPP

    International Nuclear Information System (INIS)

    Ilieva, K.; Apostolov, T.; Belousov, S.; Petrova, T.; Antonov, S.; Ivanov, K.; Prodanova, R.

    1993-01-01

    In Units 1-4 of Kozloduy NPP (WWER-440/230), the weld 4 of RPV undergoes the most severe irradiation embrittlement. Neither witness-samples, nor detectors are designed for these reactors. Transport calculations of fast neutron fluence on WWER-440 RPV and ex-vessel measurements by threshold activation detectors are the primary means for adequate assessment of metal state and for prognosis concerning the reactor life span. In WWER-1000 reactors (Units 5-6) the maximum neutron fluence occurs on the weld 3. The systematical observation of metal state is performed through witness-samples and threshold activation detectors ( 54 Fe (n,p), 63 Cu (n,α), 93 Nb (n,n')) placed above the reactor top edge and at the first vessel ring level. There are big differences in energy spectrum and integral neutron flux falling onto the weld 3, the RPV base metal and the staff detectors. This requires additional neutron measurements in the air gap between the RPV and the thermal insulation. (author)

  5. Experience in start-up of the South-Ukrainian-2 power unit with the WWER-1000 reactor

    International Nuclear Information System (INIS)

    Belov, Yu.V.; Kazakov, V.A.; Kirilov, V.V.; Kryakvin, L.V.

    1987-01-01

    The volume, sequence and dates of works fulfilled during hot testing, physical and power start-ups and while bringing output of the South-Ukranian-2 power unit with the WWER-1000 reactor to the design figure are described. The works were fulfilled according to the standard schedules from October in 1984 till April in 1985. Combination of the stages and intensification of works before the physical start-up have allowed to shorten the dates by 90 days as compared to the schedule. The physical and power start-ups, including bringing reactor output to the design figure, were performed during 140 days, that permits to shorten the dates by 20 days more. The results of physical experiments carried out at the South-Ukranian-2 power unit, are in good agreement with the data obtained at the first power units of the given and Kalinin NPPs. Besides, during physical and power start-ups additional measures ensuring nuclear safety are developed

  6. Power release estimation inside of fuel pins neighbouring fuel pin with gadolinium in a WWER-1000 type core

    International Nuclear Information System (INIS)

    Mikus, J.

    2006-01-01

    The purpose of this work consists in investigation of the gadolinium fuel pin (fps) influence on space power distribution, especially from viewpoint of the values and gradient occurrence inside of neighbouring FPs that could result in static loads with some consequences, e.g., FP bowing. Since detailed power distributions cannot be obtained in the NPPs, needed information is provided by means of experiments on research reactors. As for the power release measurement inside of FPs, some special (e.g. track) detectors placed between fuel pellets are usually used. Since such works are relatively complicated and time consuming, an evaluation method based on mathematical modelling and numerical approximation was proposed by means of that, and using measured (integral) power release in selected FPs, relevant information about power release inside of needed (investigated) FP, can be obtained. For this purpose, an experiment on light water, zero-power research reactor LR-0 was realized in a WWER-1000 type core with 7 fuel assemblies at zero boron concentration and containing gadolinium FPs. Application of the above evaluation method is demonstrated on investigated FP neighbouring a FP with gadolinium by means of the 1) Azimuthal power distribution inside of investigated FP on their fuel pellet surface in horizontal plane and 2) Gradient of the power distribution inside of investigated FP in two opposite positions on pellets surface that are situated to- and outwards a FP with gadolinium. Similar information can be relevant from the viewpoint of the FP failures occurrence investigation (Authors)

  7. Comparison calculations of WWER-1000 fuel assemblies by using the MCNP 4.2 a KASSETA codes

    International Nuclear Information System (INIS)

    Trgina, M.

    1993-12-01

    The power multiplication and distribution factors are compared for various geometries and material configurations of WWER-1000 fuel assemblies. The calculations were performed in 2 ways: (i) using nuclear data, employing older and current data collections, and (ii) using the author's own model based on the KASSETA code. The comparison code MCNP 4.2 is described, intended for computerized simulation of the transport of neutrons, photons and electrons. This code uses its own cross section library. The methodology is outlined and a specification of the Monte Carlo method employed is given. The use of the refined data library gave rise to appreciable deviations of the multiplication factors in all variants. The use of the older data library led to identical criticality results for the variant with water holes. For inserted absorbers the discrepancies in criticality and in power distribution data are appreciable. The marked disagreement between the results of application of the MCNP 4.2 and KASSETA codes for the variants with inserted control elements is indicative of inappropriateness of the approximation procedure in the latter code. (J.B.). 2 tabs., 11 figs., 11 refs

  8. Effect of nickel content on mechanical properties and fracture toughness of weld metal of WWER-1000 reactor vessel welded joints

    Energy Technology Data Exchange (ETDEWEB)

    Zubchenko, A.S.; Vasilchenko, G.S.; Starchenko, E.G.; Nosov, S.I

    2004-08-01

    Welding of WWER-1000 reactor vessel of steel 15X2HMPHIA is performed using the C{sub B}-12X2H2MAA wire and PHI-16 or PHI-16A flux. Nickel content in the weld metal usually lays within the limits 1.2-1.9%. The experimental data is shown on the weld metal with the nickel contents 1.28-2.45% after irradiation with fluence up to 260.10{sup 22}n/m{sup 2} at energy more than 0.5 MEV. The embrittlement was measured by shift of critical brittleness temperature. Has appeared, that the weld metal with the low nickel content is the least responsive to irradiation embrittlement. The mechanical properties and fracture toughness of the weld metal with the contents of a nickel less than 1.3% are studied. Specimens CT-1T are tested, the 'master-curve', and its confidence bounds with probability of destruction 5 and 95% is built. 'Master-curve' in the specified confidence interval is affirmed by CT-4T specimens test data. Is shown, that the mechanical properties and fracture toughness of the weld metal with the contents of nickel less than 1.3% satisfy the normative requirements.

  9. Effect of nickel content on mechanical properties and fracture toughness of weld metal of WWER-1000 reactor vessel welded joints

    International Nuclear Information System (INIS)

    Zubchenko, A.S.; Vasilchenko, G.S.; Starchenko, E.G.; Nosov, S.I.

    2004-01-01

    Welding of WWER-1000 reactor vessel of steel 15X2HMPHIA is performed using the C B -12X2H2MAA wire and PHI-16 or PHI-16A flux. Nickel content in the weld metal usually lays within the limits 1.2-1.9%. The experimental data is shown on the weld metal with the nickel contents 1.28-2.45% after irradiation with fluence up to 260.10 22 n/m 2 at energy more than 0.5 MEV. The embrittlement was measured by shift of critical brittleness temperature. Has appeared, that the weld metal with the low nickel content is the least responsive to irradiation embrittlement. The mechanical properties and fracture toughness of the weld metal with the contents of a nickel less than 1.3% are studied. Specimens CT-1T are tested, the 'master-curve', and its confidence bounds with probability of destruction 5 and 95% is built. 'Master-curve' in the specified confidence interval is affirmed by CT-4T specimens test data. Is shown, that the mechanical properties and fracture toughness of the weld metal with the contents of nickel less than 1.3% satisfy the normative requirements

  10. Modernization in-core monitoring system, of WWER-1000 reactors (W-320) by fuel assemblies with individual characteristics using

    International Nuclear Information System (INIS)

    Mitin, V. I.; Semchenkov, J. M.; Kalinushkin, A. E.

    2007-01-01

    The present report covers object, conception, engineering solution of construction of modern system of high-powered reactor in-core control, including WWER-1000 (V-320) reactors. It is known that ICMS main task is on-line monitoring distribution of power release field and its functioning independently of design programs to avoid common reason error. It is shown in what way field of power release recovery has been carrying on; rest on the signals of in-core neutron and temperature sensors. On the base of the obtained and refined information there have being automatically generated signals of preventive and emergency protection on local parameters (linear power to the maximum intensive fuel elements, reserve to heat exchange crisis, 'picking factor'). There have represented technology on sensors and processing methods of SPND and TC signals, ICIS composition and structure, program hard ware, system and applied software. Structure, composition and the taken decisions allow combining class 1E and class B and C tasks in accordance with international norms of separation and safety classes' realization. At present ICIS-M is a system, providing implementation of control, safety, information and diagnostic functions, which allow securing actual increase of quality, reliability and safety in operation of nuclear fuel and NPP units. And at the same time it reduces human factor negative influence to core work thermo technical eliability in the operational process (Authors)

  11. Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants

    Energy Technology Data Exchange (ETDEWEB)

    Saunin, Yuri V.; Dobrotvorski, Alexander N.; Semenikhin, Alexander V.; Korolev, Alexander S. [JSC ' ' Atomtechenergo' ' , Novovoronezh (Russian Federation). Novovoronezh Filial ' ' Novovoronezhatomtechenergo' ' ; Ryasny, Sergei I. [JSC ' ' Atomtechenergo' ' , Moscow (Russian Federation)

    2017-09-15

    The JSC ''Atomtechenergo'' experts have developed a new methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants. The necessity for developing the new methodology was determined by the need to decrease the calculation error of the weighted mean coolant temperature in the hot legs because of the coolant temperature stratification. The methodology development was based on the findings of experimental and calculating research executed by the authors. The methodology verification was fulfilled through comparison of calculation results obtained with and without the methodology use in various operational states and modes of several WWER-1000 power units. The obtained verification results have confirmed that the use of the new methodology provides objective error decrease in determining the weighted mean coolant temperature in the primary circuit hot legs. The decrease value depends on the stratification character which is various for different objects and conditions.

  12. Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants

    International Nuclear Information System (INIS)

    Saunin, Yuri V.; Dobrotvorski, Alexander N.; Semenikhin, Alexander V.; Korolev, Alexander S.

    2017-01-01

    The JSC ''Atomtechenergo'' experts have developed a new methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants. The necessity for developing the new methodology was determined by the need to decrease the calculation error of the weighted mean coolant temperature in the hot legs because of the coolant temperature stratification. The methodology development was based on the findings of experimental and calculating research executed by the authors. The methodology verification was fulfilled through comparison of calculation results obtained with and without the methodology use in various operational states and modes of several WWER-1000 power units. The obtained verification results have confirmed that the use of the new methodology provides objective error decrease in determining the weighted mean coolant temperature in the primary circuit hot legs. The decrease value depends on the stratification character which is various for different objects and conditions.

  13. Report of a consultants meeting on control rod insertion reliability for WWER-1000 nuclear power plants. Extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1995-09-01

    Starting from 1992, an increased drop time of control rods exceeding the design limit of four seconds has been observed in most of the operating WWER-1000 reactors in Russia and in the Ukraine. In some cases a dropped control rod became stuck in an intermediate position near the bottom of the core. In October 1994, a similar control rod problem was also observed at Unit 6 of the Kozloduy NPP. The issue of control rod insertion reliability was considered at a consultants' meeting on ''Core Control and Protection Strategy of WWER-1000 Reactors'' in April 1994. A consultants' meeting specifically focused on ''Control Rod Insertion Reliability'' was convened in Vienna in February 1995 attended by 15 international experts. The objectives of this meeting were: The exchange of international experience on problems and solutions related to anomalous control rod insertion; judgement of the safety concern of this issue for WWER-1000 reactors based on safety analyses; consideration of regulatory requirements and interim measures to continue operation in short term including modifications implemented or planned; and, status of root cause analyses and pending problems. The technical discussions were held in plenary sessions and in three working groups devoted to specific aspects of the issue. Refs, figs, tabs

  14. Report of the review of WWER-1000 safety issues resolution at Temelin nuclear power plant, Temelin, Czech Republic 11 to 15 March 1996

    International Nuclear Information System (INIS)

    Almeida, C.; Hoehn, J.; Seiberling, R.; Chambon, J.L.; Fil, N.S.; Munoz, A.; Roennberg, G.; Wenk, W.

    1996-01-01

    At the request of the Government of the Czech Republic, the IAEA conducted, in the period of 11-15 March 1996, a mission to review the resolution of WWER-1000 safety issues at Temelin NPP. These safety issues have been identified for WWER-1000 model 320 reactors and ranked according to their importance to safety in the frameworks of the IAEA Extrabudgetary Programme on Safety of WWER and RBMK Nuclear Power Plants. The Temelin NPP is a WWER-1000 and was originally designed according to standards of the former Soviet Union. After a series of reviews in the 1980s, a decision was taken by the Temelin NPP management to upgrade the design of Temelin, including the supply of fuel and instrumentation and control by a western company. The objective of the mission was to review the response of Temelin to the safety issues identified by the IAEA. The mission assessed the current Temelin design, including proposed modifications and plans for operation at Temelin, in the light of the IAEA recommendations for each relevant issue. The present report contains the mission's general conclusions and recommendations and an overview of the review performed in each topical area. The attachment contains a brief summary of the discussions on each individual safety issue and associated conclusions and recommendations. 3 refs

  15. WWER-1000 steam generator integrity. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-07-01

    Programme was initiated by IAEA in 1990 with the aim to assist the countries of Central and Eastern Europe and former Soviet Union in evaluating the safety of their first generation WWER-440/230 nuclear power plants. The main objectives were: to identify major design and operational safety issues; to establish international consensus on priorities for safety improvements; and to provide assistance in the review of the competence and and adequacy of safety improvement programs. The scope was extended in 1992 ro include RBMK, WWER-440/312 and WWER-1000 plants in operation and under construction. Based on the operational experience of more than 90 reactor years of WWER-1000 NPPs having 80 steam generators in operation or under construction the steam generator integrity was recognized as an important issue of high safety concern. The purpose of this report is to integrate available information on the issue of WWER-1000 steam generator integrity with the focus on the steam generator cold collector damage in particular. This information covers the status of stem generators at operating plants, cause analysis of collector cracking, the damage mechanisms involved, operational aspects and corrective measures developed and implemented. Consideration is given to material, design and fabrication related aspects, operational conditions, system solutions, and in-service inspection. Detailed conclusions and recommendations are provided for each of these aspects

  16. Steam feeding redundancy for turbine-drives of feed pumps at WWER-1000 NPP

    International Nuclear Information System (INIS)

    Nesterov, Yu.V.; Shmukler, B.I.

    1987-01-01

    The system of steam supply for feed pump driving turbines (T) at the South Ukrainian Unit 1 according to the centralized redundancy principle is described. T is feeded through the collector of water auxiliary sytem (CWAS) to which steam from the third steam extraction line of turbine is supplied under thenormal regime. Under the reduction of turbine load, live steam from the steam generator is supplied to CWAS through the pressure regulator, possesing 10 s speed of responce. In this case the level reduction in the steam generator makes up 170 mm

  17. Seismic evaluation and upgrading design of overhead roads between reactor buildings of WWER-1000 MW type NPP

    International Nuclear Information System (INIS)

    Jordanov, M.J.; Stoyanov, G.S.; Geshanov, I.H.; Kirilov, K.P.; Schuetz, W.

    2003-01-01

    This paper presents results obtained during the study of overhead roads between Reactor Building (RB) of WWER-1000 MW NPP and possible measures for their seismic upgrade. The main objective of this project is to evaluate the behavior of overhead roads under site-specific seismic loading and to determine whether this structure satisfies current international safety regulations, followed by development of upgrading concepts. Overhead roads are pre-cast RC structure, which can be divided to separate substructures. They comprise of pedestrian gallery and pipeline box, connecting reactor buildings with auxiliary building. They are mounted at approximately 10 m above ground level. The overhead roads are evaluated for Review Level Earthquake (RLE) as seismic category II structures. As seismic input motion is RLE, free field response spectra anchored to 0.2 g PGA are used with 0.5 scaling factor. Soil-Structure Interaction effects are taken into account through equivalent soil springs with frequency adjusted stiffness. In order to meet the objective of the project a technical design specification is developed for conformance with International, US and Bulgarian standards and codes, taking into account site specific conditions. The general approach is consistent with up-to-date practice for evaluation and upgrade of nuclear power plant facilities. The separate steps comprising the overall fulfillment of project's major objectives may be summarized as follows: study of all available data for initial design and as built conditions, creation of 3-D detailed finite element models for as-built structure, determination of dynamic characteristics, evaluation of adequacy of initial design under new seismic loading (calculation of D/C ratios for structural members and connections, evaluation of embedment lengths for embedded parts and rebars, deformation evaluation, stability checks), development of upgrading concepts for enhancement, verification of capability of upgraded structure

  18. Development of Generic SAM Strategies and Evaluation of their Implementability at Operating WWER-1000/V-320 Power Units

    International Nuclear Information System (INIS)

    Podshibiakin, A.K.; Fil, N.S.; Kuznetsova, T.E.; Krushelnitsky, V.N.; Peressadko, V.G.; Korshunov, A.S.

    2001-01-01

    requirements give, although implicitly, the certain directions with regard to approac h to be used when developing the BDBA management measures. The BDBA management measures shall include the following: - determination of the operational objectives in order to prevent or to terminate core melting and to mitigate radioactive release into the environment; - determination of systems and equipment on the NPP site and outside it that could be used to achieve the operational objectives; - development of the strategies for personnel's actions to achieve the safety objectives. It's worth noting that the accident management strategies should foresee the usage of all the available systems and components (including systems and components not related to safety) that could be applied not in accordance with design purpose and under off-design operational conditions. This paper presents: the Current status of AM at operating WWER-1000 (Instruction on accident liquidation, Guideline on BDBA management, Upgrading the BDBA management); the approach to generic SAM strategy development, the evaluation of generic strategies for operating WWER-1000, the severe accident mitigation in advanced WWER-1000/V-392 design (NVAES-2 design, Hydrogen control, Containment function provisions)

  19. WWER-1000 dominance ratio

    International Nuclear Information System (INIS)

    Gorodkov, S.S.

    2009-01-01

    Dominance ratio, or more precisely, its closeness to unity, is important characteristic of large reactor. It allows evaluate beforehand the number of source iterations required in deterministic calculations of power spatial distribution. Or the minimal number of histories to be modeled for achievement of statistical error level desired in large core Monte Carlo calculations. In this work relatively simple approach for dominance ratio evaluation is proposed. It essentially uses core symmetry. Dependence of dominance ratio on neutron flux spatial distribution is demonstrated. (Authors)

  20. Calculation of isotope burn-up and change in efficiency of absorbing elements of WWER-1000 control and protection system during burn-up

    International Nuclear Information System (INIS)

    Timofeeva, O.A.; Kurakin, K.U.

    2006-01-01

    The report deals with fast and thermal neutron flows distribution in structural elements of WWER-1000 fuel assembly and absorbing rods, determination of absorbing isotope burn-up and worth variation in WWER reactor control and protection system rods. Simulation of absorber rod burn-up is provided using code package SAPPHIRE 9 5 end RC W WER allowing detailed description of the core segment spatial model. Maximum burn-up of absorbing rods and respective worth variation of control and protection system rods is determined on the basis of a number of calculations considering known characteristics of fuel cycles (Authors)

  1. Lessons learned from the computational simulation of thermomechanical behaviour of the WWER-1000 reactor cores: FA development and its implantation into the Balakovo NPP unit 1

    International Nuclear Information System (INIS)

    Troyanov, V.; Likhatchev, Y.; Folomeev, V.; Demishonkov, A.

    2003-01-01

    The fuel assembly is forced under operation conditions by weight and hydraulic force; hold-down force; contact transversal forces; non-uniform thermal and neutron fields; thermomechanical forces in the fuel assembly multirod structure. The fuel assembly bowing has been investigated in this work. The objective of the study is to recommend the optimal design for fuel assemblies. Calculations are made using the code TEREMOK. A new generation fuel assemblies for WWER-1000 named FA-2 are suggested. The performance of the FA- 2 has been studied. The theoretical approach and the calculation technique have been verified

  2. Calculations of fission rate distribution in the core of WWER-1000 mock-up on the LR-0 reactor using alternative methods and comparison with results of measurements

    International Nuclear Information System (INIS)

    Zaritskiy, S.; Kovalishin, A.; Tsvetkov, T.; Rypar, V.; Svadlenkova, M.

    2011-01-01

    General review of experimental and calculation researches on WWER-440 and WWER-1000 mock-ups on the reactor LR-0 was introduced on the twentieth Symposium AER. The experimental core fission rate distribution was obtained by means of gamma-scanning of the fuel pins - 140La single peak (1596 keV) measurements and wide energy range (approximately 600-900 keV) measurements. Altogether from 260 to 500 fuel pins were scanned in different experiments. The measurements were arranged in the middle of the fuel (the active part of pin). Pin-to-pin calculations of the WWER-1000 mock-up core fission rate distribution were performed with several codes: Monte Carlo codes MCU-REA/2 and MCNPX with different nuclear data libraries, diffusion code RADAR (63 energy groups library) and code SVL based on Surface Harmonics Method (69 energy groups). Calculated data are compared with experimental ones. The obtained results allow developing the benchmark for core calculations methodologies, evaluating and validating source reliability for the out-of-core (inside and outside pressure vessel) neutron transport calculations. (Authors)

  3. RELAP5/MOD3.2 investigation of loss of in-house supply power for WWER 1000/320V

    International Nuclear Information System (INIS)

    Gencheva, R.; Pavlova, M.; Groudev, P.

    2001-01-01

    This paper discusses the results of the thermal-hydraulic investigations of the 'Loss of in-house supply power' accident at the Kozloduy NPP Unit 6. The RELAP5/MOD3.2 computer code has been used to stimulate the loss of in-house supply power accident in a WWER 1000 Nuclear Power Plant model. This model was developed at the Institute for Nuclear Research and Nuclear Energy for analyses of operational occurrences, abnormal events and design basis scenarios. It will provide a significant analytical capability for the Bulgarian technical specialists located at the Kozloduy NPP. The criteria used in selecting transient are: importance to safety, availability and suitability of data followed by suitability for RELAP5 code validation. The investigation of 'Loss of normal and reverse AC power' is a process that compares the analytical results obtained by RELAP5/MOD3.2 model of the WWER 1000 against experimental transient data obtained from Kozloduy NPP Unit 6. The comparisons between the RELAP5 results and the test data indicate good agreement

  4. Concept for creating program-technical complex of safety monitoring with system of safety parameters presentation functions on the basis of routine WWER-1000 systems

    International Nuclear Information System (INIS)

    Dunaev, V.G.; Tarasov, M. V.; Povarov, P.V.

    2005-01-01

    Prerequisites of creating the software-hardware complex for reactor safety monitoring on the Volgodonsk NPP are analyzed and generalized. The concept of this complex is based on functions of the safety parameters presentation system. It will serve as an interface between operator and technological process and give to operator a possibility to estimate quickly the state of the safety of the nuclear power unit. The complex will be created on the basis of routine reactor monitoring and control systems intended for the WWER-1000 reactor. In addition to existing soft- and hard-wares for reactor monitoring and for analysis of technological archive, it is proposed to create and connect in parallel the new software-hardware complex which ensures calculation and presentation of generalized factors of reactor safety [ru

  5. Numerical modelling of the processes in the WWER-1000 containment building during cold leg LOCA using the CONTEMPT-LT/026 code

    International Nuclear Information System (INIS)

    Kolev, N.I.; Sybotinov, L.S.

    1984-01-01

    The CONTEMPT-LT/026 code has been used to produce numerical results for the processes in a WWER-1000 containment building during cold leg LOCA with break at the reactor vessel. The objective of the analysis is to estimate the maximal loads on the containment in case of LOCA. Available design data for the geometry and for the operational characteristics of the low-pressure ECC system and the sprinkler system have been used. Boundary conditions such as mass flow and enthalpies at the breach are given by a RELAP4/MOD6 computation. Hydrogen explosions in the containment are not considered. It is found that in case of normal functioning of the low-pressure ECC system the maximal pressure is 3,26±0,44 bar. In the case of malfunctioning of the low-pressure ECC system, the predicted maximal pressure is 4±0,44 bar, when: a) only 50% of the heat transfer surface of the heat exchanger is effectively used due to pollution; b) the main pipeline of the sprinkler is broken; c) the pipeline to the heat exchanger is partially broken so that the mass flow through the exchanger is only 50% of the nominal; and d) ECC low-pressure ECC system attains its maximal efficiency within 3 min, the predicted maximal pressure is 4±0,44 bar

  6. Nuclear safety analysis for transport cask TK-6 (for WWER-440) and cover for fresh assemblies (for WWER-1000) in implementation of new fuel types at Ukrainian NPP

    International Nuclear Information System (INIS)

    Bilodid, Y.; Kovbasenko, Iu; Dudka, Olena

    2006-01-01

    According to the fresh fuel management procedure, fuel assemblies - after nuclear fuel delivery to the NPP fresh fuel unit - are vertically loaded into a cover intended for the delivery of fuel assemblies into the containment of the NPP reactor compartment. The cover is placed into an universal jack in the cooling and refueling pond, and then the fresh fuel assemblies are loaded into the reactor core. Based on the nuclear safety analysis carried out by the Russian Research Center 'Kurchatov Institute' for contemporary WWER-1000 fuel, it has become necessary to limit the number of fuel assemblies loaded into a cover below its designed capacity (12 FA instead of 18 FA as originally designed). Such a decision leads to worse economic performances in fuel transportation. The paper considers potential ways to overcome this restriction. Transport container TK-6 for spent fuel assemblies was designed quite a long time ago and, as shown in this paper, the requirement on the maximally permissible neutron multiplication factor of the loaded container for individual states to be analyzed in compliance with Ukrainian regulations is not met. First of all, this concerns the container criticality analysis in optimal neutron slow-down (container filling with water-air mixture with optimal density). The paper shows potential ways for TK-6 burnup-credit loading with the maximum number of fuel assemblies and partial container loading (Authors)

  7. Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Noori-Kalkhoran, Omid; Ahangari, R. [Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of). Reactor Research school; Shirani, A.S. [Shahid Beheshti Univ., Tehran (Iran, Islamic Republic of). Faculty of Engineering

    2017-03-15

    In this study a code based method has been developed for calculation of integral and differential control rod worth in terms of burn-up for a WWER-1000 reactor. Parallel processing of WIMSD-5B, PARCS V2.7 and COBRA-EN has been used for this purpose. WIMSD-5B has been used for cell calculation and handling burn-up of core at different days. PARCS V2.7?has been used for neutronic calculation of core and critical boron concentration search. Thermal-hydraulic calculation has been performed by COBRA-EN. A Parallel processing algorithm has been developed by MATLAB to couple and transfer suitable data between these codes in each step. Steady-State Power Picking Factors (PPFs) of the core and Control rod worth have been calculated from Beginning Of Cycle (BOC) to 289.7 Effective full Power Days (EFPDs) in some steps. Results have been compared with Bushehr Nuclear Power Plant (BNPP) Final Safety Analysis Report (FSAR) results. The results show great similarity and confirm the ability of developed coupling in calculation of control rod worth in terms of burn-up.

  8. Simulation of protected and unprotected loss of flow transients in a WWER-1000 reactor based on the Drift-Flux model

    Energy Technology Data Exchange (ETDEWEB)

    Baghban, Ghonche [Atomic Energy Organization of Iran, Tehran (Iran, Islamic Republic of). Nuclear Science and Technology Research Inst.; Shayesteh, Mohsen [Imam Hussein Univ., Tehran (Iran, Islamic Republic of). Dept. of Physics; Bahonar, Majid [Islamic Azad Univ., Tehran (Iran, Islamic Republic of). Dept. of Nuclear Engineering

    2017-03-15

    In view of the importance of studying coolant transient behavior in a nuclear reactor, this work is devoted to the thermal-hydraulic analysis of protected and unprotected loss of flow transients in a WWER-1000 reactor. A series of corresponding mathematical and physical models based on the four-equation Drift-Flux model has been applied. Based on a multi-channel approach, the core has been divided into different regions. Each region has different characteristics as represented in a single fuel pin with its associated coolant channel. Appropriate initial and boundary conditions have been considered and two situations of tripping four and two primary pumps in a protected core in addition to situation of tripping all four pumps in an unprotected core have been analyzed. For each transient, a full range of thermal-hydraulic parameters has been obtained. For verification of the proposed model, the results have been compared with those of the RELAP5/MOD3 and Bushehr nuclear power plant Final Safety Analysis Report (FSAR). A good agreement between results has been attained for the aforementioned transients.

  9. Start up physics tests of units 5 and 6 (WWER 1000) at Kozloduy NPP by comparison with the calculated neutron physics characteristics

    International Nuclear Information System (INIS)

    Antov, A.; Stoyanova, I.

    2008-01-01

    In conjunction with each refuelling shutdown of the reactor core, nuclear design calculations are performed to ensure that the reactor physics characteristics of the new core will be consistent with the safety limits. Prior to return to normal operation, a physics test program is required to determine if the operating characteristics of the core are consistent with the design predictions and to ensure that the core can be operated as designed. Successful completion of the physics test program is demonstrated when the test results agree with the predicted results within predetermined test criteria. Successful completion of the physics test program and successful completion of other tests, which are performed after each refuelling provides assurance that the plant can be operated as designed. The calculated neutron-physics characteristics values of Kozloduy NPP Unit 5 and Unit 6 (WWER 1000) obtained by the computer code package KASKAD are compared with the obtained results during the start up physics tests. The core fuel loading consists of 163 fuel assemblies (FAs). The calculated values are given according to actual experimental conditions of the reactor core during start up physics tests. The report includes comparisons between calculation results by code package KASKAD (BIPR7A) and experimental data values of main neutron-physics characteristics during start up physics tests in selected recent cycles of Kozloduy NPP Unit 5 and Unit 6. (authors)

  10. Start up physics tests of Units 5 and 6 (WWER-1000) at Kozloduy NPP by comparison with the calculated neutron physics characteristics

    International Nuclear Information System (INIS)

    Stoyanova, I.; Antov, A.

    2007-01-01

    In conjunction with each refuelling shutdown of the reactor core, nuclear design calculations are performed to ensure that the reactor physics characteristics of the new core will be consistent with the safety limits. Prior to return to normal operation, a physics test program is required to determine if the operating characteristics of the core are consistent with the design predictions and to ensure that the core can be operated as designed. Successful completion of the physics test program is demonstrated when the test results agree with the predicted results within predetermined test criteria. Successful completion of the physics test program and successful completion of other tests which are performed after each refuelling provides assurance that the plant can be operated as designed. The calculated neutron-physics characteristics values of Kozloduy NPP Unit 5 and Unit 6 (WWER 1000) obtained by the computer code package KASKAD are compared with the obtained results during the start up physics tests. The core fuel loading consists of 163 fuel assemblies. The calculated values are given according to actual experimental conditions of the reactor core during start up physics tests. The report includes comparisons between calculation results by code package KASKAD (BIPR7A) and experimental data values of main neutron-physics characteristics during start up physics tests in selected recent cycles of Kozloduy NPP Unit 5 and Unit 6 (Authors)

  11. Principles of building and assembly technology of containment from steel structural blocks for WWER 1000 nuclear power plant

    International Nuclear Information System (INIS)

    Eichstedt, J.; Friedrich, F.

    1983-01-01

    This technology is being developed in cooperation between the USSR and the GDR. The cylindrical part of the containment consists of prefabricated double-sided steel blocks with inner reinforcement. The steel plates in a thickness of 20 mm provide casing and secure tightness. Blocks with one steel wall are used for the construction of the cupola. The outer slabs are assembled subsequently. The methods of assembly, concreting and quality assurance are described. (Ha)

  12. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  13. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  14. Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Noori-Kalkhoran, Omid, E-mail: o_noori@yahoo.com [Reactor Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of); Yarizadeh-Beneh, Mehdi [Faculty of Engineering, Shahid Beheshti University, Tehran (Iran, Islamic Republic of); Ahangari, Rohollah [Reactor Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran (Iran, Islamic Republic of)

    2016-08-15

    Highlights: • Calculation of control rod worth in term of burn-up. • Calculation of differential and integral control rod worth. • Developing an external couple. • Modification of thermal-hydraulic profiles in calculations. - Abstract: One of the main problems relating to operation of a nuclear reactor is its safety and controlling system. The most widely used control systems for thermal reactors are neutron absorbent rods. In this study a code based method has been developed for calculation of integral and differential control rod worth in terms of burn-up for a WWER-1000 nuclear reactor. External coupling of WIMSD-5B, PARCS V2.7 and COBRA-EN has been used for this purpose. WIMSD-5B has been used for cell calculation and handling burn-up of the core in various days. PARCS V2.7 has been used for neutronic calculation of core and critical boron concentration search. Thermal-hydraulic calculation has been performed by COBRA-EN. An external coupling algorithm has been developed by MATLAB to couple and transfer suitable data between these codes in each step. Steady-State Power Picking Factors (PPFs) of the core and control rod worth for different control rod groups have been calculated from Beginning Of Cycle (BOC) to 289.7 Effective Full Power Days (EFPDs) in some steps. Results have been compared with the results of Bushehr Nuclear Power Plant (BNPP) Final Safety Analysis Report (FSAR). The results show a good agreement and confirm the ability of developed coupling in calculation of control rod worth in terms of burn-up.

  15. Blind pre-analysis of the main building complex WWER-1000 Kozloduy. Comparison of analytical and experimental results obtained by explosive testing (task 8a of workplan 96/97)

    International Nuclear Information System (INIS)

    Krutzik, N.J.

    1999-01-01

    In accordance with the 96/97 workplan of the Research Programme on 'Benchmark Studies for Seismic Analysis and Testing of WWER-Type Nuclear Power Plants', blind pre analyses were prepared for the main building complex of the WWER-1000 based on given excitations derived from explosive tests. The investigations were performed by several institutions based on various mathematical models and procedures for consideration of soil-structure interaction effects, but on the same explosive test input data recently obtained. The methods of calculation and software tools used will also be different. The aim of this investigation is to validate different idealization concepts (mathematical models for the idealization of the structures and the soil) as well as investigation procedures (time domain and frequency domain analysis) and finally the software tools by comparing structural response results (time histories and response spectra). This report contains the results of the blind pre analysis performed by Siemens using an equivalent beam model of the main building of the WWER 1000. The calculations were performed by means of a frequency domain calculation

  16. Comparative calculations and operation-to-PIE data juxtaposition of the Zaporozhye NPP, WWER-1000 FA-E0325 fuel rods after 4 years of operation up to ∼49 MWd/kgU burnup

    International Nuclear Information System (INIS)

    Passage, G.; Stefanova, S.; Scheglov, A.; Proselkov, V.

    2006-01-01

    Operational and PIE data for the Zaporozhe NPP, FA-E0325, WWER-1000 fuel rods were provided in the OECD NEA IFPE Database and were used to perform comparative calculations among several fuel performance codes. The fuel rods had been irradiated for 4 years of operation up to ∼49 MWd/kg U burnup. The fuel rod operation histories are developed for the PINw99, TRANSURANUS (V1M1J03) and TOPRA-2 codes. The initial state fuel rod parameters are analysed and calculations are carried out. The PIE data enable the comparison of experimental measurement with code-calculated values for cladding elongation (49 rods), FGR and gas pressure (35 rods). Cladding diameter creep-down and gap closure results are juxtaposed as well. The capability of the applied codes correctly to predict the WWER fuel rod performance is shown. The WWER-1000 fuel rod data include initial geometrical and design parameters of the fuel rods, as well as description of the operation regime, NPP unit loading history and PIE results at normal conditions. The data are sufficient for modelling all 312 fuel rod and for comparison of calculations with experimental results for a limited number of fuel rods. The comparison between the calculated and measured results discussed in this paper shows that the codes PINw99, TRANSURANUS and TOPRA-2, are capable of adequate predicting the thermophysical and the mechanical performance of the WWER-1000 fuel rods. The PINw99 code predicts conservative BOL FGR values and conservative gas pressure values in the region of burnups higher than 30 MWd/kg U, which can be explained by the underprediction of the cladding gas inner volume and cladding elongation. The improved version PIN2K (not applied in the present study) predicts much better FGR and gas pressure, though, it is still under development in the high burnup FGR modelling part. In the TRANSURANUS code, there are also areas, where refinements are clearly indicated. They are subjects of the ongoing research projects and

  17. Improving the refueling cycle of a WWER-1000 using cuckoo search method and thermal-neutronic coupling of PARCS v2.7, COBRA-EN and WIMSD-5B codes

    Energy Technology Data Exchange (ETDEWEB)

    Yarizadeh-Beneh, M.; Mazaheri-Beni, H.; Poursalehi, N., E-mail: n_poursalehi@sbu.ac.ir

    2016-12-15

    Highlights: • The cuckoo search algorithm is applied to the loading pattern optimization of a nuclear reactor core. • Calculations during the cycle show a good agreement between results and reference for the original LP. • Results indicate the efficient performance of cuckoo search approach coupled with thermal-neutronic solvers. • Neutronic parameters of proposed core pattern are improved relative to original core pattern. - Abstract: The fuel loading pattern optimization is an important process in the refueling design of a nuclear reactor core. Also the analysis of reactor core performance during the operation cycle can be a significant step in the core loading pattern optimization (LPO). In this work, for the first time, a new method i.e. cuckoo search algorithm (CS) has been applied to the fuel loading pattern design of Bushehr WWER-1000 core. In this regard, two objectives have been chosen for finding the best configuration including the improvement of operation cycle length associated with flattening the radial power distribution of fuel assemblies. The core pattern optimization has been performed by coupling the CS algorithm to thermal-neutronic codes including PARCS v2.7, COBRA-EN and WIMSD-5B for earning desired parameters along the operation cycle. The calculations have been done for the beginning of cycle (BOC) to the end of cycle (EOC) states. According to numerical results, the longer operation cycle for the semi-optimized loading pattern has been achieved along with less power peaking factor (PPF) in comparison to the original core pattern of Bushehr WWER-1000. Gained results confirm the efficient and suitable performance of the developed program and also the introduced CS method in the LPO of a nuclear WWER type.

  18. Report of the review of the safety improvement programme for South Ukraine NPP units 1 and 2 and to identify the safety issues of ''small series'' WWER-1000 NPPs. South Ukraine Yuzhnoukrainsk, Nikolaev Region Ukraine, 8 to 19 July 1996. Draft

    International Nuclear Information System (INIS)

    Bastin, S.; Hoehn, J.; Lin, C.; Taylor, R.; Benitez, F.; Dale, H.; Mueller, B.; Rieg, C.Y.

    1996-10-01

    According to the Ukrainian request the purpose of the IAEA experts' mission was to review the safety improvement programme for South Ukraine NPP Units 1 and 2 in order to advise on the completeness and adequacy of safety improvements implemented and/or proposed. Another purpose of the mission was to identify major design and operational deficiencies as a basis to compile a consolidated list of generic safety issues for the units of the 'small series'' of WWER-1000 reactors (''Issue Book for ''small series'' WWER-1000 NPPs). Conclusions and recommendations from the IAEA mission are based on the combined expertise of the international group of experts who composed the team. They are intended to assist national authorities and plant operators who have the sole responsibilities for the regulation and safe operation. tabs

  19. Analysis of WWER 1000 collector cracking mechanisms

    Energy Technology Data Exchange (ETDEWEB)

    Matocha, K.; Wozniak, J. [Vitkovice J.S.C., Ostrava (Switzerland)

    1997-12-31

    The presentation reviews the large experimental program, started in 1993 in Vitkovice, where the main aim was: (1) a detailed study of strain and thermal ageing, dissolved oxygen content and temperature on subcritical crack growth in 10NiMo8.5 (10GN2MFA) steel, (2) a detailed study of the effect of high temperature water and tube expansion technology on fracture behaviour of ligaments between holes for heat exchange tubes, and (3) a detailed study of the effect of drilling, tube expansion technology and heat treatment on residual stresses on the surface of holes for heat exchange tubes. The aim of all these investigations was to find a dominant damage mechanism responsible for collector cracking to be able to judge the efficiency of implemented modifications and suggested countermeasures and to answer a very important question whether proper operation conditions (mainly water chemistry) make the operation of steam generators made in Vitcovice safe throughout the planned lifetime. 10 refs.

  20. Analysis of WWER 1000 collector cracking mechanisms

    Energy Technology Data Exchange (ETDEWEB)

    Matocha, K; Wozniak, J [Vitkovice J.S.C., Ostrava (Switzerland)

    1998-12-31

    The presentation reviews the large experimental program, started in 1993 in Vitkovice, where the main aim was: (1) a detailed study of strain and thermal ageing, dissolved oxygen content and temperature on subcritical crack growth in 10NiMo8.5 (10GN2MFA) steel, (2) a detailed study of the effect of high temperature water and tube expansion technology on fracture behaviour of ligaments between holes for heat exchange tubes, and (3) a detailed study of the effect of drilling, tube expansion technology and heat treatment on residual stresses on the surface of holes for heat exchange tubes. The aim of all these investigations was to find a dominant damage mechanism responsible for collector cracking to be able to judge the efficiency of implemented modifications and suggested countermeasures and to answer a very important question whether proper operation conditions (mainly water chemistry) make the operation of steam generators made in Vitcovice safe throughout the planned lifetime. 10 refs.

  1. Steam turbine of WWER-1000 unit

    International Nuclear Information System (INIS)

    Drahy, J.

    1986-01-01

    The manufacture was started by Skoda of a saturated steam, 1,000 MW, 3,000 rpm turbine designed for the Temelin nuclear power plant. The turbine provides steam for heating water for district heating, this either with an output of 893 MW for a three-stage water heating at 150/60 degC, or of 570 MW for a two-stage water heating at 120/60 degC. The turbine features one high-pressure and three identical low-pressure stages. The pressure gradient between the high-pressure and the low-pressure parts was optimized with respect to the thermal efficiency of the cycle and to the thermodynamic efficiency of the low-pressure part. A value of 0.79 MPa was selected corresponding to the maximum through-flow of steam entering the turbine. This makes 5,495 t/h, the admission steam parameters are 273.3 degC and 5.8 MPa. The feed water temperature is 220.9 degC. 300 cold starts, 1,000 starts after shutdowns for 55 to 88 hours and 600 starts after shutdown for 8 hours are envisaged for the entire turbine service life. (Z.M.). 5 figs., 1 tab., 6 refs

  2. ASTEC and MELCOR comparison for a VVER-1000 60 mm small break LOCA

    International Nuclear Information System (INIS)

    Georgieva, J.; Stefanova, A.; Groudev, P.; Tusheva, P.; Mladenov, I.; Dimov, D.; Passalacqua, R.

    2005-01-01

    In this paper a comparison between severe accident calculations performed for a WWER 1000 with the ASTEC1.1v0 and MELCOR 1.8.5 computer codes for a small break LOCA (ID 60 mm) without intervention of hydro accumulators is presented. This investigation has been performed in the framework of the SARNET project under the EURATOM 6th framework program. Once the accident sequence scenario is specified, both codes (MELCORE and ASTEC) are able to determine the core and containment damaged states, to estimate the release of radionuclides from the fuel as well as from the primary circuit and containment. Theses results are used to estimate the maximum period of the time during which the personnel could still take particular decisions in order to mitigate such an accident. The aim of the performed analysis is to estimate the discrepancy between ASTEC and MELCORE 1.8.5 calculations. Such discrepancies will be studied, if the case, proposal for ASTEC improvements will be made. Also the ASTEC capability to simulate specific reactor accident scenarios and/or particular safety systems will be tested. The final target is to propose severe accident management procedure for WWER 1000 reactors. In conclusions, the analysis for a small break LOCA (ID 60 mm without hydroelectricities) has shown some discrepancies between ASTEC and MELCORE especially during the degradation of the core. Further analyses are planed in which the MELCORE temperature 'set point' for core degradation (2520 K) will be progressively increased to approach the ASTEC one (which has been estimated to be about 3200 K). The comparison of the new results will allow a better evaluation of the in-vessel models implemented in ASTEC

  3. Strelovodna zaščita za stanovanjski objekt

    OpenAIRE

    Kunšek, Rok

    2014-01-01

    V diplomskem delu je opisana zaščita stanovanjskega objekta pred udarom strele. Obravnavano je projektiranje, načrtovanje, izračun rizika in meritve. Podani so predlogi izvedbe strelovodne zaščite za stanovanjski objekt, ki so izdelani in izračunani z upoštevanjem najnovejših standardov s področja zaščite pred delovanjem strele. Za dodatno pomoč pri izdelavi lovilnega sistema je uporabljeno programsko orodje Ščit, ki je namenjeno projektiranju in dimenzioniranju strelovodne zaščite....

  4. Kauli za utendwa/utendewa katika tamthilia za Machozi ya ...

    African Journals Online (AJOL)

    Kazi hii ni ya utafiti wa kiisimu mitindo unaolenga kulinganisha na kulinganua kazi mbili za tamthiliya za Kiswahili ambazo ni Heshima Yangu (Muhando, 1974) na Machozi ya Mwanamke (Ngozi, 1977). Kwanza, makala inachunguza matumizi ya kauli za utendwa/utendewa katika tamthiliya hizi ili kujua kama ni ya hiari au ...

  5. ODLOČITVENI MODEL ZA OCENJEVANJE KANDIDATOV ZA ŠOLO ZA ČASTNIKE

    OpenAIRE

    Ogrinc, Matjaž

    2011-01-01

    Diplomsko delo se loteva postopka izbora najprimernejših kandidatk in kandidatov za šolanje na Šoli za častnike Slovenske vojske. Cilj naloge je razvrstitev in izbor najprimernejših kandidatov, ki sodelujejo na selekciji in bodo napoteni na šolanje v Šolo za častnike. Problem smo rešili z izgradnjo modela za večparametrsko odločanje. Odločitveni model je predstavljen z izbranimi kriteriji, ki so najbolj pomembni za končno oceno in razvrstitev kandidatov. Pri modeliranju večparametrskega model...

  6. Za balony do knihovny

    Czech Academy of Sciences Publication Activity Database

    Jelínková, Andrea

    2017-01-01

    Roč. 69, č. 5 (2017), s. 192-192 ISSN 0011-2321 Keywords : ballooning * historical book collections * scientific literature Subject RIV: AF - Documentation, Librarianship, Information Studies http://ctenar.svkkl.cz/clanky/2017-roc-69/5-2017/poklady-knihoven-za-balony-do-knihovny-170-2496.htm

  7. Bodimo soodgovorni za razvoj

    Directory of Open Access Journals (Sweden)

    Dušana Findeisen

    1997-12-01

    Full Text Available Živimo v času socialnih, ekonomskih in političnih sprememb. Prebivalstvo se stara, okolje je onesnaženo, ponekod ga je prizadela prehitra urbanizacija, želimo si boljšega življenja. Mnogi v tem vidijo izziv za delovanje in učenje. Pri prebivalcih in posameznikih se pojavljajo tudi mnoge nove potrebe, na katere se ne moreta odzvati ne trg ne država s svojimi institucijami. Tudi vloga podjetij, ki so nekoč skrbela za izobraževanje delavcev in njihovo socialno varnost, se spreminja. Če je izobraževanje strateška naložba podjetja, se potem lahko za gotovo sklepamo, da podjetja svoje prihodnosti ne želijo ustvarjati z manj izobraženimi ljudmi, takšnimi, ki so potrebni temeljnega izobraževanja za življenje in delo. Kako lahko pomagamo tem manj izobraženim, da se bodo znašli v novih razmerah?

  8. Optimized core loading sequence for Ukraine WWER-1000 reactors

    International Nuclear Information System (INIS)

    Dye, M.; Shah, H.

    2015-01-01

    Fuel Assemblies (WFAs) experienced mechanical damage of the grids during loading at both South Ukraine 2 (SU2) and South Ukraine 3 (SU3). The grids were damaged due to high lateral loads exceeding their strength limit. The high lateral loads were caused by a combination of distortion and stiffness of the mixed core fuel assemblies and significant fuel assembly-to-fuel assembly interaction combined with the core loading sequence being used. To prevent damage of the WFA grids during core loading, Westinghouse has developed a loading sequence technique and loading aides (smooth sided dummies and top nozzle loading guides) designed to minimize fuel assembly-to-fuel assembly interaction while maximizing the potential for successful loading (i.e., no fuel assembly damage and minimized loading time). The loading sequence technique accounts for cycle-specific core loading patterns and is based on previous Westinghouse WWER core loading experience and fundamental principles. The loading aids are developed to “open-up” the target core location or to provide guidance into a target core location. The Westinghouse optimized core loading sequence and smooth sided dummies were utilized during the successful loading of SU3 Cycle 25 mixed core in March 2015, with no instances of fuel assembly damage and yet still provided considerable time savings relative to the 2012 and 2013 SU3 reload campaigns. (authors)

  9. Modernization incore monitoring system of WWER-1000 reactors (V-320)

    International Nuclear Information System (INIS)

    Mitin, Valentin; Semchenkov, Yurij; Kalinushkin, Andrey

    2008-01-01

    Modern ICIS system for VVER-1000, including a number of sensors, cable runs, corresponding measuring equipment and computer engineering, software, accumulated 30 year experience of interaction researches on VVER reactors and is capable to ensure carrying out of control, protection, informational, diagnostic functions and thus to promote real increase of quality, reliability and safety in nuclear fuel and NPP power units operation

  10. WWER-1000/320 steam generator collector rupture. Radiological consequences

    Energy Technology Data Exchange (ETDEWEB)

    Ivanova, A; Sartmadzhiev, A; Balabanov, E [Energoproekt, Sofia (Bulgaria)

    1996-12-31

    A model describing a hypothetical accident with direct release of primary coolant to the atmosphere is proposed. Cover lifting of the primary collector due to a rupture of the fixing bolts leads to a coolant release. The initial and boundary conditions of the accident scenario have been selected to provide for the most unfavorable conditions. The total release of primary coolant during the first 15 min of transient are estimated to 50.8 tons, of these 48.5 t with the initial activity in the primary coolant circuit. Without evacuation or sheltering, after 7 days of exposure, the expected dose at the boundary of the restricted zone is 0.0182 Sv for the whole body and 0.184 Sv for the thyroid gland. The effective equivalent dose on the site would be 0.0521 Sv. As a result of the analysis it is concluded that the steam generator collector rupture is not jeopardizing the core heat removal even with a minimum configuration of ECCS as the cooling is accomplished through the steam generators. The radiological consequences of the accident would be relatively small if an emergency procedure is applied at the 15-th minute of the transient. 1 ref.

  11. Dynamic response of Belene WWER-1000 to seismic loading conditions

    International Nuclear Information System (INIS)

    Krutzik, N.J.; Petrovski, D.; Sachanski, S.

    1993-01-01

    Within the framework of investigating of the capacity of the WWER-100 at the Belene site, an analysis was performed using revised seismic input data as well as two alternative foundation concepts (natural soil and soil exchange). The starting point for the analysis was the development of a suitable model of the coupled structures (base building, external building, containment, internal structure) and soil taking into account the real properties of the originally layered as well as the exchanged soil. The soil-structure effects were considered according to the analytical method employed, either through soil impedance (substructure method) or explicitly by a complex (direct method). On the basis of the results obtained by the two methods (substructure and direct method) the seismic safety of the complex structures for different foundation concepts was evaluated. By comparing the calculated structural response with the design spectra originally used for the design of components and systems the available safety margin was estimated

  12. New methods of building WWER 1000 nuclear power plants

    International Nuclear Information System (INIS)

    Tadzher, O.

    1983-01-01

    The shortening of construction time needed for building the 5th unit of the Kozloduj nuclear power plant in Bulgaria is discussed. In the 2nd to 4th stages of construction the builders are expected to use the large CC-4000 mobile crane with high lifting power (Demag, FRG) for construction and assembly work. This work may be done by ''open'' assembly, i.e., the assembly of equipment in an unfinished building. By using the said crane it is possible to increase the weight of the individual units and thereby to reduce their number. The advantages of ''open'' assembly is that there is no need for a opecial transport corridor for the lifting and assembly of heavy handling units. A preliminary evaluation of the new technology has shown that assembly of the reactor hall equipment can be started 6 to 8 months ahead of schedule. (E.S.)

  13. WWER-1000 simulator instructor service in NV TC

    International Nuclear Information System (INIS)

    Pogrebitsky, S.L.

    1997-01-01

    In July 1996 a full-scope simulator developed by the joint efforts of ATOMTECHENERGO, VNII AES (Russia) and Mitsubishi Heavy Industries (Japan) was put into service Novovoronezh Training Centre (NV TC). this paper describes the Instructor Station equipment and its capabilities for training process monitoring and simulation. (author)

  14. Electrode for welding steel for WWER-1000 reactor pressure vessel

    International Nuclear Information System (INIS)

    Lakatos, L.

    Of two types of electrodes, ie., with an alloyed core and with an unalloyed core, an electrode was chosen consisting of a basic coat and an unalloyed core. Fluctuations are shown of shear strength, tensile strenght and contraction with the welding mode and annealing temperature. It was found that pre-heating to 250 and 350 degC, respectively, was most suitable for welding a pressure vessel manufactured from material designated SKODA A3/II. Annealing aimed at removing stress was chosen at 650 to 700 degC. (H.S.)

  15. Materijali za izradu mikroreaktora

    Directory of Open Access Journals (Sweden)

    Zana Hajdari Gretić

    2017-11-01

    Full Text Available Mikroreaktori su reaktorski sustavi izvedeni u mikroskopskom mjerilu, a zbog svoje velike međufazne površine imaju prednosti u odnosu na klasične – makroreaktorske sustave. Odabir materijala za izradu mikroreaktora ovisi o vrsti reakcije koja se provodi u sustavu, kompatibilnosti otapala i materijala, mehaničkim zahtjevima te o cijeni i dostupnosti na tržištu. Materijali koji se najčešće upotrebljavaju za izradu su različite vrste stakla, keramike, metali te polimerni materijali. Ovisno o materijalu odabiru se postupci izrade, a najčešći postupci su jetkanje, litografija, pjeskarenje, strojna obrada, injekcijsko prešanje te aditivni postupci izrade. Cilj ovog rada je predstaviti najčešće materijale i postupke izrade mikroreaktora.

  16. STROJEVI ZA PRIJENOS I DIZANJE

    OpenAIRE

    Mesić, Slaven

    2016-01-01

    U ovom završnom radu obrađeni su strojevi za prijenos i dizanje materijala. Strojevi za prijenos i dizanje su posebni strojevi namijenjeni unutarnjem (gradilišnom) transportu. Prikazane su opće podjele i karakteristike toranjskih dizalica, mobilnih dizalica, kabel kranova, „Derrick kranova“, mosnih kranova i građevinskih dizala. Uporaba strojeva za prijenos i dizanje je uvjetovana masom tereta koji je potrebno prenijeti te specifičnim uvjetima na gradilištu. Odabir potrebnog st...

  17. Nobelova nagrada za kemiju 2005

    OpenAIRE

    Frkanec, Leo; Portada, Tomislav

    2006-01-01

    Ovogodišnju Nobelovu nagradu za kemiju podijelila su trojica dobitnika: Francuz Yves Chauvin, Amerikanci Robert H. Grubbs i Richard R. Schrock. Prema obrazloženju Kraljevske švedske akademije znanosti, Nobelova nagrada dodijeljena im je za razvoj postupka metateze u organskoj sintezi. Osim velikog odjeka u akademskoj zajednici, laureati su svojim znanstvenim postignućima omogućili značajan napredak u kemijskoj industriji i proizvodnji kemikalija otvarajući pregršt novih mogućnosti za pripravu...

  18. Nobelova nagrada za kemiju 2006.

    OpenAIRE

    Frkanec, L.; Portada, T.

    2006-01-01

    Ovogodišnju Nobelovu nagradu za kemiju podijelila su trojica dobitnika: Francuz Yves Chauvin, Amerikanci Robert H. Grubbs i Richard R. Schrock. Prema obrazloÞenju Kraljevske švedske akademije znanosti, Nobelova nagrada dodijeljena im je za razvoj postupka metateze u organskoj sintezi. Osim velikog odjeka u akademskoj zajednici, laureati su svojim znanstvenim postignuæima omoguæili i znaèajan napredak u kemijskoj industriji i proizvodnji kemikalija otvarajuæi pregršt novih moguænos...

  19. MOBILNA APLIKACIJA ZA ORGANIZACIJO DOGODKOV

    OpenAIRE

    Vantur, Blaž

    2015-01-01

    Cilj diplomske naloge je preučiti mobilni operacijski sistem Android in njegovo delovanje, izdelava preproste mobilne aplikacije za ustvarjanje dogodkov ter pošiljanje vabila preko SMS sporočila. V njej bomo opisali zgradbo Android sistema in funkcionalnosti, ki smo jih uporabili pri razvoju naše aplikacije.

  20. Smernice za izvedbo komunikacijskih povezav v sistemih za preskrbo s pitno vodo

    OpenAIRE

    PAVŠIČ, EDVARD

    2016-01-01

    Voda je osnovna človekova dobrina, ki spremlja človeštvo že od samega začetka. Zagotavljanje pitne vode je bilo nekoč velik izziv, prav nič drugače pa ni danes, kljub temu, da imamo visoko razvito tehnologijo za zajem, obdelavo in transport vode. V diplomskem delu primerjam stanje v sistemih za preskrbo s pitno vodo nekoč in danes ter nakažem možnosti za nadaljnji razvoj. Razdelam različne možnosti za prenos podatkov med soodvisnimi objekti vodovodnega sistema in ocenim njihove prednosti in s...

  1. PRIPRAVA STROKOVNIH PODLAG ZA UVEDBO SISTEMA ZA UPRAVLJANJE INFORMACIJSKE VARNOSTI

    OpenAIRE

    Tršelič, Tugomir

    2014-01-01

    V diplomskem delu smo raziskali področje informacijske varnosti. Namen raziskave je bil priprava strokovnih podlag, na osnovi katerih smo pridobili podporo vodstva za vpeljavo sistema upravljanja z informacijsko varnostjo v podjetju. V raziskavo smo vključili ključne koncepte informacijske varnosti, pregled novih tehnologij, opravljene lokalne in globalne raziskave s področja varnostnih incidentov in pregled pomembne področne zakonodaje. Ugotovitve smo nadgradili s pregledom ključnih področni...

  2. Parametri za procena na kvalitetot na polietilenska i na polipropilenska ambalaza i na gumeni zatvoraci nameneti za farmacevtski preparati

    Directory of Open Access Journals (Sweden)

    Liljana Ugrinova

    2002-03-01

    Full Text Available Napraven e pregled na parametrite za procena na kvalitetot na polietilenska i na polipropilenska ambalaza i na gumeni zatvoraci nameneti za farmacevtski preparati. Za procena na kvalitetot na ispituvaniot materijal bea izvrseni fizicki, hemiski i bioloski ispituvanja spored postapkite dadeni vo Ph. Eur., DIN i spored DIN ISO standardite. Baranjata za kvalitet na ovoj vid ambalaza propisani spored Ph. Eur., DIN i DIN ISO standardite se razlikuvaat vo odnos na predvidenite parametri za fizicki, za hemiski i za bioloski ispituvanja. Isto taka, propisani se i razlicni granici na dozvoleno otstapuvanje na oddelni parametri.

  3. Prenova razsvetljave na Fakulteti za elektrotehniko

    OpenAIRE

    ŠTAJDOHAR, JAN

    2015-01-01

    Pri energetskem pregledu stavbe Fakultete za elektrotehniko v Ljubljani je bilo ugotovljeno, da je razsvetljava prostorov na fakulteti v veliko primerih stara, neprimerna in energetsko potratna. V diplomski nalogi smo se posvetili energetski analizi prenove razsvetljave predavalnice P7 in kabineta AZ101. Pri načrtovanju in izbiri svetil smo upoštevali vse tehnične in energetske smernice za učinkovito razsvetljavo prostorov za izobraževanje. V uvodu smo opisali fizikalne osnove svetlobe, k...

  4. Stroj za mešanje komposta

    OpenAIRE

    Žvikart, Klemen

    2015-01-01

    V podjetju BIJOL d.o.o iz Vuzenice je že dolgo prisotna ideja o lastnem proizvodu, saj si podjetje želi svojo dejavnost razširiti na več panog. Razviti stroj za mešanje komposta je bila ena izmed njih. Na tej osnovi in že vnaprej pripravljeni zasnovi, kako naj bi izgledal stroj za mešanje komposta, sem prevzel projekt in na osnovi lastne ideje skonstruiral stroj za mešanje. Namen te naloge je skonstruirati stroj ter pripraviti dokumentacijo. Poleg same izdelave stroja so cilji naloge tudi spo...

  5. Ogrodja JavaScript in orodja za razvoj za odjemalca: primerjava in ovrednotenje z empiričnim modelom

    OpenAIRE

    Podbojec, Damir

    2017-01-01

    V magistrskem delu je predstavljen razvoj JavaScripta skozi čas, moderna ogrodja JavaScript, ki se uporabljajo za razvoj dinamičnih spletnih aplikacij, in orodja za razvoj za odjemalca, ki pospešujejo in pripomorejo k celotnemu razvojniškemu procesu. Analizirana je arhitektura današnjih dinamičnih spletnih aplikacij ter osnovne funkcionalnosti ogrodij JavaScript in orodij za razvoj za odjemalca. V namen lažje diferenciacije med ogrodji in lažje izbire ogrodij za razvoj dinamičnih spletnih apl...

  6. Aplikacija za avtomatizirano prepoznavanje listov dreves in grmov kritosemenk za operacijski sistem Android

    OpenAIRE

    Puhmeister, Sandro

    2016-01-01

    V tem diplomskem delu smo implementirali aplikacijo za avtomatizirano prepoznavanje listov dreves in grmov kritosemenk za operacijski sistem Android, pri čemer smo postopek prepoznavanja vrste razdelili na štiri ključne faze: zajem slik, obdelavo slik, luščenje značilnic in določitev vrste. Pri zajetju slik smo uporabili privzeto aplikacijo operacijskega sistema Android, kjer uporabnik zajame dve fotografiji (fotografira spodnjo in vrhnjo površino lista) za obdelavo slik. Pri obdelavi slik sm...

  7. PRIMERJAVA OGRODIJ ZA RAZVOJ MOBILNIH IGER

    OpenAIRE

    Damiš, Aleksander

    2012-01-01

    V dobi vsestranske in vsakdanje uporabe pametnih mobilnih telefonov se posledično veča priljubljenost mobilnih iger. Zaradi zmogljivosti najnovejših mobilnih telefonov in zahtev trga po boljši odzivnosti, izvirni zgodbi in dobro zasnovani grafiki je razvoj sodobnih mobilnih iger vse prej kot lahek. V tem diplomskem delu je predstavljen postopek od načrtovanja do objave preproste mobilne igre za platformo iOS v treh različnih ogrodjih, ki omogočajo razvoj mobilnih iger tako začetnim navdušence...

  8. Odgovornost za svijet u misli Romana Guardinija

    OpenAIRE

    Domazet, Anđelko

    2014-01-01

    Teološki opus Romana Guardinija snažno je svjedočanstvo nastojanja da se katolička teologija izvede iz tjesnoće stoljećima dugog nepovjerenja prema svijetu i otvori za istinsko evanđeosko zalaganje u svijetu. U ovom razmišljanju sažeto iznosimo na vidjelo autorovo poimanje kršćanske odgovornosti u svijetu i za svijet. Rad je podijeljen u dva dijela. U prvom dijelu analizira se Gaurdinijev pogled na moderno doba (novi vijek). Svjestan dvoznačnosti moderne svijesti, on pozitivnu dimenziju moder...

  9. PRIRODOSLOVLJE U KURIKULUMU ZA OBVEZNO OBRAZOVANJE

    OpenAIRE

    Domazet, Mladen

    2007-01-01

    Obzirom na raskorak između na europskoj razini izražene potrebe za većim brojem stručnjaka u području prirodnih znanosti i tehnologije (okvirno: prirodoslovlja), te višim stupnjem opće razine prirodoznanstvene pismenosti, i opadanje interesa osnovnoškolaca za teme iz područja prirodoslovlja, prikazuju se struktura i karakteristike nekih nacionalnih okvirnih kurikuluma u području prirodoslovlja, kao jednog od čimbenika usvajanja znanja i vještina iz područja prirodoslovlja na...

  10. Alati za poboljšavanje kvalitete

    OpenAIRE

    Čelar, Dražen; Valečić, Vladimir; Željezić, Dubravko; Kondić, Živko

    2014-01-01

    Kvaliteta je postala svjetski pokret i način življenja. Uspjeh organizacije najviše zavisi o kvaliteti proizvoda ili usluga. Za to najveću odgovornost snosi uprava, ali pri tome svi zaposleni moraju participirati u ostvarivanju kvalitete. Kvaliteta jest i biti će ključ za poboljšanje konkurentnosti na tržištu. Kvaliteta je značajan faktor opstanka, poslovnog uspjeha i prosperiteta poduzeća. Ključni princip sistema kvaliteta je donošenje odluka na osnovu činjenica, do kojih se dolazi prikuplja...

  11. Izdelava 3D tiskalnika za ciljno nalaganje

    OpenAIRE

    Kaštigar, Žiga

    2017-01-01

    Delo zajema razvoj in izdelavo 3D-tiskalnika od zasnove ohišja do prilagojevanja programske opreme za pravilno delovanje s podanimi parametri. Obsega izbiro materialov, konstrukcijske rešitve problemov prenosa moči iz motorja na jermen ali navojno vreteno. Zastavljeni cilji diplomske naloge so izdelati tiskalnik za ciljno nalaganje materiala, z avtomatsko kalibracijo mize, zaprto ohišje z možnostjo tiska več vrst materialov, na tiskalnik priključen zaslon LCD z bralnikom spominskih kartic in ...

  12. VMESNIK ZA DALJINSKO VODENJE NANO-ROBOTA

    OpenAIRE

    Kocmut, Silvester

    2015-01-01

    V diplomskem delu je predstavljen programski uporabniški vmesnik za vodenje realnega nano-robota. Uporabniški vmesnik omogoča neposredno krmiljenje nano-robota. Realni nano-robot ima pet translacijskih osi, omogoča tudi montažo prijemala. Osi delujejo na osnovi piezoelektričnih aktuatorjev. Izhod iz inkrementalnih dajalnikov nam da povratno informacijo o gibanju. Uporabniški vmesnik omogoča ročno vodenje preko navideznih gumbov za vseh pet osi ter vodenje preko ročne ure EZ430-Chronos. Krmilj...

  13. POMEN DOJENJA ZA OTROKA IN MATER

    OpenAIRE

    Apat, Alja

    2014-01-01

    Dojenje je naravni način hranjenja otroka v prvih mesecih njegovega življenja. Omogoča optimalno telesno in duševno rast ter razvoj otroka. Materino mleko vsebuje vsa življenjsko pomembna hranila v pravilnem ravnovesju. Dojenje ima mnoge prednosti, tako za mater, ki doji, kakor za njenega otroka. Pomembno vlogo pri dojenju imajo tudi medicinske sestre v porodnišnici in patronažne medicinske sestre. Njihova naloga je tudi zdravstveno-vzgojno delo pri dojenju. Cilj raziskave je bil ugotoviti os...

  14. Analiza reklamnih poruka za prehrambene proizvode namijenjene djeci

    OpenAIRE

    Ivančić, Ana Lana

    2015-01-01

    Cilj ovoga rada bio je utvrditi broj i kvalitetu reklama za prehrambene proizvode namijenjene djeci koje se pojavljuju u različitim medijima: 1) televiziji (nacionalnoj i komercijalnoj), 2) tiskovinama (dnevnim tiskovinama, specijaliziranim časopisima za majke i časopisima općeg sadržaja) te na 3) Internet portalima (općeg i specijaliziranog sadržaja). U specijaliziranom dvomjesečniku za majke pojavljuje se tek 2,4% reklama za mlijeko i mliječne proizvode, a 17,7% za dehidriranu dječju hranu ...

  15. Risk based definition of TS requirements for NPPs with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Morozov, V.; Tokmachev, G.

    2000-01-01

    The main regulations in safety related maintenance for NPPs in Russia are defined as a part of Technical Specifications (TSs). It includes limiting conditions for operation (surveillance requirements, allowed outage time, et.). In Russian practice the two levels of TSs are presented: general TSs that have been established as a master documents for similar designed NPPs and plant specific based on operation practice of each NPP unit. This paper presents a brief review of submissions to TS changes for NPPs with WWER type reactor were issued by AEP PSA team since 1988 year. Besides it provides an approach allows to estimate the complex affect on plant risk for both Limiting Conditions of Operation (LCO) and Surveillance Test Intervals (STI) based on relevant probabilistic tool (Minimal Cut Sets method and Marcov Chains methods). (author)

  16. Frequency response analysis of NPP containment with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Zoubkov, D.; Isaikin, A.; Shablinsky, G.

    2005-01-01

    Analysis of vibration load on the building structures of nuclear power plants (NPP) has come to the fore due to extension of their operational lifetime. Such analysis could be carried out if dynamic characteristics test (natural vibration frequency and natural mode) of NPP building structures is conducted in full-scale conditions. In this paper we represent methods of frequency response analysis of the generating unit 1 (RO-1) reactor compartment at Kalininskaya NPP on the basis of technogenic vibration. Main vibration sources of RO-1 are turbine-type generators, main centrifugal pumps and pipelines of power generating units 1 and 2. Vibration of RO-1 has been measured alternately at three points of RO-1 containment which is 76 m high and 47.4 m in diameter: top of the dome (76.0 m), holdout ring (70.3 m), point on the ground next to containment (0.0 m). Three components of vibration velocity have been measured simultaneously at each point: vertical Z-component, horizontal Y-component along the axis of the apparatus room and horizontal X-component across the room axis. Magnetoelectric pendulum-type vibrometers have been used for measurement. They were modernized by ad hoc multiposition amplifier card installed into the sensor body. Vibrometers were connected to the recorder by vibration protected and jam resistant cables. The results of present researches testified that dominant frequencies of X- and Y-oscillation spectra at RO-1 of Kalininskaya NPP (1.7 and 1.9 Hz correspondingly) correspond to the first vibration mode of RO-1 as a rigid construction on elastic foundation. High peaks of spectra at 16.7 and 25 Hz result from vibrations caused by main centrifugal pumps and turbine-type generators and coincide with the number of their revolutions per minute (1000 and 1500 rpm). Other peaks of spectra are related to the vibration of pipelines of primary and secondary circuits. (authors)

  17. Application of risk-informed approaches for optimization of control of WWER 1000 pipe metal

    International Nuclear Information System (INIS)

    Kolykhanov, Viktork; Komarov, Yuriy; Skalozubov, Volodymyr; Kovryzhkin, Yuriy

    2007-01-01

    According to Ukrainian regulations, the periodic control of pipes by non-destructive methods has to be performed on a precise basis depending on the degree of influence of a system on the nuclear power plant safety. In order to improve control programs of pipes metal, risk-informed approaches have been introduced. The characteristics of a pipe (or part of a pipe) has been assessed according 4 aspects: the influence on reactor safety, the influence on the reliability of power generation, the influence on residual resource (the resource is worked-out or not), and the absence/presence of defects in the pipe. The above assessment for a pipe or part of a pipe leads to one of the 4 levels of operational metal controls. Level 0: metal control is not carried out (the pipe is fixed when a failure appears), level 1: partial metal controls are performed, level 2: operational metal controls are performed, and level 3: extended metal controls are performed. This new approach has been applied to the pipes involved in the high pressure emergency core cooling system of the VVER-1000

  18. Analysis of reactor installation accident WWER-1000 caused by collector head rupture of steam generator

    International Nuclear Information System (INIS)

    Sviridenko, I.I.

    2005-01-01

    System classification of passive heat defence of nuclear dangerous objects with usage of heat pipes. The article is continuation of series of works devoted to research and development of promising passive cooling system of nuclear dangerous objects which use evaporating-condensing heat transfer devices of closed type - heat pipes and two-phase thermosyphons. Classification of autonomous systems of passive heat defence with usage low temperature heat tubes is given. Base classificational lectures are observed. Advantages n disadvantages of various circuit (scheme) solutions are analyzed

  19. A new diagnostic concept for the primary circuit of WWER 1000 reactors

    International Nuclear Information System (INIS)

    Streicher, V.; Liska, J.

    1993-01-01

    The new concept developed by the Skoda and Siemens companies is based on their own experience, the requirements of the Czech Power Board/NPP Temelin Diagnostic Department, and on the research work of various institutes in Czechoslovakia. The development of a complex diagnostic concept is an iterative process and includes parts with different stages of experience and different goals. They can be divided into five groups: PC-based diagnostic systems with continuous or periodic functions, equipment for condition monitoring, PC-based data collectors, studies, analyses and measures which are mandatory for the correct performance and interpretation of the diagnostic systems, and the integration of all subsystems and data acquisition/evaluation units into a Local Area Network with a graphic workstation. (Z.S.) 2 figs., 4 refs

  20. The Heat Exchanger for Passive Part ECCS of WWER-1000 on Base of the Thermo siphons

    International Nuclear Information System (INIS)

    Kirov, V.; Chulkin, O.

    2008-01-01

    One of NPP's systems providing safe operation is the system of emergency core cooling system (ECCS), which primary function in accidents is to flood the nuclear reactor core and to assure the sub critical condition and core cooling. At injection of cold water in reactor thermal stresses and thermal fatigue in the vessel cladding and constructional materials are arise. Low temperature of the water injected in reactor is a reason of occurrence of these undesirable consequences. Some variants of the water heating in accumulators of ECCS are considered. Now at Ukrainian NPPs the electrical heating in accumulators is used. Electrical heaters create the essential additional loading to diesel generators at imposing of two accidents - the large break and losses of power supplies on own needs. It is offered to use a heater in accumulators that working by a principle two-phase thermal siphon which advantages is: small dimensions, small delay and design reliability. In such heat exchanger the heating medium is a direct steam and the heated up medium is water with boric acid from accumulators of ECCS. Under requirements of the service regulations of ECCS accumulators it is necessary to guarantee injected water heating up to 90 ?? in case of a small break and to 150 ?? in case of the large break. Results of calculations for different external diameters of a tube of thermal siphon which have allowed to define the constructive sizes of heat exchanger, providing necessary conditions for required functioning of passive part ECCS are submitted The calculation and analysis of operating modes of the changed circuit of passive part ECCS for various accidents is carried out. The calculated pressure drop indicates that changes do not have essential influence on system work as a whole. Thus, the submitted decision provides the increase of reliability of ECCS at small and large breaks accidents, i.e. in all modes stipulated by the project.(author)

  1. Experimental study of new generation WWER-1000 fuel assemblies at JSC NCCP

    International Nuclear Information System (INIS)

    Enin, A.; Rozhkov, V.; Sinikov, Y.; Ustimenko, A.; Shustov, M.

    2003-01-01

    An experimental program for the study of fuel assembly thermomechanical stability has been established together with RF SSC IPPE and Russian Scientific Center Kurchatov Institute. Assembly fragments and small dummy models of fuel assembly skeletons and fuel rod bundles have been used for the tests. The test results are used for the design selection, verification of the design codes and substantiation of operating capacity of fuel assemblies with a rigid skeleton. The mechanical characteristics of units make it possible to perform fuel assembly strength and rigidity calculations, including the cases of abnormal operation. The mechanical characteristics of the skeleton and fuel rod bundle dummy models make it possible to check for the adequacy of the fuel assembly design model. The mechanical characteristics obtained during fuel rods bundle push through experiments make it possible to substantiate the fuel assembly serviceability under the conditions of fuel rods bundle and skeleton interaction

  2. Algorithms for diagnostics of the measuring channels and technological equipment at NPP with WWER-1000

    International Nuclear Information System (INIS)

    Vysotskij, V.G.

    1997-01-01

    An algorithm for diagnostics of the state of measuring channels of an information computer system with usage of analysis of statistical channel characteristics is presented. An algorithm for testing the generalized state of the NPP technological equipment is proposed

  3. SPND detectors response at the control rod drop in WWER-1000. Measurement and modelling results

    International Nuclear Information System (INIS)

    Mitin, V.; Milto, N.; Shishkov, L.; Tsyganov, S.; Kuzmichev, M.

    2006-01-01

    The paper analyzes and discusses possibility of neutron flux inspection in the WWER core during fast dynamic processes applying existing in-core monitoring system. The structure and functions of the system, basic principal of detector functioning and its temporal parameters are described briefly. To assess the ability of such dynamic monitoring the event with control rod drop happened during operation of Kozloduy NPP Unit 5 is observed - at the level of power close to nominal one of the rod from control group shifted to the lowest position at-2 seconds. In-core detectors readings at the process were registered and processed with mathematical methods that allow to single out only the prompt part of the signal. Results of the processing are presented. Furthermore, the process observing have been modeled with 3D dynamic code NOSTRA. Results of modeling are presenting in a paper, and comparing with experimental ones. A good agreement achieved. The analysis of measurements and its imitation give a hope that with an aggregate signal of detectors the measurement of control rod worth could be provided, and it allows to avoid of influence of spatial effects that are significant at standard technique with ex-core ion chambers (Authors)

  4. Development of expert system for fuel monitoring and analysis in WWER-1000 units

    International Nuclear Information System (INIS)

    Likhanskii, V.; Evdokimov, I.; Sorokin, A.; Kanukova, V.; Zborovskii, V.; Aliev, T.; Sokolov, N.; Shishkin, A.

    2011-01-01

    At present, an expert system (software package) for fuel monitoring in WWER units is under development in Russia. It comprises several modules which cover analysis of coolant activity, detection of failures and estimation of failure parameters, predictions of activity level and some aspects of PCI analysis. This paper outlines the current version of the fuel monitoring system, its basic features and user interface. Advances in development of computer modules for PCI analysis are reported. At present two levels of PCI analysis are used. The first is estimation of probability for pellets to get in contact with cladding in fuel rods. Estimations are made with taking into account specifications and tolerances for fuel fabrication as well as fuel operation conditions. The second level of PCI analysis implies a simplified approach for on-line calculations of stresses in cladding depending on power ramping rates. The model for PCI calculations and its application within the computer system is demonstrated. (authors)

  5. Initial data on protective containment for safety analysis of NPP with WWER-1000 Preparation

    Directory of Open Access Journals (Sweden)

    Gubeladze Oleg

    2017-01-01

    Full Text Available In the presented article the nuclear safety issues with VVER-1000 reactor are considered. The study element is the protective containment (PC, the most important function of which is localization and retention of radioactive substances within the accident localization zone. The example of possible unregulated destructive forcing (UDF on the PC for the construction and installation work period is given.

  6. Experiments for neutron fluence assessment on WWER-440 and WWER-1000 pressure vessel

    Energy Technology Data Exchange (ETDEWEB)

    Ilieva, K; Apostolov, T; Penev, I; Trifonov, A; Taskaev, E; Belousov, S; Antonov, S; Petrova, T; Stoeva, L [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika; Boyadzhiev, Z; Nelov, N; Tsocheva, V; Andreeva, I; Lilkov, B; Velichkov, V; Monev, M [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

    1996-12-31

    The activity of shavings sampled out from the expected maximum embrittlement location (weld 4) on the inner pressure vessel wall of the Kozloduy-1 Unit after the 14-th cycle has been measured. The experiment was carried out along the INEI channel using Fe and Cu string and foil detectors. The axial neutron flux distribution at the Unit 3 after the cycle 11 has been measured and compared to the calculated values. The calculations of the expected activities have been carried out taking into account the local power distribution. A comparison between measured and calculated values using ACTIVAT code is made. It shows a discrepancy of about 20%. It is recommended to carry out ex-vessel neutron fluence measurements using a rack device with activation detectors in order to verify the calculation results. 8 refs., 3 figs., 2 tabs.

  7. Alternative technology of containment construction for WWER 1000 nuclear power plant

    International Nuclear Information System (INIS)

    Chalus, Z.

    1982-01-01

    A number of alternatives was assessed for the assembly of the steel elements of the cylindrical part of containment. Alternative 1 is based on the common technology of manufacture, transport and assembly of reinforced concrete blocks of ca. 3x12 m in size, used for building leak-proof walls of WWER 440 nuclear power plants. Alternative 2 is based on reinforced concrete blocks using 12x12 m blocks assembled from individual elements on the building. site. Alternative 3 is a specific variant of the previous alternative. Alternative 4 envisages the assembly of a prefabricated support structure made of steel. Alternative 5 is based on the gradual assembly of partial elements mounted onto a support structure. Alternative 6 only differs from 5 in the method of assembly and manufacture of the support structure. All alternatives are shown in diagrams. (J.B.)

  8. Post-test investigation result on the WWER-1000 fuel tested under severe accident conditions

    International Nuclear Information System (INIS)

    Goryachev, A.; Shtuckert, Yu.; Zwir, E.; Stupina, L.

    1996-01-01

    The model bundle of WWER-type were tested under SFD condition in the out-of-pile CORA installation. The objective of the test was to provide an information on the WWER-type fuel bundles behaviour under severe fuel damage accident conditions. Also it was assumed to compare the WWER-type bundle damage mechanisms with these experienced in the PWR-type bundle tests with aim to confirm a possibility to use the various code systems, worked our for PWR as applied to WWER. In order to ensure the possibility of the comparison of the calculated core degradation parameters with the real state of the tested bundle, some parameters have been measured on the bundle cross-sections under examination. Quantitative parameters of the bundle degradation have been evaluated by digital image processing of the bundle cross-sections. The obtained results are shown together with corresponding results obtained by the other participants of this investigation. (author). 3 refs, 13 figs

  9. Floor response spectra of WWER-1000, NPP Kozloduy generated from local seismic excitation

    International Nuclear Information System (INIS)

    Bojadziev, Z.; Kostov, M.

    1996-01-01

    The seismic review level characteristics for the Kozloduy NPP site were set to 0.2 g and a respective free field acceleration response spectra were derived after a profound site conformation project. Accordingly a separate investigation is recommended for local seismic excitation. The goals of the analyses are: to define the seismic motion characteristics from local seismic sources; to perform structural analyses and in-structure spectra generation for local seismic excitation; and to compare the forces (spectra) from local events with those generated as seismic design review basis

  10. Main Aspects and Results of Level 2 PSA for KNPP WWER-1000/B320

    International Nuclear Information System (INIS)

    Mancheva, Kaliopa

    2014-01-01

    The PSA Level 2 for Kozloduy NPP (KNPP) is an update of an older study with wider scope of analysis. The older study represented the status of the units up to 2001. The current PSA Level 2 is based on the PSA Level 1 and represents the status of the units up to 2007 year concerning the systems and procedures included in PSA level 1 and status up to 2011 for the systems and procedures (e.g. SAMG) related to containment and severe accident aspects. The study is performed after the PSA level 1 has been finished and approved by the customer. Compare to the older analysis all modes of operation for analyzed in PSA level 1 event groups as well Spent Fuel Pool accidents are investigated. The analysis consists of both deterministic and probabilistic analysis. As part of deterministic analysis a contemporary containment strength analysis and accident progression deterministic analysis using last version of MELCOR are performed. The probabilistic analysis contains of two part: Interface PSA and CET are calculated using Riskspectrum program code. Two types of models for CET have been developed: one for conditional probabilities calculations and a set of simplified CET's for each PDS group-for integral model. The purpose of the first model is to be able to perform quick calculations and for sensitivity analyses as well. The simplified CET's are used for integral calculation of the model. Source Term analysis is mainly based on the MELCOR analyses results. All characteristics of the releases have been defined, i.e. location, mass, energy of radionuclide groups and activity of the released isotopes (most important are reported only). The main goals of the study are to analyze the status of the containment, systems designed to prevent containment failure and operator action required under the severe accident and to give quantitative assessment of the risk parameter LERF (Large Early Release Frequency). This report will present main aspects, results, finding and conclusions of the analysis. Based on the results, the effectiveness of the current means and SAMG are assessed qualitatively. (author)

  11. Reactor noise analysis applications and systems in WWER-440 and WWER-1000 type PWRs

    International Nuclear Information System (INIS)

    Por, G.

    1998-01-01

    This paper presents an introduction on different types of well selected noise diagnostic methods with their occurrence in WWER reactors with an analysis of their impact on operational safety and aging which affects the installations safety as well. The main objective is to attract the attention of NPP management staff dealing with safety, safety culture, maintenance, operation and quality assurance proving that such methods can give benefit not only to economy but impact safety of nuclear installations

  12. Application of simple approximate system analysis methods for reliability and availability improvement of reactor WWER-1000

    International Nuclear Information System (INIS)

    Manchev, B.; Marinova, B.; Nenkova, B.

    2001-01-01

    The method described on this report provides a set of simple, easily understood 'approximate' models applicable to a large class of system architectures. Constructing a Markov model of each redundant subsystem and its replacement after that by a pseudo-component develops the approximation models. Of equal importance, the models can be easily understood even of non-experts, including managers, high-level decision-makers and unsophisticated consumers. A necessary requirement for their application is the systems to be repairable and the mean time to repair to be much smaller than the mean time to failure. This ia a case most often met in the real practice. Results of the 'approximate' model application on a technological system of Kozloduy NPP are also presented. The results obtained can be compared quite favorably with the results obtained by using SAPHIRE software

  13. Results of research and development for nuclear power plants with WWER-1000 type light water reactors

    International Nuclear Information System (INIS)

    1984-01-01

    The conference met in three sessions: 1. Project designing and construction of nuclear power plants; 2. Materials, technologies and applied mechanics; 3. Physics, thermal physics and control. The proceedings contains 82 papers of which only two have not been inputted in INIS. The final resolutions of session 1 related to the reduction of capital costs for newly built units, processing of project documentation, the introduction of step motors manufactured in Czechoslovakia, in-service diagnostics of nuclear power plants, etc. The final recommendations of session 2 dealt with the centralization of the management of research into the reliability, safety and residual life of nuclear installations, with radiation stability of weld metals, repairs of nuclear power plants by patch welding, with welding in nuclear power plants and stress calculations using mathematical methods. Session 3 centred on questions of the safety, reliability and economy of nuclear power plant operation. It was recommended to make a comparison of the results of theoretical calculations with experiments, to concentrate on the automation of measurement, to extend international division of labour and cooperation of CMEA countries, to extend publishing activities in the field of thermal physics, etc. General recommendations were related to the conception of the construction of nuclear power plants in Czechoslovakia, the implementation of original scientific, research and development work, to the question of personnel for nuclear research, the experimental base of the Czechoslovak nuclear programme and to planning and management of technical development. (E.S.)

  14. Recent advances and achievements in WWER-1000 fuel design performance and operation

    International Nuclear Information System (INIS)

    Vasilchenko, I.; Molchanov, V.

    2009-01-01

    In this paper the main results of TVS-2 (TVS-2M) basic design operation like TVS-2 - 1216 pcs., including 687 in operation, TVS-2M - 66 pcs. in operation (Balakovo-1); reliability -1,6·10-6 in 2008 and the Balakovo NPP capacity factor - 90% are presented. Average efficient operating time of the Balakovo power units, calculated capacity factor for the Balakovo NPP at transition to fuel cycle 3x1,5, contemporary operational requirements for fuel and their realization as well as SPND axial position variation in the core with TVS - 2M and CPS AR usage are shown

  15. Building concept of cooling towers for WWER-1000 nuclear power plants

    International Nuclear Information System (INIS)

    Bucha, V.; David, M.

    1984-01-01

    A project is described of cooling towers with natural draught for the Temelin nuclear power plant. The concept proceeds from the classical design of the so-called Itterson type, i.e., the outer cladding of the draught stack is made of a monolithic reinforced concrete unit in the shape of a hyperboloid of revolution supported by a system of oblique supports mounted along the edge of the cooled water tank. The procedure is explained of the thermal calculation for the given operating conditions. The basic alternatives are considered of the choice of material and design of the cooling system. Questions are discussed relating to the design of the eliminator, the windwart wall and the shape of the shell of the draught stack and its loading by wind and seismic effects. (E.S.)

  16. Improvement of operation efficiency for WWER-440 and WWER-1000 for TRIGON fuel assembly design features

    Energy Technology Data Exchange (ETDEWEB)

    Silberstein, A [European WWER Fuels GmbH, Lyon (France)

    1994-12-31

    TRIGON 440 and TRIGON 1000 fuel assemblies and their assembly matching counterparts are described. Their role in increasing the efficiency of WWER reactors is stressed. Special attention is paid to their design features as well as calibrated means of predicting behaviour under irradiation from light water reactor core operation. They reduce the fuel cycle cost as a result of the reduced need for natural uranium which have to be enriched and of the smaller number of fuel assemblies which have to be fabricated, stored or reprocessed. The improved control assemblies bring comfort to the plant operator due to intrinsic progress in safety with respect to accidental situation, trouble-free behaviour and long time utilization in the reactor. 14 figs.

  17. Experimental study of ballooning and failure of WWER-1000 fuel cans during maximum design basis accident

    International Nuclear Information System (INIS)

    Karetnikov, G.V.; Bogdanov, A.S.; Semishkin, V.P.; Bezrukov, Yu.A.; Trushin, A.M.; Frizen, E.A.

    2001-01-01

    The processes of ballooning and fracturing in tubular specimens of Eh635 and Eh110 alloy fuel cans are investigated with the use of cinematography. The investigations are carried out under steady-state conditions in the temperature range from 680 to 900 deg C and at pressure drops on the can from 2 to 12 MPa. Time dependences of circumferential strains are plotted for various temperatures of fuel cans at pressure of 2 MPa. It is shown that strain changes are of linear character at an initial portion of the curve and then an accelerated strain development takes place with transition to fracture. Using methods of nonlinear evaluation for time to fracture the approximation dependences are obtained for fuel cans. Experimental data are intended to form the equations of state for fuel can materials and to verify the program TVEL-3 [ru

  18. Digitalni servo sistem za upravljanje infracrvenim lokatorom

    OpenAIRE

    Aleksandar Viličić; Mirko Jezdimirović

    2009-01-01

    U radu je predstavljen digitalni servo sistem sa pogonskim elektromotorom koji zamenjuje postojeći elektrohidraulički servo pogon na uređaju za upravljanje IC lokatorom, koji obezbeđuje zahtevanu tačnost pozicioniranja i praćenja sa minimalnim brzinama.

  19. RAZVOJ REŠITVE ZA KONTROLO PRISTOPA

    OpenAIRE

    Sladič, Tim

    2016-01-01

    Diplomsko delo opisuje področje mikrokrmilnikov in razvoj rešitve za kontrolo pristopa. Rešitev deluje na principu oddaljenosti naprave od senzorja, preko brezžične tehnologije Bluetooth, ki ga imamo danes že skoraj v vsaki napravi.

  20. Sedimentation survey of Lago Loíza, Trujillo Alto, Puerto Rico, July 2009

    Science.gov (United States)

    Soler-López, Luis R.; Licha-Soler, N.A.

    2014-01-01

    Lago Loíza is a reservoir formed at the confluence of Río Gurabo and Río Grande de Loíza in the municipality of Trujillo Alto in central Puerto Rico, about 10 kilometers (km) north of the town of Caguas, about 9 km northwest of Gurabo, and about 3 km south of Trujillo Alto (fig. 1). The Carraizo Dam is owned and operated by the Puerto Rico Aqueduct and Sewer Authority (PRASA), and was constructed in 1953 as a water-supply reservoir for the San Juan Metropolitan area. The dam is a concrete gravity structure that is located in a shallow valley and has a gently sloping left abutment and steep right abutment. Non-overflow sections flank the spillway section. Waterways include an intake structure for the pumping station and power plant, sluiceways, a trash sluice, and a spillway. The reservoir was built to provide a storage capacity of 26.8 million cubic meters (Mm3) of water at the maximum pool elevation of 41.14 meters (m) above mean sea level (msl) for the Sergio Cuevas Filtration Plant that serves the San Juan metropolitan area. The reservoir has a drainage area of 538 square kilometers (km2) and receives an annual mean rainfall that ranges from 1,600 to 5,000 millimeters per year (mm/yr). The principal streams that drain into Lago Loíza are the Río Grande de Loíza, Río Gurabo, and Río Cañas. Two other rivers, the Río Bairoa and Río Cagüitas, discharge into the Río Grande de Loíza just before it enters the reservoir. The combined mean annual runoff of the Río Grande de Loíza and the Río Gurabo for the 1960–2009 period of record is 323 Mm3. Flow from these streams constitutes about 89 percent of the total mean annual inflow of 364 Mm3 to the reservoir (U.S. Geological Survey, 2009). Detailed information about Lago Loíza reservoir structures, historical sediment accumulation, and a dredge conducted in 1999 are available in Soler-López and Gómez-Gómez (2005). During July 8–15, 2009, the U.S. Geological Survey (USGS) Caribbean Water Science

  1. AMS Radiocarbon Dating of Large Za Baobabs (Adansonia za) of Madagascar.

    Science.gov (United States)

    Patrut, Adrian; Patrut, Roxana T; Danthu, Pascal; Leong Pock-Tsy, Jean-Michel; Rakosy, Laszlo; Lowy, Daniel A; von Reden, Karl F

    2016-01-01

    The article reports the radiocarbon investigation of Anzapalivoro, the largest za baobab (Adansonia za) specimen of Madagascar and of another za, namely the Big cistern baobab. Several wood samples collected from the large inner cavity and from the outer part/exterior of the tree were investigated by AMS (accelerator mass spectrometry) radiocarbon dating. For samples collected from the cavity walls, the age values increase with the distance into the wood up to a point of maximum age, after which the values decrease toward the outer part. This anomaly of age sequences indicates that the inner cavity of Anzapalivoro is a false cavity, practically an empty space between several fused stems disposed in a ring-shaped structure. The radiocarbon date of the oldest sample was 780 ± 30 bp, which corresponds to a calibrated age of around 735 yr. Dating results indicate that Anzapalivoro has a closed ring-shaped structure, which consists of 5 fused stems that close a false cavity. The oldest part of the biggest za baobab has a calculated age of 900 years. We also disclose results of the investigation of a second za baobab, the Big cistern baobab, which was hollowed out for water storage. This specimen, which consists of 4 fused stems, was found to be around 260 years old.

  2. AMS Radiocarbon Dating of Large Za Baobabs (Adansonia za of Madagascar.

    Directory of Open Access Journals (Sweden)

    Adrian Patrut

    Full Text Available The article reports the radiocarbon investigation of Anzapalivoro, the largest za baobab (Adansonia za specimen of Madagascar and of another za, namely the Big cistern baobab. Several wood samples collected from the large inner cavity and from the outer part/exterior of the tree were investigated by AMS (accelerator mass spectrometry radiocarbon dating. For samples collected from the cavity walls, the age values increase with the distance into the wood up to a point of maximum age, after which the values decrease toward the outer part. This anomaly of age sequences indicates that the inner cavity of Anzapalivoro is a false cavity, practically an empty space between several fused stems disposed in a ring-shaped structure. The radiocarbon date of the oldest sample was 780 ± 30 bp, which corresponds to a calibrated age of around 735 yr. Dating results indicate that Anzapalivoro has a closed ring-shaped structure, which consists of 5 fused stems that close a false cavity. The oldest part of the biggest za baobab has a calculated age of 900 years. We also disclose results of the investigation of a second za baobab, the Big cistern baobab, which was hollowed out for water storage. This specimen, which consists of 4 fused stems, was found to be around 260 years old.

  3. Savremeno naoružanje i vojna oprema za br. 2-2005 / Modern weapons and military equipment for issue 2-2005 / Современное вооружение и военное оборудование за но. 2-2005

    Directory of Open Access Journals (Sweden)

    Mirko Krbavac

    2005-03-01

    Full Text Available Laser protiv minobacačkih napada; Poboljšana laka samohodna haubica 155 mm; Velika Britanija poboljšava moć zemaljske artiljerije; Laki raketni artiljerijski sistem LIMAWS(R; Poboljšani sistem PVO Osa–AKM; Južnokorejski višecevni raketni lanser 70 mm; Novi SUV za projektile Krasnopolj; Borbeno vozilo pešadije Marder MK 30; Novi čistač mina marinskog korpusa SAD; Izraelski oklopni transporter Nemerah; Sistem Protektor za oklopna vozila; Dodatna zaštita za lako oklopljena vozila Modernizovani lovački avion Su-27SM; Sistem za samozaštitu helikoptera; Bespilotni helikopter Little Bird; Bolja zaštita vozila M2 Bradley; „Elektromagnetni oklop“ za laki tenk Thunderbolt; Poboljšani ručni laserski daljinomer Vector; Ekonomišan sistem za identifikaciju; Lako vozilo za vatrenu podršku; Naoružana robotizovana vozila; Razvoj snažnijih tenkovskih motora u Rusiji; Motori za laka borbena vozila; Prvo terensko vozilo na vodonik; Nove tehnologije za borbu protiv bombi; Novi kineski i iranski RPG-7; Lako oklopno vozilo CM-32; Taktičko vozilo MTV A1+ 8×8; Ručni širokopojasni softverski radio; Sistem za akviziciju cilja na bespilotnoj letelici; Osmatrački radar nove generacije MRR-3D; Novi koncept brzih brodova; Patrolni čamac Super Dvora Mk III; Nova ruska podmornica Projekt 677; Višenamenski patrolni brod MOPV; Detektor za streljačko naoružanje; Laka verzija avioradara N011M Bars.

  4. Upotreba začina u proizvodnji tradicionalnih sireva

    OpenAIRE

    Josipović, Renata; Markov, Ksenija; Frece, Jadranka; Stanzer, Damir; Cvitković, Ante; Mrvčić, Jasna

    2016-01-01

    Sir je visoko cijenjeni mliječni proizvod u mnogim zemljama svijeta, a posebna pažnja pridaje se tradicionalnim sirevima, koji nisu samo hrana već i dio kulture i obilježja neke zemlje. Zahvaljujući zemljopisnom položaju i klimatsko-vegetacijskoj raznolikosti Republike Hrvatske, u pojedinim regijama razvijena je proizvodnja različitih tradicionalnih sireva uz upotrebu začina. Kod proizvodnje sireva sa začinima, začini se dodaju ili u sir koji se potom oblikuje, ili se sir omata lišćem začinsk...

  5. Primerjava orodij za avtomatizacijo testiranja uporabniških vmesnikov

    OpenAIRE

    GABER, DOMEN

    2018-01-01

    V diplomskem delu je predstavljeno delovanje in uporaba modernih orodij za avtomatizacijo testiranja uporabniških vmesnikov. Namen dela je primerjati izbrana orodja za avtomatizacijo testiranja in olajšati odločitev pri izboru orodja za avtomatizacijo testiranja. Glavni cilj avtomatizacije je zmanjšanje stroškov in hitrejše izvajanje testiranja. Na trgu je danes na voljo več orodij za avtomatizacijo testiranja, ki so si med seboj različna po zahtevnosti uporabe, načinu delovanja in podpor...

  6. Cesta za divokým kaprem.

    Czech Academy of Sciences Publication Activity Database

    Blabolil, Petr

    2016-01-01

    Roč. 2016, č. 6 (2016) E-ISSN 1214-4029 R&D Projects: GA MŠk(CZ) EE2.3.20.0204 Grant - others:AV ČR(CZ) StrategieAV21/9 Program:StrategieAV Institutional support: RVO:60077344 Keywords : common carp * habitat alteration * distribution Subject RIV: EH - Ecology, Behaviour http://vesmir.cz/2016/06/28/cesta-za-prakaprem/

  7. 2-mm microwave interferometer

    International Nuclear Information System (INIS)

    Futch, A.H.; Mortensen, W.K.

    1977-01-01

    A 2-mm microwave interferometer has been developed, and phase shift measurements have been made on the Baseball II experiment. The interferometer system employs a 140-GHz receiver for double down conversion of the plasma signal to a 60-MHz, IF frequency. The 140-GHz references signal is also down-converted and compared with the plasma signal to provide the desired phase change of the signal passing through the plasma. A feedback voltage from a 60-MHz discriminator to a voltage-controlled oscillator in the receiver provides frequency stability of the 60-MHz IF signals

  8. Dhima za Mbinu Linganishi katika Kuhusisha Lugha na Lahaja ...

    African Journals Online (AJOL)

    Lengo la makala hii ni kujadili dhima za Mbinu Linganishi katika kuhusisha lugha na lahaja. Data za makala hii zilikusanywa kwa kutumia mbinu mbalimbali ambazo ni usaili, ushuhudiaji, hojaji na majadiliano katika majopo. Utafiti ulifanyika Tanzania Bara hususan Mkoani Mtwara na Tanzania Visiwani katika maeneo ya ...

  9. Dhima ya Mianzo na Miisho katika Nathari za Kiswahili za Fasihi ya ...

    African Journals Online (AJOL)

    Fasihi ya watoto hutofautiana na fasihi ya watu wazima katika maudhui, fani, mawanda, walengwa na hata umri. Pamoja na kutofautiana huko, bado dhima ya fasihi inabaki ileile ya kufundisha, kuburudisha, kuonya, kuadibu, kurithisha amali za jamii na kadhalika. Wataalamu mbalimbali wa fasihi wakiwapo waandishi, ...

  10. Muziki wa Hip Hop na Haki Za Kijamii: Dhima, Changamoto na ...

    African Journals Online (AJOL)

    Ni dhahiri kuwa haki za kijamii zinaweza kuwasilishwa kwa jamii pana kupitia sanaa ya hip hop. Makala haya basi, yanabainisha dhima na mchango wa muziki wa hip hop katika masuala ya haki za kijamii, yanafafanua changamoto za muziki huu katika kuwasilisha haki za kijamii na kutoa mapendekezo kwa makundi ...

  11. 'Iktibasi' katika Tenzi za Mwanakupona na Al-Inkishafi | Beja | Kioo ...

    African Journals Online (AJOL)

    Makala haya yanatazama tenzi za kale za Kiswahili kwa mkabala wa kitabu kitukufu cha Kurani na Sunnah za Mtume Muhammad (SAW). Wahakiki wengi wamechambua tenzi hizi za kale na kutoa maoni kwamba zina maudhui ya dini ya Kiislamu. Hata hivyo ushahidi halisi wa jinsi watunzi walivyochota maudhui yao ...

  12. IZDELAVA SPLETNE TRGOVINE ZA PRODAJO UNIKATNIH IZDELKOV

    OpenAIRE

    Vrečar, Maja

    2016-01-01

    Podjetje PAR, Maja Vrečar, s. p., izdeluje unikaten nakit iz polimerne gline in drugih materialov ter drobne uporabne predmete, kot so knjižna kazala ali obešalniki za torbice. Prodaja je do zdaj potekala prek zasebnih stikov in na sejmih. Udeležba na sejmih je majhna, prodaja pa je odvisna od številnih zunanjih dejavnikov. Dodatne zaplete povzroča tudi spremenjena davčna zakonodaja pri poslovanju z gotovino. Drugih ustreznih prodajnih kanalov podjetje nima, zato je prodaja slaba. Dobra alter...

  13. Frenulektomije - kada i zašto?

    OpenAIRE

    Kopić, Vlatko; Perić, Berislav; Macan, Darko

    2004-01-01

    Podatci iz literature često su dijametralno suprotni što se tiče potrebe da se izvede kirurški zahvat kod perzistentnoga frenuluma, bilo da se radilo o njegovoj izravnoj povezanosti s dijastemom medijanom ili ne. Različita su mišljenja o najpovoljnijem vremenu za zahvat ili na redoslijed intervencije kirurga, odnosno ortodonta. Većina se autora slaže u tome da je zahvat potreban, ali i da se s njim ne treba žuriti. Pojedini autori smatraju kako treba pričekati da iznikne trajni očnjak, a d...

  14. Naravna interakcija za mobilno navidezno resničnost

    OpenAIRE

    PROSENIK, UROŠ

    2016-01-01

    Navidezna resničnost (angl. virtual reality, VR) na tehnološkem trgu povzdiguje vse več prahu. Prav tako vse več mobilnih naprav, ki jih uporabniki uporabljajo za vsakodnevne potrebe, podpira in je dovolj zmogljivih za izvajanje VR aplikacij. Zaradi tega se na trgu pojavlja vse večje število VR očal, ki skrbijo za projekcijo slike z zaslona mobilne naprave na uporabnikove oči. Ta očala so lahko od različnih proizvajalcev in raznovrstnih oblik. Mnoga ne posedujejo nobenih dodatnih kontrolnih g...

  15. SISTEMI ZA ČIŠČENJE FOTONAPETOSTNIH MODULOV

    OpenAIRE

    Džidić, Adnan

    2013-01-01

    V diplomskem delu so predstavljeni nanopremazi za čiščenje sončnih modulov kot učinkovita metoda za povečanje izplena proizvodnje električne energije sončnih modulov. Opisane so fizikalne osnove delovanja sončnih celic, ki so potrebne za osnovno razumevanje delovanja sončnih modulov. Nanopremazi zagotavljajo, da se umazanija in dežne kapljice ne zadržujejo na aktivni površini sončnih modulov in s tem zagotavljajo čistost površine. Na eksperimentalnem primeru je ovrednoten izplen proizvedene e...

  16. ODLOČITVENI MODEL ZA IZBIRO INFORMACIJSKEGA SISTEMA GOSTINSKEGA LOKALA

    OpenAIRE

    Radišić, Nikola

    2011-01-01

    Diplomska naloga vsebuje obravnavo procesa odločanja v kontekstu poslovnih sistemov. Osredotočenje je na računalniškem programu za podporo odločanju Dexi in reševanju odločitvenega problema izbire informacijskega sistema gostinskega lokala (GIS). Za reševanje problema uporabljena je metoda modeliranja večkriterijskega odločitvenega modela v DEXi-ju, kjer so za slučaj gostinskega lokala "Flirt Sushi Longue" ovrednoteni pet variant (ponudnikov GIS-ov v Sloveniji). Rezultat diplomskega dela je a...

  17. RAZVOJ MOBILNE APLIKACIJE ZA INFORMACIJE O BANKOMATIH

    OpenAIRE

    Jenko, Bojan

    2016-01-01

    Vsakodnevno se srečujemo z opravljanjem storitev na bančnih avtomatih, od dviga gotovine do nakupa mobi kartice. Če storitve opravljamo na vedno istem bančnem avtomatu, nam to postane rutina in se ne obremenjujemo z ostalimi težavami, ki lahko nastanejo, kot sta odpoved bančnega avtomata, ki ga po navadi uporabljamo, menjava okolja ipd. Začne se iskanje najbližjega bančnega avtomata, ki ustreza našim potrebam. Najbližji bančni avtomat pa ni nujno najboljša izbira, saj mogoče ne podpira želeni...

  18. Raziskava o sprejemljivosti komasacije za urbano prenovo v Hongkongu

    Directory of Open Access Journals (Sweden)

    Yung Yau

    2009-01-01

    Full Text Available Ker se Hongkong spopada z vse hujšim propadanjem, si mestne oblasti zelo prizadevajo za obnovo. Vendar se sanacija zaradi zamudnega in zahtevnega pridobivanja zemljišč pogosto zavleče. Obvezni odkupi pridobivanje zemljišč sicer pospešijo, vendar tej tehniki marsikdo očita, da ustvarja družbene napetosti med predstavniki za prenovo in prizadetimi lastniki posesti. Nekaj pravic prizadetim lastnikom zagotavlja zakon o zaščiti zasebne lastnine, vendar se nekateri odločijo še za dodatne ukrepe, da si zagotovijo udeležbo pri dobičku, ustvarjenim s prenovo. Prisilna selitev zaradi prenove lahko resno ogrozi socialne mreže. Zaradi teh težav so strokovnjaki predlagali »komasacijo« (ang. land readjustment. Ta tehnika zagotovi partnerski odnos med interesnimi skupinami, udeleženimi pri projektu prenove. V tujini uporabljajo komasacijo v različne namene, vendar je njena uporabnost za prenovo zgradb v Hongkongu vprašljiva. Ta prispevek se ukvarja s sprejemljivostjo komasacije v Hongkongu. Sestavili smo vprašalnik, ki ga je izpolnilo 356 prebivalcev mesta Kowloon City. Na podlagi rezultatov raziskave smo oblikovali predloge in praktične rešitve. Izsledki o trajnostni prenovi mest ponujajo dragocena spoznanja za javne upravljavce in mestne upravitelje.

  19. SSC 40 mm cable results and 50 mm design discussions

    International Nuclear Information System (INIS)

    Christopherson, D.; Capone, D.; Hannaford, R.; Remsbottom, R.; Delashmit, R.; Jayakumar, R.J.; Snitchler, G.; Scanlan, R.; Royet, J.

    1991-01-01

    This paper presents a summary of the cable produced for the 1990 40 mm Dipole Program. The cable design parameters for the 50 mm Dipole Program are discussed, as well as portions of the SSC specification draft. Considerations leading to the final cable configuration and the results of preliminary trials are included. The first iteration of a strand mapping program to automate cable strand maps is introduced

  20. SSC 40 mm cable results and 50 mm design discussions

    International Nuclear Information System (INIS)

    Christopherson, D.; Capone, D.; Hannaford, R.; Remsbottom, R.; Jayakumar, R.; Snitchler, G.; Scanlan, R.; Royet, J.

    1990-09-01

    A summary of the cable produced for the 1990 40 mm Dipole Program is presented. The cable design parameters for the 50 mm Dipole Program are discussed, as well as portions of the SSC specification draft. Considerations leading to the final cable configuration and the results of preliminary trials are included. The first iteration of a strand mapping program to automate cable strand maps is introduced. 7 refs., 2 figs., 1 tab

  1. Peta obletnica prve slovenske revije za izobrazevanje odraslih

    Directory of Open Access Journals (Sweden)

    Ana Kranjc

    2000-12-01

    Full Text Available RevijaAndragoška spoznanja, prva slovenska revija za izobraževanje odraslih, praznuje peto obletnico izhajanja. Člani uredniškega odbora se skupaj z avtorji in bralci veselimo tega jubileja. Pred očmi imamo začetna prizadevanja, da je revija sploh nastala, in nato prizadevanja za njen obstoj, pri pridobivanju novih sodelavcev, širjenju kroga bralcev in zagotavljanju materialnih sredstev, pri čemer ne smemo pozabiti tudi na občasne težave. Večina truda pa je bila posvečena temu, da bi revija opravljala svoje osnovno poslanstvo.

  2. Kdo se izobražuje za partnerske odnose?

    Directory of Open Access Journals (Sweden)

    Natasa Rijavec Klobučar

    2004-12-01

    Full Text Available V prispevku avtorica analizira znacilnosti udelezencev izobrazevanja za partnerske odnose, ki obiskujejo Solo za zakon. Podatke interpretira v skladu s sistemsko relacijsko teorijo, ki cloveka ne obravnava posamicno, marveč z vidika odnosov, ki jih dejavno oblikuje z drugimi. Rezultati raziskave kazejo, da so moski bolj zadovoljni s partnerskim odnosom kot zenske. Oboji pricakujejo, da bo izobrazevanje pomagalo izboljsati njihove partnerske odnose, ne pa tudi komunikacije z otroki. Svoje odnose vecinoma dozivljajo kot konfliktne. 0 tem prica tudi dejstvo, da jih najbolj privlacijo teme, ki pojasnjujejo genezo konfliktov in obravnavajo naCine reševanja.

  3. Robotizacija oddelka lakirnice v programu za pralno pomivalne aparate

    OpenAIRE

    Klemenčič, Matej

    2012-01-01

    V začetnem delu diplomskega dela smo na kratko predstavili podjetje Gorenje d.d., njihovo dejavnost in poslovna področja. Nato je opisano, kakšen je pomen oblikovanja delovnih mest za same pogoje dela ter razlaga sistemizacije in ergonomije, ki imata tudi zelo pomembno vlogo pri urejanju delovnih mest. V nadaljevanju je predstavljena metoda 20 ključev, ki pomaga podjetjem, da se čim hitreje prilagajajo globalnemu trgu. Zaradi varnostnih in ekonomskih razlogov se je podjetje odločilo, d...

  4. Primerjava ogrodij entity framework in nhibernate za objektno - relacijsko preslikavo

    OpenAIRE

    Rola, Tadej

    2017-01-01

    V diplomskem delu primerjamo ogrodji za objektno-relacijsko preslikavo Entity Framework in NHibernate. Na začetku smo razložili klasičen način dostopa do podatkovne baze preko ADO.NET komponente, v nadaljevanju še O-RM tehnologijo. Nato je sledila podrobna predstavitev obeh ogrodij. V drugem delu diplomskega dela najprej razložimo in prikažemo glavne funkcionalnosti enega in drugega na praktičnem primeru. V zadnjem delu diplomskega dela pišemo o razlikah med enim in drugim ter njunih prednost...

  5. Odgoj za poduzetništvo u primarnom obrazovanju

    OpenAIRE

    Posavec, Mirjana

    2011-01-01

    Suvremena škola povećava važnost komunikacijskih i interpersonalnih vještina, a društvo treba široko obrazovane kadrove pripremljene za nove promjene što zahtijeva različite i inovativne pristupe u učenju. To uključuje stjecanje novih vještina i kompetencija. Jedna od takvih kompetencija jest odgoj i obrazovanje za poduzetništvo, koje se kao međupredmetna tema pojavljuje u Nacionalnom okvirnom kurikulumu. Školske zadruge imaju dugogodišnju predanost obrazovanju, a zadružne vrijednosti imaju m...

  6. PRIMERJAVA DVEH METOD ZA MERJENJE ZADOVOLJSTVA GOSTOV V HOTELIH

    OpenAIRE

    Osterc, Miša

    2016-01-01

    Zadovoljstvo gostov je ključni element za uspešen razvoj in dolgoročen obstoj kateregakoli hotelskega podjetja, zato mora biti njihovo doseganje tudi glavni cilj vsakega hotela. Pri tem je potrebno upoštevati, da zagotavljanje zadovoljstva gostov zahteva dobro poznavanje želja in pričakovanj vsakega gosta, zato je merjenje, analiziranje in spremljanje zadovoljstva eden najpomembnejših izzivov pri pripravi strategije poslovanja vsakega hotela. To velja tudi za Hotel Bioterme Mala Nedelja,...

  7. Vgrajen sistem za kontrolo dostopa z modulom Bluetooth

    OpenAIRE

    PETROVSKA, ANA

    2014-01-01

    Vprašanje varnosti in zasebnosti je izziv že leta. Zaradi tega je pomembno imeti lasten system za nadzor dostopa, ki ga bo uporabnik nadzoroval ob vsakem trenutku, ko ima s seboj svojo mobilno napravo. V tem delu bomo predstavili vgrajen system za nadzor dostopa, temelječ na STM32F4 razvojni plošči. Razvojna plošča temelji na mikrokrmilniku STM32F407VGT6 z jedrom ARM® Cortex™-M4F in vgrajenim pomnilnikom Flash in SRAM. Na plošči so povezani Bluetooth modul HC-05, bralnik RFID in modul z ...

  8. Modeling of the WWER-1000 fuel-rod behavior in steady-state condition with FRAPCONE-3 computer code

    International Nuclear Information System (INIS)

    Andreeva, Marina; Totev, Totju; Stoyanov, Stoyan

    2008-01-01

    It is presented within the paper the results of the modeling and the assessment of the integral code predictions of the WWER fuel-rod behavior in steady-state condition. The assessments in this paper have used the MASSIH and ANS 5.4 subroutine in the code. The modeling and calculations have been performed with FRAPCONE-3 computer code in Argonne National Laboratory, USA

  9. Reactor physics of light water power reactors of the WWER-1000 type in the SKODA Trust. Part 2

    International Nuclear Information System (INIS)

    Zbytovsky, A.; Vyskocil, V.; Vacek, J.; Krysl, V.

    1979-01-01

    The system is described of multigroup transport programs and the respective data libraries used at the SKODA WORKS for calculating few-group diffusion constants. The importance is stressed of precisioning nuclear data. The programs for multigroup calculations are mostly written in FORTRAN-1900. The structure of microcalculations is described and the possible cost savings are indicated. (J.P.)

  10. Development of requirements for seismic upgrading of equipment of existing WWER-440 and WWER-1000 type NPPs

    International Nuclear Information System (INIS)

    Kaznovsky, S.; Ostretsov, I.

    1993-01-01

    The change in seismology data and safety demands a necessity arose for seismic upgrading of the existing operating NPPs of WWER type which have been originally designed and built without or with simplifies calculations of seismic influences. The paper describes the traditional methods and approaches and calculation-experimental method for examining and ensuring of equipment seismic resistance at the NPPs directly. Method of ground explosions is included as well

  11. Analyses with ASTEC related to release of FPs and aerosol transport in case of SBLOCA For WWER 1000

    International Nuclear Information System (INIS)

    Atanasova, B.; Stefanova, A.; Groudev, P.

    2008-01-01

    The objective of this paper is to present the results obtained from performing the calculations with ASTEC computer code for the Source Term evaluation for specific severe accident transient. The calculations have been performed with the new version of ASTEC. The ASTEC 1.3 R2 code version is released by the French IRSN (Institut de Radioprotection at de surete nucleaire) by the end of 2007. The sequences include the release of fission products into the reactor containment and environment and transport of fission products. The analyses proposed here are performed to simulate radioactive products release through the cold leg of SG under accidental conditions. This investigation has been performed in the framework of the SARNET project (under the EURATOM 6th framework program) by the FoBAUs group (Forum of Bulgarian ASTEC users). (authors)

  12. The feasibility of express in situ measurement of the isotopic composition of uranium in fresh WWER-1000 fuel

    International Nuclear Information System (INIS)

    Christoskov, I.; Tsankov, L.; Ivanov, N.

    2011-01-01

    A study of the feasibility and accuracy of measurement of the enrichment of fresh VVER-1000 fuel assemblies using a miniature CdZnTe probe is performed.The possibilities of improvement of the analytical procedure are briefly discussed. (authors)

  13. Results of TVSA fuel assemblies development and 10-years operation in WWER-1000 reactors cores. Development trends

    International Nuclear Information System (INIS)

    Molchanov, V.; Sharikov, A.; Samoilov, O.; Kaidalov, V.; Falkov, A.; Romanov, A.; Shishkin, A.

    2009-01-01

    The basic TVSA design is now operating successfully in 17 VVER-1000 power units of Russia, Ukraine and Bulgaria. TVSA design is characterized by reliability and validity of designs and resource characteristics. TVSA possesses light hydraulics and peak ratio for implementation of effective fuel cycles. Unique parameters on time of maintenance and burnup are achieved. The basic design - TVSA-5M - has been introduced into commercial operation. It is necessary to expand heading TVSA with debris filter and temperature control tubes. Two directions of evolution of a design - TVSA-ALPHA and TVSAPLUS are realized. Evolution is directed on increasing uranium content and realization of 5x1 and 3x1.5 fuel cycles with operation at raised power. The TVSA design offers a great optimization potential based on a series of proven (reference) technical solutions. TVSA is competitive and cost effective and ensures the market advantages of Russian nuclear fuel

  14. Control of power distribution and the safety of a WWER-1000 reactor during operation in a load-following regime

    International Nuclear Information System (INIS)

    Filipchuk, E.V.; Dunaev, V.G.; Luk'yanets, I.A.; Potapenko, P.T.; Timokhin, E.S.; Voznesenskij, V.A.; Mitin, V.I.

    1984-01-01

    An important task in ensuring the operational safety of a nuclear power plant with a vessel-type water-cooled, water-moderated reactor is the development of algorithms for controlling power distribution in base-load and load-following regimes. The control strategy must ensure that the form of power distribution is maintained within the permissible limits in the case of situations presenting a nuclear hazard and of xenon fluctuations when there are variations in power output. The task of controlling power distribution can be broken down into an axial problem and a radial-azimuthal problem. For maintenance of the form of axial power distribution an algorithm of optimum fast-action control is proposed; for maintenance of the radial-azimuthal form, an algorithm of optimum (i.e. best) approximation to the given distribution of control. The two control problems are solved by using a single computerized procedure based on mathematical programming. The algorithms are designed for use in computerized control. The paper presents the results of algorithm simulation. The authors propose that in the first stage, activation of the control systems should involve the operator, who can view the sequence of actions on a display screen. (author)

  15. Probability analysis of WWER-1000 fuel elements behavior under steady-state, transient and accident conditions of reactor operation

    International Nuclear Information System (INIS)

    Tutnov, A.; Alexeev, E.

    2001-01-01

    'PULSAR-2' and 'PULSAR+' codes make it possible to simulate thermo-mechanical and thermo-physical parameters of WWER fuel elements. The probabilistic approach is used instead of traditional deterministic one to carry out a sensitive study of fuel element behavior under steady-state operation mode. Fuel elements initial parameters are given as a density of the probability distributions. Calculations are provided for all possible combinations of initial data as fuel-cladding gap, fuel density and gas pressure. Dividing values of these parameters to intervals final variants for calculations are obtained . Intervals of permissible fuel-cladding gap size have been divided to 10 equal parts, fuel density and gas pressure - to 5 parts. Probability of each variant realization is determined by multiplying the probabilities of separate parameters, because the tolerances of these parameters are distributed independently. Simulation results are turn out in the probabilistic bar charts. The charts present probability distribution of the changes in fuel outer diameter, hoop stress kinetics and fuel temperature versus irradiation time. A normative safety factor is introduced for control of any criterion realization and for determination of a reserve to the criteria failure. A probabilistic analysis of fuel element behavior under Reactivity Initiating Accident (RIA) is also performed and probability fuel element depressurization under hypothetical RIA is presented

  16. Thermal-hydraulic model of the primary coolant circuits for the full-scale training facility with WWER-1000

    International Nuclear Information System (INIS)

    Kroshilin, A.E.; Zhukavin, A.P.; Pryakhin, V.N.

    1992-01-01

    The mathematical model realized in the full-scale educational facility for NPP operator training is described. The RETACT computational complex providing real time process simulation for all regimes including the maximum credible accident is used for calculation of thermohydraulic parameters of the primary coolant circuits and steam generator under stationary and transient conditions. The two-velocity two-temperature model of one-dimensional steam-water flow containing uncondensed gases is realized in the program

  17. Main trends and content of works on fabrication of fuel rods with MOX fuel for the WWER-1000 reactor

    International Nuclear Information System (INIS)

    Tsykanov, V.A.; Golovanov, V.N.; Mayorshin, A.A.; Yurchenko, A.D.; Ilyenko, S.A.; Syuzev, V.N.

    2000-01-01

    The main trends of production of pellet MOX-fuel for the WWER reactors using the trial-experimental equipment at SSC RF RIAR are set forth. The main realized parameters of fabrication of MOX-fuel pellets are presented. The content of the reactor tests program is considered with allowance for their licensing requirements for the WWER reactors. (author)

  18. First qualitative analysis of fuel irradiation results carried out in the MR reactor on WWER-1000 fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chantoin, P [International Atomic Energy Agency, Vienna (Austria); Dubrovin, K; Platonov, P [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation); Onufriev, V [Vsesoyuznyj Nauchno-Issledovatel` skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)

    1994-12-31

    Four experiments carried out in the MR reactor are evaluated. They are aimed to assess the influence of burnup and the size of the pellet central hole on the fuel temperature and thus on the fuel swelling and fission gas release. The experiments have been performed at different linear rate and burnup of the fuel rods which are above the actual licensed values in WWER power stations. In this paper the results on WWER fuel rod behaviour are examined. The main fabrication and irradiation characteristics for each experiment are given. The main results from destructive and non-destructive examinations are summarized. They include: burnup determination by gamma spectroscopy, caesium shifting along fuel column and accumulation at the end of the fuel stack, fission gas release. fuel rod diameter and length change and macro-graphs showing the central hole size and the morphology after irradiation. From observation of fuel structure, Cs spectrometry and fission gas release, a large degradation of fuel thermal conductivity can be identified at high burnup. If the fuel burnup is the right parameter to be considered, burnup limits identified are: 0 70-75 MWd/kg for rods with large central hole; (2) 58-64 MWd/kg for rods with small central hole. As a general conclusion it is stressed the importance of the study due to irradiation beyond the usual linear rates at high burnup. Up to now the fuel life limiting factor was cladding corrosion when using Zircaloy-4. As the cladding corrosion situation improves, the next life limiting factor to be met could be the fuel itself. The decreasing fuel thermal conductivity is probably of prime importance and should be further studied and modelled. 5 tabs., 5 figs., 3 refs.

  19. Uelekeo wa Maana za Kipolisemia katika Msamiati wa Kiswahili ...

    African Journals Online (AJOL)

    Data iliyotumika ni kutoka Kamusi ya Kiswahili Sanifu (TUKI, 2013). Ili kukidhi malengo hayo tumetumia Nadharia ya Maana kama Dhana, ambapo tunahusisha maana (dhana) mpya za kipolisemia na maana ya msingi ya neno hilo. Matokeo ya utafiti huu yamebaini kuwa polisemia huwa na maana zaidi ya moja ...

  20. Majukumu ya Wahusika Wanawake katika Tendi teule za Kiswahili ...

    African Journals Online (AJOL)

    Utendi ni mojawapo ya tanzu za fasihi ya Kiswahili ulio na historia ndefu. Miongoni mwa tendi hizi ni Utendi wa Mwanakupona, Utendi wa Fumo Liyongo, Utendi wa Swifa ya Nguvumali, Utendi wa Ngamia na Paa, na Utendi wa Mikidadi na Mayasa au Utendi wa Qiyama. Tendi hizi huwa na sifa zinazolandana upande wa ...

  1. Juhudi za Vyombo vya Habari katika Kukuza na Kueneza Kiswahili ...

    African Journals Online (AJOL)

    Vyombo vya habari ni asasi muhimu sana katika kukuza na kueneza lugha yoyote ile, hasa katika enzi hii ya utandawazi. Vyombo hivyo ni kama vile idhaa za redio, televisheni na magazeti. Katika nchi ya Kenya kuna vyombo vya habari vinavyotoa huduma anuwai kwa ajili ya kutosheleza mahitaji ya wateja wao. Katika ...

  2. Asili na Chimbuko la Wazungumzaji wa Kimakunduchi: Hoja za ...

    African Journals Online (AJOL)

    Wakati tukiwa tunasherehekea mafanikio ya lugha ya Kiswahili katika nyanja mbalimbali, hatuna budi kujiuliza katika mijadala yetu ni kwa kiwango gani tumezishirikisha lahaja za Kiswahili katika kubaini mambo mbalimbali ikiwemo historia ya lugha hii. Tukumbuke kwamba wakati wa uteuzi wa lahaja ya Kiunguja kuwa ...

  3. Utafiti Wa Lahaja Za Kiswahili: Uzoefu Wa Uwandani | Ismail ...

    African Journals Online (AJOL)

    Katika ujumla wake, historia ya utafiti, na hasa utafiti wa uwandani, ni historia ya jitihada za binadamu katika kujishughulisha kwake ili ayaelewe masuala mengi mtambuka katika mazingira fungamanishi. Hakuna mtafiti yeyote anayeweza kudai kuwa utafiti wa mada fulani katika eneo fulani umekamilika na ...

  4. ulinganishi wa muundo wa vitomeo katika kamusi mbili za kiswahili

    African Journals Online (AJOL)

    ULINGANISHI WA MUUNDO WA VITOMEO KATIKA KAMUSI MBILI ZA KISWAHILI - KIINGEREZA. E.K.F Chiduo. Abstract. Ulinganishi wa Kamusi Sanifu ya Kiswahili-Kiingereza (KSKK, 1993) na Kamusi ya Kiswahili- Kiingereza (KKK, TUKI 2001) unazingatia mtazamo wa Nkweti-Azel. Mtizamo huu unazingatia vipengelele ...

  5. Regulations and instructions for RA reactor operation; Propisi i uputstva za pogon reaktora 'A'

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-07-01

    This regulatory guide consists of following 4 chapters: Description of the RA reactor, organization scheme, regulations for performing experiments; Regulations for staff on duty; Instructions for operating the vacuum systems, heavy water and helium systems; and evacuation in case of accident. [Serbo-Croat] Ovaj pravilnik sadrzi sledeca 4 poglavlja: Opis reaktora RA, sema organizacije rada, propisi za izvodjenje eksperimenata; Pravilnik za rad dezurnog osoblja; Uputstva za rada sa vakuum sistemima, sistemom teske vode, sistemom helijuma; evakuacija u slucaju udesa.

  6. Odnos međunarodnoga i europskoga pravnog okvira za suzbijanje terorizma

    OpenAIRE

    Pedić, Žana

    2012-01-01

    U radu se razmatra složenost pravnog okvira za borbu protiv terorizma na univerzalnoj razini i na razini Europske Unije te njihov međuodnos. Navodi se problematika nepostojanja jedinstvene definicije terorizma, analizira se međunarodni pravni okvir kroz ulogu Ujedinjenih naroda u stvaranju međunarodnih pravnih i kvazipravnih instrumenata za borbu protiv terorizma, analizira se struktura sustava Europske Unije i njezina uloga u provedbi međunarodnih instrumenata za borbu protiv terorizma te pr...

  7. METODOLOGIJA ZA DIMENZIONIRANJE NESEMAFORIZIRANIH NIVOJSKIH KRIŽIŠČ

    OpenAIRE

    Vogrinec, Petra

    2010-01-01

    Promet je pomemben dejavnik v razvoju človeštva. Omogoča transport ljudi, tovora in informacij. Ker se cestni promet iz leta v leto povečuje, prihaja do večjih zamud in kolon na cestah in v križiščih. Če so povprečne zamude prevelike, je treba izvesti ukrepe za povečanje prepustnosti ceste oziroma križišča. V diplomi je predstavljena metodologija za dimenzioniranje nesemaforiziranih nivojskih križišč. Poudarek je na križišču glavne in stranske ceste. Izračun je narejen po »Highway Capacity...

  8. Razlikovnost kao pretpostavka za registraciju žiga

    OpenAIRE

    Matanovac Vučković, Romana

    2012-01-01

    U radu se obrazlaže stupnjevanje razlikovnosti u ispitivanju apsolutnih smetnji za registraciju nekog znaka kao žiga nakon harmonizacije žigovnoga prava u Europskoj uniji. Obrazlaže se i nerazdruživost između funkcije označivanja podrijetla i razlikovnosti žiga. S time u svezi obrađuju se Direktiva 2008/95/EZ Europskog parlamenta i Vijeća od 22. listopada 2008. za usklađivanje propisa država članica koji se odnose na žigove (kodificirani tekst), Uredba Vijeća (EZ) 207/2009 od 26. veljače 2009...

  9. Poenostavljen sistem za samodejno bočno parkiranje

    OpenAIRE

    ŠTROS, MATIC

    2014-01-01

    Diplomsko delo prikazuje poenostavljen sistem bočnega parkiranja na modelu vozila. Sistemi za bočno parkiranje se že pojavljajo v avtomobilski industriji in so zmožni detekcije praznega parkirnega mesta ter vožnje v parkirni prostor. Prednost takega sistema, vgrajenega v vozilo, je v tem, da lajša bočno parkiranje, ki ga mnogi neizkušeni vozniki ne obvladajo.

  10. The ZaP Flow Z-Pinch Project

    International Nuclear Information System (INIS)

    Shumlak, U.; Nelson, B. A.

    2005-01-01

    The results from the ZaP experiment are consistent with the theoretical predictions of sheared flow stabilization. Z pinches with a sheared flow are generated in the ZaP experiment using a coaxial accelerator coupled to an assembly region. The current sheet in the accelerator initially acts as a snowplow. As the Z pinch forms, plasma formation in the accelerator transits to a deflagration process. The plasma exits the accelerator and maintains the flow in the Z pinch. During the quiescent period in the magnetic mode activity at z=0 cm, a stable Z pinch is seen on the axis of the assembly region. The evolution of the axial velocity profile shows a large velocity shear is measured at the edge of the Z pinch during the quiescent period. The velocity shear is above the theoretical threshold. As the velocity shear decreases towards 0.1kV A , the predicted stability threshold, the quiescent period ends. The present understanding of the ZaP experiment shows that it may be possible for the Z pinch to operate in a steady state if the deflagration process can be maintained by constantly supplying neutral gas or plasma to the accelerator

  11. Marketingová analýza úspěšnosti projektu ZaNázory.cz

    OpenAIRE

    Pohan, Lukáš

    2012-01-01

    The bachelor thesis analyses the ZaNázory.cz project, its various parts and its success as well as its target audience. The analysis of the project is based on experience from the making of this project. Other field of interest of this thesis is to evaluate the success of this project in present and its future forecasts and compares the estimated target audience with real target audience at present.

  12. STRATEGIJE VARNOSTNEGA KOPIRANJA PODATKOV IN REŠITVE ZA MALA PODJETJA

    OpenAIRE

    Kočevar, Dušan

    2012-01-01

    V diplomskem delu bomo definirali in predstavili strategije varnostnega kopiranja podatkov in pomen podatkov za podjetja. V teoretičnem delu smo opisali zgodovino varnostnega kopiranja in arhiviranja, medije za shranjevanje in podatkovne repozitorne modele. Opisali in primerjali smo strategije in pristope varnostnega kopiranja ter predstavili statistiko izgube podatkov. Zraven tradicionalnih pristopov smo predstavili tudi varnostno shranjeva...

  13. Mkanganyiko wa Dhana za Mzizi, Kiini na Shina katika Mofolojia ya ...

    African Journals Online (AJOL)

    Kwa mwanazuoni yeyote ambaye anafahamikiwa na dhana za kimofolojia hakosi kuwa amewahi kuzitumia au kuzisoma au hata kuzieleza dhana za kiini, shina na mzizi. Mbali na matumizi ya dhana hizi ni ukweli usiopingika kwamba dhana hizi zimekuwa zikitumika katika kufasili dhana nyingine pia. Uambishaji, kwa ...

  14. Tikuvõileivaduell / Roman Zaštšerinski ; interv. Jaanus Kulli

    Index Scriptorium Estoniae

    Zaštšerinski, Roman, 1978-

    2008-01-01

    Intervjuu kokk Roman Zaštšerinskiga, kes valmistas koos Imre Kosega ette Vabariigi Presidendi iseseisvuspäeva vastuvõtu menüü. Vt. samas: Roman Zaštšerinski menüü vabariigi presidendi vastuvõtul

  15. Friction and wear behavior of TiC particle reinforced ZA43 matrix composites

    Institute of Scientific and Technical Information of China (English)

    谢贤清; 张荻; 刘金水; 吴人洁

    2001-01-01

    TiC/ZA43 composites were fabricated by XDTM and stirring-casting techniques. The tribology properties of the unreinforced ZA43 alloy and the composites were studied by using a block-on-ring apparatus. Experimental results show that the incorporation of TiC particles improves the microstructure of ZA43 matrix alloy. The coefficient of friction μ and the width of worn groove decrease with the increase of TiC volume fraction φ(TiC). The width of worn groove and μ of the composite during wear testing increase with increasing the applied load. Metallographic examinations reveal that unreinforced ZA43 alloy has deep ploughing grooves with obvious adhesion phenomenon, whereas TiC/ZA43 composites have smooth worn surface. Delamination formation is related to the fatigue cracks and the shear cracks on the surface.

  16. Zaštita pomorskog dobra u Republici Hrvatskoj

    Directory of Open Access Journals (Sweden)

    Vinko Hlača

    2010-12-01

    Full Text Available Pomorsko dobro oduvijek je bio prostor koji je kao najinteresantniji dio teritorija svake države, pa i Republike Hrvatske, bio izložen najrazličitijim nasrtajima (primjerice izgradnja marina, apartmanskih naselja, nasipanja mora i sl.. Granica pomorskog dobra počela je biti jako važna onoga časa kada su se na morskoj obali masovnije počeli graditi raznorazni objekti (vikendice, luke, plaže, turistički objekti i sl.. U Republici Hrvatskoj pomorsko dobro je opće dobro na kojem vlast ima država te ona za njega brine, održava ga i odgovara za njega. Prema mnijenju autora do sada se postupak određivanja granice pomorskog dobra te njezino evidentiranje u katastar i zemljišnu knjigu ne može ocijeniti zadovoljavajućom ocjenom. Ako se ima na umu da je prostor koji danas zauzima Republika Hrvatska često kroz povijest mijenjao državnu pripadnost onda i ne čudi anarhija na pomorskom dobru koja traje do danas. Stoga, sve do danas nije (razriješen problem stečenih prava na pomorskom dobru. Autori daju prikaz stvarnih prava za koja su mnijenja da se mogu smatrati stečenim na pravno valjan način. Nadalje, prikazuje se pravorijek Trgovačkog suda u Rijeci koji je razriješio (nevlasničke odnose u luci posebne namjene – brodogradilištu kao i pravorijek Visokog trgovačkog suda Republike Hrvatske koji je razmatrao razlučna prava na narečenoj luci posebne namjene. Na kraju rada autori iznose svoj stav na razmatranoj problematici te moguća rješenja de lege ferenda.

  17. KOMUNICIRANJE KOT ORODJE ZA REŠEVANJE KONFLIKTOV

    OpenAIRE

    Kastrevec, Marjana

    2012-01-01

    Komuniciranje sodi med najbolj običajne in vsakodnevne aktivnosti v našem ţivljenju. Za nas je komuniciranje pogosto samoumevno, če pa ga ţelimo bolje proučiti kaj hitro postane kompleksno in zahtevno. Vse naše delovanje je pod vplivom komuniciranja bodisi z drugimi, bodisi z nami samimi. Pravzaprav komuniciramo ves čas. Komuniciranje predstavlja neke vrste orodje, s pomočjo katerega ustvarjamo in negujemo odnose z drugimi. Ţivimo v času gospodarskih, druţbenih in okoljskih ...

  18. Primernost drevesnih vrst za zasaditev deponije elektrofiltrskega pepela v Trbovljah

    OpenAIRE

    Taškar, Sašo

    2014-01-01

    Lokacija raziskovalne ploskve je na deponiji elektrofiltrskega pepela Prapretno v Trbovljah, na kateri je bilo zasajenih devet vrst dreves. Namen diplomskega dela je ugotoviti, katera vrsta se bo uspešno prilagodila danim razmeram, ki vladajo na tako degradiranih površinah. Od 2001 do 2008 so bili preučevani parametri, in sicer rast dreves v višino, razvoj koreninskega sistema, debelinska rast dreves in ekološke razmere, ki so v tem času vladale na območju deponije. Razlogi za slabo uspevanje...

  19. Primerjalna analiza platform za izdelavo spletnih mest google sites wix

    OpenAIRE

    Orešek, Mateja

    2017-01-01

    Tema diplomskega seminarja je izdelava spletnih mest s pomočjo brezplačnih orodij. V današnjem času podjetja nujno potrebujejo spletno mesto, saj večina ljudi pridobi informacije na svetovnem spletu in za nekatera podjetja je strošek izdelave spletnega mesta prevelik, zato smo v diplomskem projektu preverjali, ali lahko izdelamo spletno mesto brez znanja programiranja in ali je spletno mesto, izdelano z brezplačnimi orodji, vseeno lahko videti profesionalno. Namen diplomskega projekta je ...

  20. KONCIPIRANJE IN SNOVANJE NAPRAVE ZA SAMOPOSTREŽNO PRODAJO SVEČ

    OpenAIRE

    Banfi, Damir

    2010-01-01

    V diplomskem delu je opisano snovanje in koncipiranje naprave za prodajo sveč s pomočjo 3D programa. Prikazan je postopek snovanja z idejnimi rešitvami glavnih problemov in koncipiranje končnih rešitev. Opisan je vrstni red sestave in obdelovalni postopki ter narejena je tudi ocena lastnih stroškov. Najprej je predstavljen problem, sledijo opisane zahteve in rešitve do kateri smo prišli. Opisani so tudi nekateri problemi in predstavljeni načini obdelave in sestave samega elementa. Sledi i...

  1. SPLETNA APLIKACIJA ZA PREVERJANJE NASTAVITEV ZASEBNOSTI NA FACEBOOKU

    OpenAIRE

    Žolek, Matija

    2013-01-01

    Diplomsko delo obravnava problem zasebnosti na spletnem družbenem omrežju Facebook. Pravice do zasebnosti so vse bolj izpostavljene okolju, v katerem se nahajamo. Prav zaradi spletnih družbenih omrežij, kot je npr. Facebook, postaja vprašanje nadzora nad našo zasebnostjo in uporabo naših zasebnih podatkov tako zelo aktualna tematika. Facebook, kot vodilni med spletnimi družbenimi omrežji (Mba, 2013), vzbuja veliko vprašanj glede varnosti osebnih podatkov uporabnika. Naredili smo aplikacijo za...

  2. Sustav obrazovanja kadrova za hotelijersko-turističko gospodarstvo

    OpenAIRE

    Peršić, Milena

    1995-01-01

    Kadrovi su osnovni društveni i gospodarski resurs razvoja svake djelatnosti, pa tako i pojedinih segmenata u strukturi hotelijersko-turističkog gospodarstva. Iz te spoznaje proizlazi potreba ustroja takvog obrazovnog sustava koji će postojećim i potencijalnim djelatnicima pružiti odgovarajuća znanja za što kvalitetnije uključivanje u sve segmente izvođačkog, informacijskog i upravljačkog sustava hotelskog poduzeća. Neusklađenost nastavnih planova, programa i obrazovnih profila sa stvarnim zah...

  3. VZPOSTAVITEV SISTEMA ZA UPRAVLJANJE INFORMACIJSKE VARNOSTI V PROIZVODNEM PODJETJU

    OpenAIRE

    Škarja, Peter

    2012-01-01

    Magistrska naloga obravnava vzpostavitev sistema za upravljanje informacijske varnosti (SUIV) v proizvodnem podjetju, pri čemer se osredotoča na 1. fazo Demingovega kroga – načrtovanje vzpostavitve SUIV. Sestavljena je iz dveh delov. V prvem delu so podane teoretične osnove s področja informacijske varnosti. Prikazana je zasnova modela načrtovanja SUIV s pomočjo smernic, ki jih podaja standard ISO/IEC 27003. V drugem, praktičnem delu je predstavljeno podjetje Vega International d.o.o. Opisano...

  4. Utjecaj guma za žvakanje u prevenciji karijesa

    OpenAIRE

    Janković, Bernard; Ciglar, Ivana; Knežević, Alena; Miletić, Ivana; Bračić, H.

    2003-01-01

    Zubni karijes je zbog svoje rasprostranjenosti u svijetu velik javnozdravstveni problem. Zbog toga ne iznenađuje činjenica da postoji velik broj materijala i postupaka kojima je svrha prevencija nastanka zubnoga karijesa. Jedan je od tih postupaka uporaba guma za žvakanje koje simuliranjem lučenja sline sprječavaju stvaranje dentobakterijskoga plaka na površinu zuba i uklanjaju već akumulirani plak. Ispitivanje je obuhvatilo 16 studenata (12 studentice i 4 studenta) 3., 4. i 5. godine Stomato...

  5. Uporaba platforme Arduino za izdelavo vozlišča IoT na vezju ESP8266

    OpenAIRE

    SELAN, MATEJ

    2016-01-01

    V diplomskem delu je predstavljena zasnova sistema za merjenje temperature in relativne vlage s pomočjo modula ESP8266 z brezžičnim spletnim dostopom do rezultatov meritev. Za merjenje temperature in vlažnosti skrbi digitalni merilni senzor DHT11, modul ESP8266 pa poleg osnovnih funkcij, potrebnih za prenos podatkov, zagotavlja tudi preprost strežnik za konfiguriranje. Sestavni deli naloge so analiza področja, modul ESP8266, serijski vmesnik FTDI, protokoli za povezovanje in ostala strojna op...

  6. Uticaj oksidacije aktivnog uglja sumpornom kiselinom i impregnacije bakar-sulfatom na sorpcionu sposobnost gasnog filtra za zaštitu od dejstva amonijaka / Study of the effects of activated carbon oxidation with sulphuric acid and impregnation with copper sulphate on the protection capacity of gas filters against ammonia

    Directory of Open Access Journals (Sweden)

    Sretko Ilić

    2002-01-01

    Full Text Available U radu je istraživana mogućnost poboljšanja kvaliteta aktivnog uglja (AU za upotrebu u sredstvima za ličnu zaštitu respiratornih organa od dejstva amonijaka. Uzorci komercijalnih AU oksidovani su različitim količinama rastvora sumporne kiseline, masenih koncentracija 10% i 15%. Na uzorke AU tretirane kiselinom deponovan je zatim bakar-sulfat, metodom dvostruke impregnacije rastvorom bakar-sulfata do početne vlažnosti uzorka. Impregnisani AU ispitanje u sloju u gasnom filtru prečnika 105 mm, čije su visine imale vrednosti od 29 mm do 41 mm, a uslovi su bill: ulazna koncentracija amonijaka -3,5 mg/dm3 (zapreminska koncentracija 0,5%, protok gasne smeše vazduh-amonijak - 30 dm3/min, relativna vlažnost 70% i ambijentna temperatura. Proboj je detektovan kvalitativno, pomoću indikatorskog papirića safenolftaleinom. AU impregnisan novim postupkom obezbedio je u sloju visine 29 mm vreme proboja 108 min, a 160 min u sloju visine 41 mm. / The objective of this paper has been the study of the possibility to enhance the properties of activated carbon (AC for using it in respiratory protective devices for ammonia removal from the air. The commercial AC samples were oxidized with different amounts of 10% and 15% sulphuric acid solutions. The acid treated AC samples were the loaded with copper sulphate with twofold impregnation by the incipient wetness method. The impregnated AC was tested in a packed bed in the gas filter with a diameter of 105 mm and a bed depth ranging from 29 mm to 41 mm under the following test conditions inlet concentration of ammonia was 3,5 mg/dm3, flow rate of 30 dm3/min at 70% relative humidity and ambient temperature. The breakthrough was detected qualitatively by the phenolphtalein indicator paper. The new impregnated AC reached the breaktrough time of 108 min for a 29 mm bed depth, and 160 min for a bed depth of 41 mm.

  7. Ekološko oblikovana embalaža za naravno kozmetiko

    OpenAIRE

    Šepec, Urša

    2017-01-01

    Namen diplomskega dela je bil raziskati področje ekološkega oblikovanja, zahteve in priporočila pri embaliranju na področju kozmetične industrije ter načrtovati in izdelati inovativno ekološko oblikovano funkcionalno embalažo za kolekcijo trdnih mil in šamponov, ki po odprtju služi kot podstavek za milo na umivalniku. Poleg embalaže smo izdelali tudi etikete za ostale kozmetične izdelke, kot so losjoni, kreme in mazila. V teoretičnem delu je opredeljeno ekološko oblikovanje embalaže ter s...

  8. IZDELAVA E-UČBENIKA ZA PRVO POMOČ S PROGRAMOM ADOBE CAPTIVATE

    OpenAIRE

    Vrščaj, Sonja

    2013-01-01

    Diplomska naloga predstavlja in govori o izdelavi elektronskega učbenika za izbrano podjetje, ki se nanaša na tematiko prve pomoči. E-učbenik bo predstavljal obliko izobraževanja ob podpori računalniške tehnologije v programu Adobe Captivate 5.5., ki je namenjen oblikovanju interaktivnih vsebin za elektronsko učenje. V nalogi bodo obdelane teme, ki so pomembne za izdelavo e-učbenika. Podrobno si bomo ogledali potek izdelave e-učbenika v navedenem programu, proučili pa bomo tudi koncept izobra...

  9. Razvoj in industrializacija močnostnega pretvornika za pogon sesalnika z vodnim filtrom

    OpenAIRE

    ŠUBIC, MIHA

    2015-01-01

    Magistrsko delo je osredotočeno na razvoj elektromehanskega pogona za sesalnik z vodnim filtrom ter na pripadajoče zahteve in postopke, ki jih narekuje tako imenovana industrializacija izdelka. Slednja se ne podreja le zahtevam naročnika, temveč splošnejšim predpisom ter standardom, ki regulirajo ustreznost izdelka za prodajo na svetovnih trgih. Elektromehanski pogon sesalnika z nazivno vhodno močjo 720 W sestavljata elektronsko komutiran motor (EKM) in elektronsko vezje, ki skrbi za zanes...

  10. UPORABA SOCIALNIH OMREŽIJ ZA POVEČANJE OBISKA SPLETNE STRANI

    OpenAIRE

    Kepnik, Valerija

    2010-01-01

    Diplomska naloga obravnava uporabo socialnih omrežij za povečanje obiska spletne strani podjetja Tridens. Predstavljeno je podjetje, njihova spletna stran in socialna omrežja, ki jih uporabljajo. Za potrebe naloge so podrobno opisani: Facebook, blog, Twitter, Flickr, SlideShare, LinkedIn in YouTube. Predstavljene so tudi nekatere prednosti za podjetja, ki jih ponujajo socialna omrežja. V eksperimentalnem delu naloge je bila izvedena analiza obiskov na spletni strani in sicer pred uporabo s...

  11. Instructions for RA reactor decontamination - Annex 10; Prilog 10 - Uputstvo za dekontaminaciju Reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-12-15

    Instructions for RA reactor decontamination includes: action plan for decontamination of the heavy water system by 7% water solution of H{sub 3}PO{sub 4} + 2% CrO{sub 3} acid; description of the preparatory work including calculation of the pipes volume and installation of special pipes; detailed instructions for decontamination procedure. [Serbo-Croat] Uputstvo za dekontaminaciju Reaktora RA sadrzi: plan operacija za dekontaminaciju sistema teske vode 7% vodenim rastvorom kiseline H{sub 3}PO{sub 4} + 2% CrO{sub 3}; opis pripremnih radova ukljucujuci proracun zapremine covovoda i montiranje posebnih cevovoda; detaljno uputstvo za izvodjenje operacija pri dekontaminaciji.

  12. MODEL SISTEMA ZA UPRAVLJANJE INFORMACIJSKE VARNOSTI V DRŽAVNI UPRAVI

    OpenAIRE

    Tomažič, Samo

    2012-01-01

    V magistrskem delu je predstavljena zasnova modela sistema za upravljanje informacijske varnosti za slovensko državno upravo. Informacijski sistemi v državni upravi morajo namreč zaradi svoje ključne vloge, ki jo opravljajo, delovati brezhibno, saj ima lahko že majhen izpad hujše ekonomske ali drugovrstne posledice, ki jih državljani čutimo neposredno. V okviru sistematične vpeljave sistema za upravljanje informacijske varnosti (SUIV) v katerokoli organizacijo, se držimo štirih temeljnih faz ...

  13. Uporaba algoritmov inteligence rojev za rešitev problema dostavnih vozil

    OpenAIRE

    Hlastec, Urban

    2018-01-01

    V magistrski nalogi smo obravnavali in implementirali algoritem umetne kolonije čebel za reševanje problema dostavnih vozil z več skladišči. Zanimalo nas je, kako so algoritmi s področja inteligence rojev ustrezni in uporabni za reševanje optimizacijskih problemov. V nalogi smo združili algoritem umetne kolonije čebel ter algoritem za reševanje problema dostavnih vozil. Primerjali smo tudi rezultate pred optimizacijo različnih spremenljivk in po in tako ugotovili, kaj najbolj vpliva na hitros...

  14. Data of evolutionary structure change: 1A0ZA-2ZLWD [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1A0ZA-2ZLWD 1A0Z 2ZLW A D -VLSPADKTNVKAAWGKVGAHAGEYGAEALERMFLSFPT...R VQLSGEEKAAVLALWDKVN--EEEVGGEALGRLLVVYPWTQRFFDSFGDLSNPGAVMGNPKVKAHGKKVLHSFGEGVHHLDNLKGTFAALSEL...ex>0 2ZLW D 2ZLWD

  15. Loodusfotograaf Sven Začek saab lindudega sõbraks / interv. Kristjan Roos

    Index Scriptorium Estoniae

    Začek, Sven, 1980-

    2012-01-01

    Tartu lähedal Kõrvekülas elavast 31-aastasest loodusfotograafist Sven Začekist sai Remo Savisaare ja Priit Vesilinnu kõrval kolmas eestlane, kelle fotosid on avaldanud mainekas loodusajakiri National Geographic

  16. UPORABA PISARNE V OBLAKU ZA POTREBE DRUŽINSKEGA IN MLADINSKEGA CENTRA

    OpenAIRE

    Repnik, Tina

    2013-01-01

    V diplomski nalogi smo v prvem delu teoretično obravnavali teledelo in računalništvo v oblaku. Preučili smo poznane rešitve računalništva v oblaku na trgu in se odločili za uporabo storitev enega izmed vodilnih podjetij s tega področja Google. Opredelili smo začetke in razvoj Googlea v svetu. Za potrebe Družinskega in mladinskega centra v Cerkljah smo z uporabo storitve Google Drive in Google Koledar ustvarili pisarno v oblaku. Za vse, ki niso vešči uporabe naštetih storitev, smo pripravi...

  17. Izrada 2D video igre za iOS platformu

    OpenAIRE

    Kampuš, Dominik

    2016-01-01

    Tema ovog završnog rada temelji se na izradi 2D video igre za iOS mobilni uređaj te njezinoj demonstraciji na istom. Kroz rad su opisane sve bitne funkcije GameSalad Creator-a koje su potrebne kod izrade igre bazirane na 2 dimenzije. Također se prolazi kroz iOS operativni sustav, što je on i kako se razvijao. Spominje se i tema koja govori općenito o igrama na mobilnim uređajima. U završnom dijelu rada prikazan je postupak izrade, koje funkcije programa se točno koriste i kako se igra može te...

  18. Športsko rekreativne aktivnosti pogodne za bolesnike s osteoporozom

    OpenAIRE

    ŠAKIĆ, Davorin; BADOVINAC, Olga; AMERL-ŠAKIĆ, Vjekoslava

    2000-01-01

    Tjelovježba i povećana tjelesna aktivnost neraskidivi su dio svakog preventivnog ili terapijskog postupka kod osteoporoze. Povećanje snage mišića uz opterećenje vlastitom težinom u uspravnom stavu važan su stimulator izgradnje kosti aksijalnog skeleta, čime se smanjuje rizik od frakture, a istodobno povećava potpora kralješnice i stoga su kolapsi kralješaka manje vjerojatni. Vježbom se povećava koordinacija pokreta i time smanjuje mogućnost pada, povećava sposobnost zaštite od posljedica pada...

  19. Application of MM wave therapy in radiology

    Energy Technology Data Exchange (ETDEWEB)

    Avakian, R.S. [Inst. of Radio Physics & Electronics, Ashtarack (Argentina); Gasparyan, L.V. [Republican Medical Centre Armenia, Yerevan (Argentina)

    1995-12-31

    The authors studied the effects of MM wave electromagnetic radiation influence on patients, affected by X-ray radiation during the reparation works after Chernobyl nuclear power plant exposure. They compared results of treatment of two groups of patients: (1) control group patients received only basis therapy; (2) testing group, 10 patients received basis therapy and MM wave influence. The authors used the wide band noise generator `Artsakh - 2` for local irradiation on the acupuncture points. Their data proved that low intensity MM waves have immunocorrective, antioxidant effects, and MM wave therapy is a perspective method for treatment of patients with radiological pathology.

  20. Spletna aplikacija microCOMB za določanje komponent genske ekspresije

    OpenAIRE

    SKOK, BOŠTJAN

    2017-01-01

    Cilj diplomskega dela je bil izdelati spletno aplikacijo, ki deluje kot grafični vmesnik za uporabnike microCOMB-a in vzdržuje bazo genskih ekspresij. Glavne funkcije aplikacije so omogočiti uporabnikom posredovanje ekspresijskih podatkov v analizo in prikazati njene rezultate, vodenje zgodovine analiz in skrbeti za ažurnost javne baze ekspresijskih podatkov. V delu so opisane uporabljene tehnologije, arhitektura sistema, razvojni proces ter končna funkcionalnost aplikacije. Ob razvoju smo st...

  1. Tehnika za proizvodnju hrane u terenskim uslovima / Technology for food preparation in field conditions

    Directory of Open Access Journals (Sweden)

    Branko M. Tešanović

    2010-10-01

    Full Text Available U terenskim uslovima osnovna sredstva za pripremanje hrane su pokretne kuhinje. One se koriste u miru za vreme izvođenja vežbi, logorovanja, za obuku vojnika kuvara i u vojnim školama za obuku studenata i učenika intendantske službe. Izuzetno, mogu se koristiti za kuvanje jela kada se vojni restorani adaptiraju ili se zbog drugih razloga hrana ne može pripremati u njima. U Vojsci Srbije danas su u upotrebi sledeće vrste pokretnih kuhinja: kuhinja autoprikolica od 250, 200, 300 i 400 l i kuhinja tovarna od 25 l. Za pripremu hrane u terenskim uslovima OS NATO koriste veoma raznovrstan park poljskih tehničkih sredstava. / In field conditions, the basic means for food preparation are mobile kitchens. Mobile kitchens are used in peace time during exercise and camping as well as for training military chefs and students of logistic support in military schools. Exceptionally, they can be used for cooking meals when repairing or adapting military restaurants or for some other valid reasons. In the Army of Serbia today, there are the following types of mobile kitchens: mobile kitchen 250, 200, 300 and 400 l and a kitchen pack of 25 l. For the preparation of food in field conditions, NATO forces use a very versatile choice of field technical resources.

  2. Alloying of titanium by oxygen during chamber electroslag remelting/Legiranje titanijuma kiseonikom u peći za elektropretapanje pod troskom

    Directory of Open Access Journals (Sweden)

    Anatoliy D. Ryabtsev

    2014-10-01

    Full Text Available The paper presents the results of alloying titanium by oxygen in the process of chamber electroslag remelting. As an oxygen-containing ligature, we used the electrodes-satellite from the reaction mass residues mixture from the retort lid for magnesium thermal reduction of a titanium sponge, a specially prepared gaseous argon oxygen mixture containing 30% oxygen applied directly to the melting space, microsize (10-15 mm powder particles of titanium oxide and titanium oxide nanopowder with a particle size of 21 ± 5 nm. The structure and the properties of titanium alloyed by oxygen from the oxygen-containing ligature, gas phase and titanium oxide powder during chamber electroslag remelting of the titanium sponge are investigated. It was found that at the oxygen content of 0.053%mas. to 0.22%mas. in the metal formed a homogeneous single-phase structure typical for commercial titanium formed by polyhedral grains of the α-phase. The increase of the oxygen concentration in titanium for more than 0.22%mas. leads to the formation of the microstructure with a typical needle structure, which allows it to be classified as the α ׳-phase. / U radu su prikazani rezultati legiranja titanijuma kiseonikom u procesu elektropretapanja pod troskom u peći. Za vezivo, koje sadrzi kiseonik, korišćene su satelit elektrode iz reakcije masenih ostataka mešavine iz poklopca retorte za termalnu redukciju magnezijumtitanijumskog sunđera, specijalno pripremljena mešavina gasa argona i kiseonika sa 30% kiseonika primenjena direktno na mesto topljenja, čestice praha titanijum-oksida mikroveličine 10-15mm i nanoprah titanijum-oksida veličine čestica od 21± 5 nm. Ispitane su struktura i karakteristike titanijuma legiranog kiseonikom iz veziva , gasne faze i praha titanijum-oksida tokom elektropretapanja titanijumovog sunđera pod troskom u peći. Utvrđeno je da se pri sadržaju kiseonika od 0.053%mas.do 0.22%mas. u metalu formira homogena jednofazna struktura tipi

  3. MM Algorithms for Geometric and Signomial Programming.

    Science.gov (United States)

    Lange, Kenneth; Zhou, Hua

    2014-02-01

    This paper derives new algorithms for signomial programming, a generalization of geometric programming. The algorithms are based on a generic principle for optimization called the MM algorithm. In this setting, one can apply the geometric-arithmetic mean inequality and a supporting hyperplane inequality to create a surrogate function with parameters separated. Thus, unconstrained signomial programming reduces to a sequence of one-dimensional minimization problems. Simple examples demonstrate that the MM algorithm derived can converge to a boundary point or to one point of a continuum of minimum points. Conditions under which the minimum point is unique or occurs in the interior of parameter space are proved for geometric programming. Convergence to an interior point occurs at a linear rate. Finally, the MM framework easily accommodates equality and inequality constraints of signomial type. For the most important special case, constrained quadratic programming, the MM algorithm involves very simple updates.

  4. Magnetometer Data recovered from 35mm film

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The L57 CDMP recovery project takes magnetometer data on 35mm film stored at the archive's climate controlled warehouse and digitizes them.

  5. Atenica: u potrazi za izgubljenim spalištem

    Directory of Open Access Journals (Sweden)

    Staša Babić

    2016-11-01

    Full Text Available Funerarni konteksti svakako su arheološki zapisi u čijem formiranju značajnu ulogu igraju simboličke i kultne predstave zajednice. S druge strane, u odsustvu pisanih svedočanstava o tim predstavama, arheolozi su skloni da svoje interpretacije zasnivaju na uopštenim i pojednostavljenim idejama o „primitivnim” kultovima, kao što je „solarni kult”. U takvom postupku, tehnički aspekti zapisa zanemaruju se u korist tumačenja pretpostavljenih simboličkih „poruka”. Među kneževskim grobovima centralnog Balkana, humke u Atenici pored Čačka dugo su predstavljale jedini primer ove vrste sahrane koji je istražen u okviru sistematskih arheoloških istraživanja i stoga je čitav niz autora posvećivao posebnu pažnju konstrukciji ovih tumula i mogućnostima interpretacije rituala koji je pratio polaganje pokojnika. U ovom pogledu, naročito je značajna tzv. „ritualna površina” u okviru humke II – tri pravougaona prostora oivičena redovima oblutaka, sa pravilno raspoređenim levkastim jamama, ispunjenim tamnom zemljom, fragmentima keramike i gorelih kostiju. Interpretacije su se kretale od ideja o grobovima kremiranih ljudskih žrtava, preko replika svetilišta, sve do složene simbolike solarnog kulta, izražene numerološkim pravilnostima. S druge strane, budući da se radi o kremiranim pokojnicima, u okviru obe humke identifikovana su spališta – relativno male lučne konstrukcije od redova oblutaka, na kojima su takođe zapaženi tragovi gorenja. Niz praktičnih nelogičnosti koje proističu iz ovih tumačenja ostao je po strani, u nastojanju da se složeni ritual sahrane sa kremacijom poveže sa simboličkim predstavama percipiranim kao primerene za kulturni kontekst sahrana u Atenici – ljudske žrtve, solarni kult. U kružnom dokaznom postupku, ove su ideje, manje ili više prećutno, uzimane za početnu premisu šire interpretacije kultnih praksi zajednice koja je svoje istaknute članove sahranila pod humkama u

  6. »Za nov družbeni red«: genealogija samoupravljanja

    Directory of Open Access Journals (Sweden)

    Cirila Toplak

    2014-07-01

    Full Text Available V prispevku sem predstavila zgodovinski razvoj koncepta samoupravljanja iz političnoekonomske teorije, kot so ga utemeljili utopični socialisti in anarhisti, na primer Pierre Joseph Proudhon (Kaj je lastnina?, 1890, v našem prostoru pa krščanski socialist Andrej Gosar leta 1935 v knjigi Za nov družbeni red. Edvard Kardelj (Smeri razvoja političnega sistema socialističnega samoupravljanja, 1979 je bil nato tvorec zakonodaje, ki je uvedla samoupravljanje v SFRJ v začetku 50. let 20. stoletja. Analizirala sem specifične okoliščine, ki so botrovale odločitvi za uvedbo samoupravljanja v SFRJ, ter razloge za njegov neuspeh oziroma prekinitev implementacije z razpadom Jugoslavije v začetku 90. let. Ocenila sem vpliv jugoslovanskega modela samoupravljanja na druge politične skupnosti v svetu do danes in kaj od tega koncepta je v sodobnosti ostalo oziroma oživelo v Sloveniji. V prispevku sem poskusila odgovoriti na naslednja vprašanja: Zakaj delavsko samoupravljanje v socialistični Sloveniji oziroma Jugoslaviji ni uspelo? Kako je mogoče koncept samoupravljanja misliti in reaktualizirati v sodobnem slovenskem politično-ekonomskem kontekstu? Ali avtonomizem, ki je ena izmed teoretskih podlag samoupravljanja, lahko konstituira učinkovito alternativo oziroma grožnjo neoliberalnemu globalnemu kapitalizmu?

  7. Annual report of the maintenance division for 1965; Godisnji izvestaj Odelenja odrzavanja za 1965. g

    Energy Technology Data Exchange (ETDEWEB)

    Nikolic, M [Reaktor RA, Odelenje odrzavanja, Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1965-12-15

    The personnel of the Division is organized in groups, each responsible for a number of tasks related to maintenance of reactor mechanical structures, electric equipment, electronic equipment. According to the action plan for 1965 the division for RA reactor maintenance the main activities were: planned maintenance of the reactor components, planned repair of the main components, indispensable repairs during reactor operation, repair during planned shutdown periods and tasks related to improvement of operation components and systems. Quite a significant number of failures was related to electronic equipment resulting from failures of thermometers in the heavy water system due to vibrations of the pumps. A number of spare parts and tools were produced needed for maintenance of reactor components, as well as instruments for control and calibration of reactor measuring devices. [Serbo-Croat] Odelenje odrzavanja reaktora RA organizovano je po grupama, od kojih je svaka odgovorna za odrzavanje pojedinih delova sistema: masinske opreme, elektricne opreme, elektronskih uredjaja. Prema planu rada za 1965. godinu Odelenja za odrzavanje reaktora RA osnovne aktivnosti bile su: planirano odrzavanje komponenti reaktora, planirane popravke osnovnih komponenti, neodlozne popravke tokom eksploatacije i u toku planiranih zaustavljanja kao i usavrsavanje opreme i sistema. Znatan broj kvarova pojavio se na elektronskoj opremi usled kvarova termometara u sistemu teske vode usled vibracija koje izazivaju pumpe. Odredjeni broj delova izradjen je za potrebe odrzavanja komponenti reaktora, kao i instrumenata za kontrolu i kalibraciju mernih uredjaja.

  8. Naknada štete za onečišćenje mora iz kopnenih izvora

    Directory of Open Access Journals (Sweden)

    Axel Luttenberger

    2004-08-01

    Full Text Available Rad obrađuje složenu pravnu problematiku onečišćenja mora iz izvora na kopnu uz analizu odredaba Konvencije UN-a o pravu mora, Konvencije o sprečavanju onečišćenja iz izvora na kopnu, te Protokola o zaštiti Sredozemlja protiv onečišćenja iz kopnenih izvora i djelatnosti. Kao domaći izvori, rješenja Ustava i Deklaracije o zaštiti okoliša, te sustav zakona o zaštiti prirode i drugih ekoloških zakona, uz posebni naglasak na rješenja iz područja pomorstva. Naglašava se da je svrha regulative u propisivanju uređenja okoliša i načina obavljanja pojedinih djelatnosti, zajedno sa sustavom nadzora onečišćenja i sankcijama za nepridržavanje normi. Napominje se da je potrebno usvojiti propise tek nakon razmatranja stvarne mogućnosti primjene s odnosnim preventivnim mjerama i postupcima nakon nastupa štetnog događaja. Također se predlaže uspostava specijaliziranih neovisnih agencija zaduženih za nadzor oživotvorenja propisa.

  9. Poklicna izgorelost ali zavzetost za delo, to je zdaj vprašanje Osebni in skupinski izobraževalni moduli za preprečevanje poklicne izgorelosti (2. del

    Directory of Open Access Journals (Sweden)

    Andreja Pšeničny

    2005-12-01

    Full Text Available Raziskavo sta avtorici posvetili preucevanju potreb po varovanju zaposlenih pred poklicno izgorelostjo, hkrati pa tudi spodbujanju njihove zavzetosti za delo. Podjetje, ki se zaveda pomena svojih virov, lahko v enem in drugem primeru s podobnimi izobrazevalnimi vsebinami in postopki oplemeniti svoj najpomembnejsi vir ljudi. Avtorici ugotavljata, da v zvezi s poklicno izgorelostjo danes ni vec poudarek na preucevanju osebnostnih lastnosti za delo »preveč« vnetih ljudi, marvec predvsem na proucevanju delovnega okolja in psiholoških delovnih okolisCin v podjetju. Poklicno izgorelost lahko prepreCimo tudi z znanstveno utemeljeno organiziranostjo podjetja ali ustanove; taksno, ki spodbuja formalne in neformalne komunikacijske okoliscine, pozitivne medsebojne in kolektivne odnose ter druge ugodne psihološke delovne okoliscine. Izobrazevanje za prepoznavanje in preprečevanje poklicne izgorelosti na eni strani ter izobrazevanje za spodbujanje zavzetosti za delo na drugi strani je posvečeno posameznikom, podjetjem, strokovni in široki javnosti.

  10. Microeconomics of 300-mm process module control

    Science.gov (United States)

    Monahan, Kevin M.; Chatterjee, Arun K.; Falessi, Georges; Levy, Ady; Stoller, Meryl D.

    2001-08-01

    Simple microeconomic models that directly link metrology, yield, and profitability are rare or non-existent. In this work, we validate and apply such a model. Using a small number of input parameters, we explain current yield management practices in 200 mm factories. The model is then used to extrapolate requirements for 300 mm factories, including the impact of simultaneous technology transitions to 130nm lithography and integrated metrology. To support our conclusions, we use examples relevant to factory-wide photo module control.

  11. Potential and profile experiments in MM-4

    International Nuclear Information System (INIS)

    Tian Zhongyu; Ming Linzhou; Feng Xiaozhen; Feng Chuntang; Yin Youjun; Liu Yuhua; Wang Jihai

    1988-01-01

    Experimental results in MM-4 are presented. These results show that there were double potential wells and double ion temperatures in the plasma. The mechanism giving rise to such potential profiles can be attributed to the Stormer region in the cusp system and the different operation regimes of the electron gun used. The measured plasma potential was about - 200 - 300V

  12. Upajmo si biti starši. Praktično delovanje dveh sol za starše

    Directory of Open Access Journals (Sweden)

    Andreja Jereb

    2005-12-01

    Full Text Available V prispevku predstavljam dva primera uspdne prakse sole za starSe. Prvi zasluzi pozornost, ker zajema vse potrebne vsebine za ozavdcanje starsev o kompleksnosti in konfliktnosti odnosov v druzini tako med zakoncema kot tudi med starsi in mladostniki. Program je pripravljen sistematicno, sreeanja so strukturirana in privlacna za starSe mladostnikov, ki marsikatero tezavo iz doma prepoznajo v stevilnih primerih iger vlog. Drugi, spanski primer, zasluzi pozornost predvsem zaradi aktivne vloge starsev pri pripravi na sreeanje, z leti vedno aktivnejSe vloge na srecanjih in v pogovorih v druZini, zaradi cesar je precej zahteven tako za voditelja kot za starSe, a sodee po izjavah starsev iskana in uspdna metoda dela s starsi.

  13. Atomic Energy Research working group a on improvement extension and validation of parametrized FEW-group libraries for WWER-440 and WWER-1000

    International Nuclear Information System (INIS)

    Svarny, J.

    1998-01-01

    The AER Working Groups A and B held its sixth meeting at SKODA JS, Plzen in April 28 and 29, 1998. There were altogether 13 participants from 6 member organizations. The list of participants and the list of papers are attached. (Author)

  14. Behavior of antimony isotopes in the primary coolant of WWER-1000-type nuclear reactors in NPP Kozloduy during operation and shutdown

    International Nuclear Information System (INIS)

    Dobrevski, Ivan D.; Zaharieva, Neli N.; Minkova, Katia F.; Gerchev, Nikolay B.

    2009-01-01

    This paper focuses on the behavior of the antimony isotopes 122 Sb and 124 Sb in the coolant of the WWER reactors in the nuclear power plant Kozloduy (Bulgaria) during operation and shutdown. It is concluded that the chemical properties of their actual precursor, the isotope 121 Sb, determine the behavior of 122 Sb and 124 Sb during operation, load fluctuations, and shutdown as well as during the reactor coolant purification process. It is supposed that differences between the reactor bulk and the core fuel cladding surface chemistry as well as the presence of sub-cooled nucleate boiling at the fuel cladding may create conditions under which a local oxidizing environment may come into existence. (orig.)

  15. IMPACT OF THE CHEMICAL FORM OF IN-CONTAINMENT SOURCE ON FISSION PRODUCT RELEASE FROM WWER-1000/V-320 TYPE NPP CONTAINMENT DURING LOCA

    Directory of Open Access Journals (Sweden)

    Adam Kecek

    2016-12-01

    Full Text Available Nuclear power plant accidents may be followed by a release of fission products into the environment. This release is dependent on several phenomena, such as chemistry, pressure, type of the accident etc. The aim of this paper is to assess the impact of the chemical form of iodine on the fission product release into the environment.

  16. Assessment of realization possibility of borate-lithium water chemical regime of the PGV-100 secondary circuit for NPP with WWER-1000 type reactor

    International Nuclear Information System (INIS)

    Smykov, V.B.; Ermolaev, N.P.; Borzov, I.A.

    1994-01-01

    The theoretical and experimental assessment of chemical equilibrium reactions resulting in the weak-alkaline boric buffering water chemistry of secondary side PGV-1000 has been performed out in the article. 18 refs

  17. To the question on vibration strength of the main circulating pumps of reactor WWER-1000 at influence of the non-stationary hydrodynamic stream

    International Nuclear Information System (INIS)

    Pukhlij, V.A.

    2015-01-01

    The problem of vibration strength of working shovels of centrifugal pumps is based on definition of dynamic behaviour of shovels on the basis of the theory of flat covers, thus integration of the initial equations of movement is carried out by the modified method consecutive approach. The problem of forced and natural fluctuations of a shovel is solved, which makes it possible to identify the resonant zones of operation of centrifugal pumps of nuclear power, in particular, the main circulation pump GTSN 195M [ru

  18. The Testing of Fuel Rod Models with Zr1Nb Alloy Cladding in Water Vapor at Temperature of Hypothetical Accident Situation in WWER-1000 Type Reactors

    International Nuclear Information System (INIS)

    Krasnorutsky, V.S.; Petel'guzov, I.A.; Gritsina, V.M.; Rodak, A.G.; Belash, N.N.; Yakovlev, V.K.

    2006-01-01

    In the article happen to results of testing the fuel rod models, their welded joints, changing the mechanical characteristics of shells of models from experimental parties of pipes from Zr1Nb alloy (Zr+1 mass%Nb) at heating of models, pervaded helium before pressures, using in earned one's living fuel rods (2,2 MPa), before the temperature 770 degree C and above occurs an overblown fuels, but at temperature 820...830 degree C shells can be broken at the expense of pressure of warming gas. Swept away reduction plasticity and embrittlement shells after the heating under temperature of 900...1200 degree C and cooling before room temperature pipes-shells from Zr1Nb alloy and from the staff alloy E110

  19. RA Research reactor, Annual report 1988; Istrazivacki nuklearni reaktor RA - Izvestaj za 1988. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1988-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  20. Research nuclear reactor RA - Annual Report 1989; Istrazivacki nuklearni reaktor RA - Izvestaj za 1989. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1989, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1989. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjering RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  1. Patentna zaštita poverljivih pronalazaka / Patent protection of classified invention

    Directory of Open Access Journals (Sweden)

    Obrad T. Čabarkapa

    2008-10-01

    Full Text Available Svaki pronalazak za koji se utvrdi da je značajan za odbranu i bezbednost Republike Srbije smatra se poverljivim. Za patentnu zaštitu poverljivih pronalazaka podnosi se prijava organu nadležnom za poslove odbrane, koji ima isključivo pravo da raspolaže poverljivim pronalascima1. U organizacijskoj jedinici nadležnoj za poslove naučne i inovacione delatnosti2 realizuje postupak ispitivanja poverljivih prijava patenata. Da bi se donela ocena o poverljivosti prijavljenog pronalaska neophodno je realizovati određene faze u postupku ispitivanja prijave. Poverljivi pronalazak se ne objavljuje, a pronalazač, nakon priznavanja patenta, u skladu sa zakonskim propisima, ima određena moralna i materijalna prava. / Every invention established to be of significance for defense or security of the Republic of Serbia is considered to be a classified invention. For the purpose of patent protection of classified inventions, a confidential application must be submitted to a relevant defense authority having the exclusive right to deal with classified inventions3. An organizational unit competent for scientific and innovation issues carries out the examination of classified patent applications. In order to evaluate classification of the submitted invention, regarding its significance for defense or security of the country as well as to make the final decision on the application, the examination procedure should be carried out through several phases. A classified invention is not to be published and once the patent has been approved, the inventor enjoys moral and material rights in accordance with law.

  2. Zaštita računarskih mreža / Protection of computer networks

    Directory of Open Access Journals (Sweden)

    Milojko Jevtović

    2005-09-01

    Full Text Available U radu su obrađene metode napada, oblici ugrožavanja i vrste pretnji kojima su izložene računarske mreže, kao i moguće metode i tehnička rešenja za zaštitu mreža. Analizirani su efekti pretnji kojima mogu biti izložene računarske mreže i informacije koje se preko njih prenose. Opisana su određena tehnička rešenja koja obezbeđuju potreban nivo zaštite računarskih mreža, kao i mere za zaštitu informacija koje se preko njih prenose. Navedeni su standardi koji se odnose na metode i procedure kriptozaštite informacija u računarskim mrežama. U radu je naveden primer zaštite jedne lokalne računarske mreže. / In this paper different methods of attacks, threats and different forms of dangers to the computer networks are described. The possible models and technical solutions for networks protection are also given. The effects of threats directed to the computer networks and their information are analyzed certain technical solutions that provide necessary protection level of the computer networks as well as measures for information protection are also described. The standards for methods and security procedure for the information in computer networks are enlisted. There is also an example of protecting one local data network (in this paper.

  3. OBVLADOVANJE STRESA NA DELOVNEM MESTU OPERATERJA V REGIJSKEM CENTRU ZA OBVEŠČANJE

    OpenAIRE

    Piškur, Luka

    2016-01-01

    Hiter življenjski tempo sodobne družbe nas je v zadnjih letih privedel do tega, da ne najdemo kvalitetnega časa sami zase. Poslužujemo se nekvalitetne prehrane, ne najdemo časa za počitek, preplavljajo nas negativne misli in čustva. Tako doma kot na delovnem mestu se soočamo s frustracijami, roki in zahtevami, za katere se večina od nas sploh ne zaveda, kako stresni so. S prepoznavanjem simptomov stresa lahko naredimo prvi korak k temu, da izboljšamo kvaliteto našega življenja. Cilj diplo...

  4. Strateški marketing za popularizacijo ritmične gimnastike

    OpenAIRE

    Möderndorfer, Tjaša

    2018-01-01

    Uvodoma smo predstavili in preučili ključne pojme za lažje razumevanje trženjskih osnov. V nadaljevanju predstavimo metode in tehnike, ki nam pomagajo pri raziskovanju in posledično pri določanju trga in ciljev. Predstavljeni so nekateri osnovni modeli, ki nam pomagajo razumeti, kako trg deluje in kaj vse vpliva nanj. Naša tema se nanaša na šport, zato si v nadaljevanju pogledamo delovanje športnih organizacij. Za pripravo strategije trženja pregledamo okolje in vse deležnike, ki so pos...

  5. Arhitektonsko vrednovanje višestambenih zgrada i stanova za zbrinjavanje stradalnika Domovinskog rata

    OpenAIRE

    Homadovski, Aleksandar; Rogić, Ivan

    1999-01-01

    Arhitektonskim vrednovanjem stanova, zgrada i okoliša obuhvaćene su ove sastavnice programa za stambeno zbrinjavanje stradalnika Domovinskog rata: organizacija stana s rasporedom prostorija, kakvoćom izrade i položajem stana u zgradi, ekonomska vrijednost stana te teže prihvatljiva rješenja za korisnike koja se odnose na sadržaj, kakvoću i okolinu stana. Zaključuje se kako su u provedbi modeli stambenog zbrinjavanja različitih nositelja izgradnje pokazali kvalitativne različitosti te uputili ...

  6. RAZVOJ APLIKACIJE ZA UPRAVLJANJE SLIK IN ALBUMOV NA MOBILNI PLATFORMI ANDROID

    OpenAIRE

    Kupnik, Domen

    2012-01-01

    V okviru diplomske naloge smo izdelali mobilno aplikacijo na operacijskem sistemu Android OS za upravljanje slik in albumov. V teoretičnem delu smo najprej predstavili že obstoječe podobne aplikacije. Nato smo se seznanili z arhitekturo operacijskega sistema Android OS in s kompletom za razvijanje aplikacij Android SDK. V nadaljevanju sledi še predstavitev lokacijskega podsistema Google Map ter podrobnejši opis uporabljenih funkcionalnosti. V praktičnem delu prikažemo implementacijo aplikacij...

  7. PRIMERJAVA POROČIL ZA VODENJE INFORMATIKE COBIT 4.1 IN COBIT 5

    OpenAIRE

    Štagar, Darja

    2012-01-01

    V diplomskem delu smo predstavili področja upravljanja informatike, ki jih je za uspešno poslovanje potrebno upravljati organizirano. Priporočljiva je uporaba različnih standardov in priporočil, zato smo v delu predstavili nekatere standarde in priporočila, ki to omogočajo. Glavna tema te naloge so priporočila za vodenje informatike CobIT, ki smo jih tudi podrobneje predstavili. Obravnavali smo zadnji dve različici, CobIT 4.1 in CobIT 5. Ker sta si med seboj bistveno različni, smo ju primerja...

  8. Razvoj i primena hemometrijskih metoda za klasifikaciju i procenu kvaliteta vode

    OpenAIRE

    Živojinović, Dragana Z.

    2013-01-01

    Savremeno društvo karakteriše intenzivna industrijalizacija i urbanizacija, što ima za posledicu sve obimnije iscrpljivanje prirodnih resursa i sve opasnije ugrožavanje životne sredine. U uslovima globalnog razvoja, briga o vodi predstavlja pitanje opstanka civilizacije. Stoga upravljanje vodama i kontrola kvaliteta voda postaju suštinska društvena potreba. Timovi stručnjaka iz različitih oblasti pokušavaju da nađu obrasce i modele za modelovanje parametara kvaliteta vode i pre...

  9. ODABIR I TRENING SENZORSKOG PANELA ZA PROCJENU TRPKOĆE VINA

    OpenAIRE

    Horvat, Sandra

    2016-01-01

    Trpkoća je taktilni osjet vina koji definiramo kao osjet suhoće u ustima te neugodan i grub osjet skupljanja i stezanja tkiva u usnoj šupljini. Kondenzirani tanini (proantocijanidini) su polifenolni spojevi odgovorni za senzorsko svojstvo trpkoće. U ovom radu proveden je razvoj i trening panela za kvantitativnu deskriptivnu analizu (QDA) intenziteta trpkoće vina numeriĉkom skalom od 0 do 7. Selekcija i trening kušaĉa provedeni su primjenom triangl, ranking testova i testova QDA, a kao referen...

  10. Razvoj i validacija metode za određivanje fosfolipida u sojinom ulju

    OpenAIRE

    Rogulj, Ivana

    2016-01-01

    Trpkoća je taktilni osjet vina koji definiramo kao osjet suhoće u ustima te neugodan i grub osjet skupljanja i stezanja tkiva u usnoj šupljini. Kondenzirani tanini (proantocijanidini) su polifenolni spojevi odgovorni za senzorsko svojstvo trpkoće. U ovom radu proveden je razvoj i trening panela za kvantitativnu deskriptivnu analizu (QDA) intenziteta trpkoće vina numeriĉkom skalom od 0 do 7. Selekcija i trening kušaĉa provedeni su primjenom triangl, ranking testova i testova QDA, a kao referen...

  11. APLIKACIJA ZA PRIKAZ SLEDENJA VOZIL NA OPERACIJSKEM SISTEMU iOS

    OpenAIRE

    Mlinar, Tilen

    2011-01-01

    V diplomski nalogi prikazujemo razvoj aplikacije za operacijski sistem iOS. Razvili smo aplikacijo za sledenje vozil. V teoretičnem delu se najprej seznanimo z operacijskim sistemom iOS ter njegovo arhitekturo, nato predstavimo arhitekturo aplikacij iOS. Sledi opis kompleta razvojnih orodij v iOS SDK. V nadaljevanju se seznanimo še s programskim jezikom Objective-C, lokacijsko odvisnimi storitvam, podsistemom MapKit in delovanjem aplikacije v ozadju operacijskega sistema. V praktičnem delu op...

  12. KONSTRUIRANJE PRIPRAVE ZA VPENJANJE VPENJALNE GLAVE VEČOSNEGA STRUŽNEGA STROJA

    OpenAIRE

    Rupnik, Damijan

    2010-01-01

    V diplomskem delu sem skonstruiral pripravo za vpenjanje vpenjalne glave večosnega stružnega stroja. Ta priprava bo služila za prevoz in vpenjanje vpenjalne glave večosnega stružnega stroja EMAG REINECKER VSC 250 DS. Najprej sem si zamislil, kako naj bi naprava izgledala, nato pa sem s pomočjo sodobnih inženirskih metod (MKE metod, optimiranja) naredil različne preračune in simulacije, če bo naprava stabilna in gibljiva, zatem pa sem se lotil konstruiranja priprave. Če bo konstruiranje pripra...

  13. VODENJE PROJEKTOV VIRTUALNIH SKUPIN V VIRTUALNIH SKUPNOSTIH ZA ODPRTOKODNI RAZVOJ PROGRAMSKIH REŠITEV

    OpenAIRE

    Harej Pulko, Katja

    2009-01-01

    S prihodom interneta, se je spremenil način povezovanja in komunikacije med ljudmi. Pred tem smo lahko s sogovornikom komunicirali le preko stacionarnega telefona, pisem ali, če smo se z osebo srečali »v živo«. Nato so postale aktualne video konference, mobilni telefoni in internet. Danes se zdi, da gre čas hitreje. A vendarle hitrost časa ostaja enaka. Le komunikacija je lahko bolj dinamična, več možnosti imamo za sodelovanje in povezovanje, tudi z ljudmi na drugi strani sveta. Za komunikaci...

  14. Trening za razvijanje občutka za števila in količine pri predšolskih otrocih s posebnimi potrebami

    OpenAIRE

    Kuplenk, Petra

    2017-01-01

    Tako otroci kot tudi odrasli se z matematiko srečujemo na vsakem koraku, pa naj bo to na poti v vrtec, službo ali pa pri delu doma. Matematika vsakodnevno vpliva na naše življenje in delo. Na delovnem mestu, v vrtcu, opažam vse večje težave otrok s posebnimi potrebami na področju razvoja občutka za števila in količine. V predšolskem obdobju je namreč nujno, da otroci razvijejo občutek za števila in količine, saj vsa nadaljnja matematična znanja temeljijo na usvojenih spretnostih. V empirič...

  15. X-ray analytics for 450-mm wafer; Roentgenanalytik fuer 450-mm-Wafer

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2014-09-15

    The introduction of the 450-mm technology in the wafer fabrication and the further reduction of critical dimensions requires improved X-ray analysis methods. Therefor the PTB has concipated a metrology chamber for the characterization of 450-mm wafers, the crucial element of which is a multi-axis patent-pending manipulator.

  16. 29 mm Diameter Target Test Report

    Energy Technology Data Exchange (ETDEWEB)

    Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Olivas, Eric Richard [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dale, Gregory E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Angela Carol [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Romero, Frank Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chemerisov, Sergey [Argonne National Lab. (ANL), Argonne, IL (United States); Gromov, Roman [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-10-23

    After numerous delays, the test of the 29 mm diameter target was conducted on 8/18/2017. The complete target design report, dated 8/15/2016, is reproduced below for completeness. This describes in detail the 10 disk target with varying thickness disks. The report presents and discusses the test results. In brief summary, there appears to have been multiple instrumentation errors. Measured temperatures, pressures and IR camera window temperature measurement are all suspect. All tests were done at 35 MeV, with 171 μA current, or 6 kW of beam power.

  17. Značilnosti izobraževalne ponudbe za odrasle

    Directory of Open Access Journals (Sweden)

    Colin Titmus

    1995-12-01

    Full Text Available Poskušal sem predstaviti vso raznovrstnost izobraževalne ponudbe za odrasle. Ta je tako velika in raznovrstna, da se včasih in ponekod zdi, da so na voljo možnosti in priložnosti, ki lahko ustrežejo vsaki zahtevi po znanju, ki si jo le lahko zamislimo. In ne le to, očitno obstajajo tudi prepričljivi razlogi za začetek takega študija. Kljub temu pa se je v poljubnem letu tudi v državah, kjer imajo najvišjo stopnjo udeležbe, na primer na Švedskem in v ZDA, le manjšina odraslih vključila v nek strukturiran program namenskega učenja, ki je na voljo. Velik delež ljudi se nikoli ne odloči, da bi sodelovali v izobraževalnem programu za odrasle.

  18. RA research nuclear reactor - Annual report 1985; Istrazivacki nuklearni reaktor RA - Izvestaj za 1985. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1985 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  19. RA Research reactor, Annual report 1986; Istrazivacki nuklearni reaktor RA - Izvestaj za 1986. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1986-12-01

    Research reactor RA Annual report for year 1985 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1986 godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  20. Presidendi peolaua katavad Roman Zaštšerinski ja Imre Kose / Kristi Leppik

    Index Scriptorium Estoniae

    Leppik, Kristi

    2008-01-01

    Vt. ka Postimees : na russkom jazõke 14. veebr. 2008, lk. 2. Eesti Vabariigi aastapäeva presidendi vastuvõtu peakokad on restorani Ö peakokk Roman Zaštšerinski ja Imre Kose. Vt. samas: Retseptisoovitus 24. veebruariks

  1. Česká literatura a kultura za protektorátu

    Czech Academy of Sciences Publication Activity Database

    Piorecký, Karel

    2017-01-01

    Roč. 65, č. 3 (2017), s. 482-485 ISSN 0009-0468. [Česká literatura a kultura za protektorátu. Ostrava, 24.11.2016-25.11.2016] Institutional support: RVO:68378068 Keywords : Czech literature * 1938-1945 Subject RIV: AJ - Letters, Mass-media, Audiovision

  2. Analiza učinkovitosti učenja strojnika na stroju za sečnjo

    OpenAIRE

    Pezdevšek Malovrh, Špela; Košir, Boštjan; Krč, Janez

    2004-01-01

    Članek obravnava načine učenja bodočih strojnikov za delo s strojem za sečnjo.Na prvem takšnem primeru v Sloveniji je opisan in analiziran potek učenja s simulatorjem in merjeni so časi posameznih postopkov pri dveh kandidatih. Opisano je delovanje simulatorja za učenje na stroju Timberjack 1270 D in potek enotedenskega tečaja. Narejena je primerjava med kandidatoma glede porabe časa in števila poškodb na virtualnem stroju in sestoju, ki jih je beležil program simulatorja. Podane so usmeritve...

  3. Coordinated mm/sub-mm observations of Sagittarius A* in May 2007

    Energy Technology Data Exchange (ETDEWEB)

    Kunneriath, D; Eckart, A; Bertram, T; Konig, S [University of Cologne, Zuelpicher Str. 77, D-50937 Cologne (Germany); Vogel, S [Department of Astronomy, University of Maryland, College Park, MD 20742-2421 (United States); Sjouwerman, L [National Radio Astronomy Observatory, PO Box 0, Socorro, NM 87801 (United States); Wiesemeyer, H [IRAM, Avenida Divina Pastora, 7, Nuecleo Central, E-18012 Granada (Spain); Schoedel, R [Instituto de AstrofIsica de AndalucIa, Camino Bajo de Huetor 50, 18008 Granada (Spain); Baganoff, F K [Center for Space Research, Massachusetts Institute of Technology, Cambridge, MA 02139-4307 (United States); Morris, M; Mauerhan, J; Meyer, L [Department of Physics and Astronomy, University of California, Los Angeles, CA 90095-1547 (United States); Dovciak, M; Karas, V [Astronomical Institute, Academy of Sciences, BocnI II, CZ-14131 Prague (Czech Republic); Dowries, D [Institut de Radio Astronomie Millimetrique, Domaine Universitaire, 38406 St. Martin d' Heres (France); Krichbaum, T; Lu, R-S [Max-Planck-Institut fuer Radioastronomie, Auf dem Huegel 69, 53121 Bonn (Germany); Krips, M [Harvard-Smithsonian Center for Astrophysics, SMA project, 60 Garden Street, MS 78 Cambridge, MA 02138 (United States); Markoff, S [Astronomical Institute ' Anton Pannekoek' , University of Amsterdam, Kruislaan 403, 1098SJ Amsterdam (Netherlands); Duschl, W J, E-mail: eckart@phl.uni-koeln.de (and others)

    2008-10-15

    At the center of the Milky Way, with a distance of {approx}8 kpc, the compact source Sagittarius A* (SgrA*) can be associated with a super massive black hole of {approx}4x 10{sup 6}M{sub o-dot}. SgrA* shows strong variability from the radio to the X-ray wavelength domains. Here we report on simultaneous NIR/sub-millimeter/X-ray observations from May 2007 that involved the NACO adaptive optics (AO) instrument at the European Southern Observatory's Very Large Telescope, the Australian Telescope Compact Array (ATCA), the US mm-array CARMA, the IRAM 30m mm-telescope, and other telescopes. We concentrate on the time series of mm/sub-mm data from CARMA, ATCA, and the MAMBO bolometer at the IRAM 30m telescope.

  4. Transportation studies: 40-MM collider dipole magnets

    International Nuclear Information System (INIS)

    Daly, E.

    1992-01-01

    Several fully functional 40-mm Collider Dipole Magnets (CDM) were instrumented with accelerometers to monitor shock and vibration loads during transport. The magnets were measured with optical tooling telescopes before and after transport. Changes in mechanical alignment due to shipping and handling were determined. The mechanical stability of the cryogen lines were checked using the same method. Field quality and dipole angle were measured warm before and after transport to determine changes in these parameters. Power spectra were calculated for accelerometers located on the cold mass, vacuum vessel, and trailer bed. Where available, plots of field quality and dipole roll both before and after were created. Shipping loads measured were largest in the vertical direction, where most of the structural deformation of the magnet was evident. It was not clear that magnetic performance was affected by the shipping and handling environment

  5. PRIVLAČNOST FRANŠIZNEGA KONCEPTA ZA KOZMETIČNE SALONE PODJETJA KOZMETIKA AFRODITA D.O.O.

    OpenAIRE

    Mijošek, Ivo

    2013-01-01

    Delo diplomskega seminarja se osredotoča na zgodovinski razvoj franšiznega koncepta, njegove različne oblike ter ključne pravice in dolžnosti, ki jih potencialni franšizij pridobi z odločitvijo za franšizo. Nadalje teoretični del seminarja opisuje ključne sestavine vsake franšizne pogodbe ter se osredotoča na prednosti ter slabosti franšiznega koncepta, tako za franšizorja kot za franšizija. Ključni prednosti za franšizorja sta hitra prisotnost na več tujih trgih ter deljena odgovornost na po...

  6. Simulation of Thermal Processes in Metamaterial MM-to-IR Converter for MM-wave Imager

    International Nuclear Information System (INIS)

    Zagubisalo, Peter S; Paulish, Andrey G; Kuznetsov, Sergey A

    2014-01-01

    The main characteristics of MM-wave image detector were simulated by means of accurate numerical modelling of thermophysical processes in a metamaterial MM-to-IR converter. The converter represents a multilayer structure consisting of an ultra thin resonant metamaterial absorber and a perfect emissive layer. The absorber consists of a dielectric self-supporting film that is metallized from both sides. A micro-pattern is fabricated from one side. Resonant absorption of the MM waves induces the converter heating that yields enhancement of IR emission from the emissive layer. IR emission is detected by IR camera. In this contribution an accurate numerical model for simulation of the thermal processes in the converter structure was created by using COMSOL Multiphysics software. The simulation results are in a good agreement with experimental results that validates the model. The simulation shows that the real time operation is provided for the converter thickness less than 3 micrometers and time response can be improved by decreasing of the converter thickness. The energy conversion efficiency of MM waves into IR radiation is over 80%. The converter temperature increase is a linear function of a MM-wave radiation power within three orders of the dynamic range. The blooming effect and ways of its reducing are also discussed. The model allows us to choose the ways of converter structure optimization and improvement of image detector parameters

  7. Buccal mucosa carcinoma: surgical margin less than 3 mm, not 5 mm, predicts locoregional recurrence

    Directory of Open Access Journals (Sweden)

    Chiou Wen-Yen

    2010-09-01

    Full Text Available Abstract Background Most treatment failure of buccal mucosal cancer post surgery is locoregional recurrence. We tried to figure out how close the surgical margin being unsafe and needed further adjuvant treatment. Methods Between August 2000 and June 2008, a total of 110 patients with buccal mucosa carcinoma (25 with stage I, 31 with stage II, 11 with stage III, and 43 with Stage IV classified according to the American Joint Committee on Cancer 6th edition were treated with surgery alone (n = 32, surgery plus postoperative radiotherapy (n = 38 or surgery plus adjuvant concurrent chemoradiotherapy (n = 40. Main outcome measures: The primary endpoint was locoregional disease control. Results The median follow-up time at analysis was 25 months (range, 4-104 months. The 3-year locoregional control rates were significantly different when a 3-mm surgical margin (≤3 versus >3 mm, 71% versus 95%, p = 0.04 but not a 5-mm margin (75% versus 92%, p = 0.22 was used as the cut-off level. We also found a quantitative correlation between surgical margin and locoregional failure (hazard ratio, 2.16; 95% confidence interval, 1.14 - 4.11; p = 0.019. Multivariate analysis identified pN classification and surgical margin as independent factors affecting disease-free survival and locoregional control. Conclusions Narrow surgical margin ≤3 mm, but not 5 mm, is associated with high risk for locoregional recurrence of buccal mucosa carcinoma. More aggressive treatment after surgery is suggested.

  8. Buccal mucosa carcinoma: surgical margin less than 3 mm, not 5 mm, predicts locoregional recurrence

    International Nuclear Information System (INIS)

    Chiou, Wen-Yen; Hung, Shih-Kai; Lin, Hon-Yi; Hsu, Feng-Chun; Lee, Moon-Sing; Ho, Hsu-Chueh; Su, Yu-Chieh; Lee, Ching-Chih; Hsieh, Chen-Hsi; Wang, Yao-Ching

    2010-01-01

    Most treatment failure of buccal mucosal cancer post surgery is locoregional recurrence. We tried to figure out how close the surgical margin being unsafe and needed further adjuvant treatment. Between August 2000 and June 2008, a total of 110 patients with buccal mucosa carcinoma (25 with stage I, 31 with stage II, 11 with stage III, and 43 with Stage IV classified according to the American Joint Committee on Cancer 6 th edition) were treated with surgery alone (n = 32), surgery plus postoperative radiotherapy (n = 38) or surgery plus adjuvant concurrent chemoradiotherapy (n = 40). Main outcome measures: The primary endpoint was locoregional disease control. The median follow-up time at analysis was 25 months (range, 4-104 months). The 3-year locoregional control rates were significantly different when a 3-mm surgical margin (≤3 versus >3 mm, 71% versus 95%, p = 0.04) but not a 5-mm margin (75% versus 92%, p = 0.22) was used as the cut-off level. We also found a quantitative correlation between surgical margin and locoregional failure (hazard ratio, 2.16; 95% confidence interval, 1.14 - 4.11; p = 0.019). Multivariate analysis identified pN classification and surgical margin as independent factors affecting disease-free survival and locoregional control. Narrow surgical margin ≤3 mm, but not 5 mm, is associated with high risk for locoregional recurrence of buccal mucosa carcinoma. More aggressive treatment after surgery is suggested

  9. Prijedlog dorade pravnog režima za nautički turizam radi podizanja njegove konkurentnosti

    Directory of Open Access Journals (Sweden)

    Petar Kragić

    2018-02-01

    Full Text Available Cilj rada je predložiti određene dorade u domaćem pravnom režimu za nautički turizam radi podizanja njegove konkurentnosti. Pomorskopravni odnosi su specifični zbog međunarodnog karaktera plovidbe i konkurencije pravnih režima više država u uređenju pravnih odnosa koji proističu iz plovidbe. Zato, sugerira autor, za ocjenu da li je neka država pomorska nije odlučna dužina ili razvedenost njene obale, već da li njena vlada razumije specifične odnose vezane za pomorstvo i da li ih uređuje na način koji omogućuje razvoj pomorske privrede. Europska unija je prepoznala specifičnost pomorstva i dopustila svojim članicama da urede porezni sustav za brodarstvo drugačije od općeg poreznog sustava. Sada bi, drži autor, poseban sustav za uređenje nautičkog turizma trebalo kreirati i za jahte, u kojem niz odnosa – vezanih za tu djelatnost – treba urediti drugačije od općih odredbi. Sve to u cilju podizanja konkurentnosti hrvatskog nautičkog turizma, koji se bori na tržištu Sredozemlja s drugim, posebice za velike jahte, vrlo atraktivnim destinacijama. U radu se obrađuju administrativne procedure; kabotaža u uvjetima članstva u Europskoj uniji; porez na dodanu vrijednost na najamninu jahti; boravak posade jahti u Hrvatskoj; porezi na dohodak i doprinosi članova posade jahte; porez po tonaži i privremeni uvoz jahti. Posebice se razmatra članstvo Hrvatske u Europskoj uniji koje donosi prilike, ali i nameće ograničenja za standardne mjere protekcionizma i intervencionizma koje su povijesno koristile zemlje u razvoju da dostignu one razvijene. Ovaj je rad dio prijedloga većeg zahvata u zakonodavstvo za izmjenu određenog broja zakonskih rješenja primjenjivih na nautički turizam, koja nisu logična ili optimalna za tu gospodarsku granu.

  10. Uslovi korišćenja plovnih dizalica za dizanje potonulih objekata na unutrašnjim plovnim putevima

    OpenAIRE

    Radojević M. Slobodan

    2012-01-01

    U radu se prikazuju uslovi korišćenja plovnih dizalica za dizanje potonulih plovnih i drugih objekata na unutrašnjim plovnim putevima. Prikazani su osnovni načini podizanja plovnim dizalicama i osnovni tehnički podaci sa proračunskim pojedinostima za predložen postupak dizanja. Ukazano je na značaj dizanja potonulih objekata i njihovog uklanjanja iz unutrašnjih plovnih puteva u Republici Srbiji.

  11. OPTIMIZACIJA IN VALIDACIJA HPLC METODE ZA UGOTAVLJANJE VSEBNOSTI ARBUTINA V PRIPRAVKIH Z EKSTRAKTOM VEDNOZELENEGA GORNIKA (ARCTOSTAPHYLOS UVA-URSI L.)

    OpenAIRE

    Rajh, Eva

    2010-01-01

    Pripravki, ki vsebujejo ekstrakt ali učinkovino vednozelenega gornika, se zaradi vsebnosti arbutina, ki ima antiseptično delovanje, pogosto uporabljajo kot uroantiseptiki za samozdravljenje. Za namene zagotavljanja ustrezne kakovosti in pravilnega odmerjanja galenskega izdelka, ki so ga razvili v Javnem zdravstvenem zavodu Mariborskih lekarn Maribor, smo optimirali in validirali HPLC metodo, ki omogoča ugotavljanje vsebnosti arbutina v pripravkih, ki vsebujejo ekstrakt vednozelenega gorni...

  12. Zaustavljanje broda koji nije u vlasništvu osobe odgovorne za pomorsku tražbinu : [prikaz presude

    Directory of Open Access Journals (Sweden)

    Jasenko Marin

    2002-12-01

    Full Text Available Načelno, privremeno zaustavljen može biti samo brod čiji je vlasnik protivnik osiguranja, odnosno osoba odgovorna za pomorsku tražbinu čije se osiguranje traži. U skladu s tim nije dopušteno zaustavljanje broda u vlasništvu trgovačkog društva čiji je jedini član osoba odgovorna za pomorsku tražbinu.

  13. Purification of cooling water for nuclear reactors using ion exchangers; Preciscavanje vode za hladjenje nuklearnih reaktora pomocu neorganskih jonoizmenjivaca

    Energy Technology Data Exchange (ETDEWEB)

    Ruvarac, A [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1969-07-01

    Zirconiumphosphate, zirconiumoxide and natural magnetite as inorganic substances with favourable adsorption properties were the subject of investigations dealing with problems of water purification for nuclear rector cooling. Study on adsorption of impurities form reactor water to 300 deg C and 100 Atm was done by specially constructed autoclaves. On the other hand, a pre-project covering a laboratory plant for investigation of inorganic ion exchangers under real dynamic conditions is given. In order to obtain necessary data on the basis of which techno-economical analyses regarding utilization of zirconiumphosphate, zirconiumoxide and magnetite for water purification is cooling the reactors types BWR and PWR, could be performed, systematic investigations of physical and chemical properties of these substances were commenced. Equilibrium constants have been determined for adsorption processes at different pH values, as well as under various temperatures. Obtained equilibrium constants were used for calculation of thermodynamic quantities {delta}H, {delta}G and {delta}S (author) [Serbo-Croat] Cirkonijumfosfat, cirkonijumoksid i prirodni magnet, kao neorganski materijali sa pogodnim adsorpcionim osobinama, bili su predmet istrazivanja vezanih za probleme preciscavanja vode za hladjenje nuklearnih reaktora. Izucavanje adsorpcije necistoca iz reaktorske vode do 300 deg C i 100 Atm vrseno je pomocu specijalno konstruisanog autoklava, a za ispitivanje neorganskih jonoizmenjivaca pri realnim dinamickim uslovima dat je idejni projekt jednog laboratorijskog postrojenja. Za dobijanje potrebnih podataka, na osnovu kojih se mogu napraviti tehno-ekonomske analize o koriscenju cirkonijumfosfata, cirkoijumoksida i magnetita za preciscavanje vode za hladjenje reaktora tipa BWR i PWR, zapoceto je sa sistematskim proucavanjima fizickih i hemijskih osobina pomenutih materijala, odredjivane su konstante ravnoteze za procese adsorpcije pri razlicitim pH vrednostima, kao i na razlicitim

  14. Funzioni lessicali e aspettuali del preverbo za- nella Povest’ vremennych let

    Directory of Open Access Journals (Sweden)

    Luisa Ruvoletto

    2012-01-01

    Full Text Available This paper examines the forms of the za- prefixed verbs in the Old Russian text Povest’ vremennych let (11th-12th centuries. The study shows how this prefix, like other prefixes in Old Russian, has both lexical and aspectual functions, and that there is considerable interaction between the semantics of the prefix and the meaning of the unprefixed verb. Some groups of verbal forms can be found in which the prefix fulfils specific meanings. This analysis allows the detection of some “embryonic” forms of the lexical meanings and aspectual functions expressed in the modern Russian by the za- prefixed verbs in one of the oldest East Slavic texts. This is clearly of interest when delineating the semantic evolution of this prefix and its aspectual function in a diachronic perspective.

  15. Vseživljenjsko učenje, pogoj za preživetje in kakovost

    Directory of Open Access Journals (Sweden)

    Vida A. Mohorčič-Špolar

    1996-12-01

    Full Text Available Posvet s tem naslovom je (v organizaciji Andragoškega društva Slovenije potekal od 30. maja do l. junija 1996. Sodelovalo je več kot 100 udeležencev iz različnih dejavnosti, ki se ukvarjajo z izobraževanjem odraslih. Posvet je bil po eni strani odgovor Andragoškega društva Slovenije na izzive, ki jih izobraževalcem odraslih narekuje čas, v katerem živimo, po drugi strani pa priprava na posvet, ki ga bo v Hamburgu, julija 1997, organiziral Unesco, z geslom: Učenje odraslih, ključ za 21. stoletje. Hkrati pa je tudi čas za premislek o nadaljnjem delu društva.

  16. Kolegialni coaching: priročnik za strokovni in osebni razvoj (ocena knjige

    Directory of Open Access Journals (Sweden)

    Karin Elena Sánchez

    2014-04-01

    Full Text Available Kolegialni coaching avtoric Zore Rutar Ilc, Blanke Tacer in Brigite Žarkovič Adlešič je prvi priročnik za to področje, ki je plod slovenskega znanja. Na eni strani je sistematičen, metodičen, do bralca prijazno zasnovan, didaktično bogat in strokoven vodnik po osnovah coachinga; na drugi strani temelji na praktičnih primerih, v katerih skozi refleksijo uporabnikov in preizkuševalcev coachinga bralcu omogoča neposreden vpogled v njihovo učenje, napredek in razvoj. Pri tem ponuja nekatere preproste tehnike, orodja in modele ter bralcu na slikovit način pokaže, kako jih uporabiti v praksi. Primere uporabe začini še z izkušnjami in refleksijo tistih, ki so to že storili.

  17. Standardi za upravljanje sigurnošću podataka / Standards for management data security

    Directory of Open Access Journals (Sweden)

    Dejan Vuletić

    2006-10-01

    Full Text Available U radu su analizirani osnovni pojmovi vezani za upravljanje sigurnošću podataka. Ukazano je na potrebu i značaj standardizacije u oblasti informaciono-komunikacionih tehnologija, naročito prema standardima Međunarodne organizacije za standardizaciju (International Standardization Organization - ISO. U završnom delu rada prikazane su proaktivne i reaktivne aktivnosti u upravljanju sigurnošću podataka. / In this article basic notions of management data security are analyzed. We indicated demand and importance of standardization in information-communication technology domain, especially according to International Standardization Organization. In the final part of the article we illustrated both proactive and reactive activities in management data security.

  18. Structural evolution in films of alloy Zn70Al27Cu3 (ZA27)

    International Nuclear Information System (INIS)

    Zhu, Y.H.; Lee, W.B.; Mei, Z.; To, S.; Sze, Y.K.

    2005-01-01

    Films of alloy ZA27 were produced using electron deposition technique. Structural evolution and phase decomposition of the films were studied. It was found that the alloy films were relatively stable because of a strong preferred crystal orientation of the nano-phases. The dependence of nano-phase stability on the Zn content and the preferred crystal orientation is discussed from point of view of Gibbs free energy

  19. Optimizacija procesnih parametrov za stabilizacijo in izboljšanje sposobnosti struženja

    OpenAIRE

    Mlinar, Andrej

    2017-01-01

    Magistrska naloga obravnava proizvodni proces izdelka z ozkim tolerančnim območjem. V procesu izdelave se je pojavil problem nestabilnosti obdelovalnega procesa. Pred analizo obdelovalnega procesa smo najprej z metodo analize merilnega sistema preverili merilni proces. Po preverjanju ustreznosti merilnega procesa smo v nadaljevanju preverili obstoječi obdelovalni proces. Iz analize statistične kontrole procesa obstoječega stanja smo ugotovili, da je proces potrebno stabilizirati. Za stabiliza...

  20. Implementacija aplikacije Smart Watch Workout za naprave iOS s pametno uro Apple Watch

    OpenAIRE

    Skledar, Dejan

    2016-01-01

    V diplomskem delu opišemo in predstavimo naprave ter operacijske sisteme, na katerih teče naša aplikacija. Le-ta je namenjena mobilnim navdušencem, ki jim pomaga do vsakodnevne aktivnosti. Prav tako opišemo potek, razvoj in cilje končnega izdelka na napravi iPhone kot tudi na napravi Apple Watch. Podatki, ki so pomembni za pravilno delovanje aplikacij, se shranjujejo v lokalno podatkovno bazo.

  1. Snovanje in konstruiranje nadstreška za lahka gospodarska vozila

    OpenAIRE

    Čirić, Sebastijan

    2015-01-01

    Diplomska naloga opisuje primer snovanja in konstruiranja nadstreška za lahka gospodarska vozila. Naloga vsebuje statični preračun nadstreška sprogramom Scia Engineer 2011.1 in izdelavo modela nadstreška ter tehnično dokumentacijo v programu Pro Engineer 5.0. Rezultati statičnega preračuna so analizirane vrednosti povesa in napetosti.

  2. Celovito ravnanje s komunalnimi odpadki na primeru Centra za ravnanje z odpadki Gajke : magistrsko delo

    OpenAIRE

    Mohorič, Igor

    2011-01-01

    V magistrskem delu bomo predstavili celovit sistem ravnanja s komunalni odpadki od zbiranja, predelave, obdelave in odlaganja, s čimer se ukvarja razbremenilna logistika. Z vidika veljavne zakonodaje bomo ocenili ustreznost sedanjih tehnologij obdelave in predelave za doseganje zakonskih zahtev. V drugem delu pa bomo poskušali rešiti problematiko bioloških odpadkov v ostanku komunalnih odpadkov, namenjenih odlaganju s pomočjo nove tehnologije obdelave. Kot končni produkt bomo pridobili sno...

  3. Synthesis and characterization of ZA-27 alloy matrix composites reinforced with zinc oxide nanoparticles

    Directory of Open Access Journals (Sweden)

    B.O. Fatile

    2017-06-01

    Full Text Available An investigation has been carried out on the synthesis and characterization of ZA-27 alloy composites reinforced with zinc oxide nanoparticles. This was aimed at developing high performance ZA-27 matrix nanocomposite with low density. The particle size and morphology of the zinc oxide (ZnO nanoparticles were investigated by Transmission Electron Microscope (TEM and the elemental composition was obtained from Energy Dispersive Spectroscopy (EDS attached to TEM and X-ray fluorescence spectroscopy (XRF. ZA-27 nanocomposite samples were developed using 0, 1, 2, 3, 4 and 5 wt% of ZnO nanoparticles by double steps stir casting technique. Mechanical properties and Microstructural examination were used to characterize the composite samples produced. The results show that hardness and ultimate tensile strength of the composite samples increased progressively with increase in weight percentage of ZnO nanoparticles. Increase in Ultimate tensile strength (UTS of 10.2%, 21.1%, 22.3%, 35.5%, 33.4% and increase in hardness value of 8.2%, 14.8%, 21.7%, 27.9%, 27.1% were observed for nanocomposites reinforced with 1 wt%, 2 wt%, 3 wt%, 4 wt%, and 5 wt% ZnO nanoparticles respectively in comparison with unreinforced alloy. It was generally observed that composite sample containing 4 wt% of reinforcement has the highest tensile strength and hardness values. However, the fracture toughness and percent elongation of the composites samples slightly decreased with increase in ZnO nanoparticles content. Results obtained from the Microstructural examination using optical microscope and Scanning Electron Microscope (SEM show that the nanoparticles were well dispersed in the ZA-27 alloy matrix.

  4. The ZaP Flow Z-Pinch Project - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Shumlak, Uri [Univ. of Washington, Seattle, WA (United States); Nelson, Brian A. [Univ. of Washington, Seattle, WA (United States)

    2013-12-31

    The ZaP Flow Z-Pinch Project is a project to extend the performance of the flow Z-pinch experiment at the University of Washington to investigate and isolate the relevant physics of the stabilizing effect of plasma flow. Experimental plasmas have exhibited an enhanced stability under certain operating parameters which generate a flow state (axial flows in Z-pinches and VH mode in tokamaks). Flow has also been suggested as the stabilizing mechanism in astrophysical jets.

  5. [The life and work of Zaíra Cintra Vidal].

    Science.gov (United States)

    Lopes, G T; Caldas, N P; Lima, T C; Martingil, I C

    2001-01-01

    This is a social-historical study that aims at describing the trajectory of Zaíra Cintra Vidal, her participation in the Nursing School Rachel Haddock Lobo and in the Brazilian Association of Nursing (ABEn). The study is based on the concepts of symbolic power, habitus and symbolic struggle of Pierre Bourdieu. The primary sources are documents which were collected in the Documentation Center of Escola de Enfermagem Ana Neri (EEAN--Ana Neri School of Nursing) in the Federeal University of Rio de Janeiro (UFRJ) and at the Memory Center of the Faculty of Nursing (FENF) in the State University of Rio de Janeiro (UERJ). The data was collected between August 2000 and April 2001 by means of document analysis script. The outcomes showed that Zaíra Cintra Vidal was born on 5 May 1903; graduated from the Nursing School of the National Public Health Department in 1926; studied and post-graduated in the United States from 1927 until 1929 and returned to Brazil in 1943. Zaíra Cintra Vidal was the founder of the Nursing School Rachel Haddock Lobo and was its first director for nine years. She also and took part in ABEn's Direction Board and in the Revista Anais de Enfermagem (Nursing Magazine).

  6. PWV, Temperature and Wind Statistics at Sites Suitable For mm and Sub-mm Wavelengths Astronomy

    Science.gov (United States)

    Otarola, Angel; Travouillon, Tony; De Breuck, Carlos; Radford, Simon; Matsushita, Satoki; Pérez-Beaupuits, Juan P.

    2018-01-01

    Atmospheric water vapor is the main limiting factor of atmospheric transparency in the mm and sub-mm wavelength spectral windows. Thus, dry sites are needed for the installation and successful operation of radio astronomy observatories exploiting those spectral windows. Other parameters that play an important role in the mechanical response of radio telescopes exposed to the environmental conditions are: temperature, and in particular temperature gradients that induce thermal deformation of mechanical structures, as well as wind magnitude that induce pointing jitter affecting this way the required accuracy in the ability to point to a cosmic source during the observations. Temperature and wind are variables of special consideration when planning the installation and operations of large aperture radio telescopes. This work summarizes the statistics of precipitable water vapor (PWV), temperature and wind monitored at sites by the costal mountain range, as well as on t he west slope of the Andes mountain range in the region of Antofagasta, Chile. This information could prove useful for the planning of the Atacama Large-Aperture Submm/mm Telescope (AtLast).

  7. Testiranje balističke otpornosti zaštitnih prsluka / Ballistic resistance of body armour testing

    Directory of Open Access Journals (Sweden)

    Đuro Jovanić

    2006-04-01

    Full Text Available U radu je predstavljena osnova standarda NIJ 0101.04 (Nacionalni Institut Pravde, namenjenog za utvrđivanje minimuma tehničkih zahteva i propisivanje metoda ispitivanja balističke otpornosti zaštitnih prsluka, koji treba da zaštite gornji deo tela od dejstva streljačkog oružja. Standard jeste revizija standarda NIJ 0101.03 iz aprila 1987. i preciznije definiše zahteve u pogledu obeležavanja, kriterijume za prijem i postupke merenja otiska u materijalu iza prsluka. Područje ovog standarda odnosi se samo na balističku otpornost, ali ne i na pretnje od noža i predmeta sa oštrim vrhom. Takođe, ne odnosi se na zaštitne prsluke koji sadrže dopunske elemente ili varijacije u konstrukciji balističkih panela za malu površinu torza, radi povećanja osnovnog nivoa zaštite na ograničenim površinama (bilo balističke ili povrede od tupog vrha. / This work is a basic presentation of NIJ 0101.04 (National Institute of Justice standard, -whose purpose is to establish minimum performance requirements and methods of testing ballistic resistance of body armor intended to protect the torso against gunfire. This standard is a revision of NIJ Standard 0101.03 dated April 1987 and it clarifies the labeling requirements, acceptance criteria, and backface signature measurement procedure. The scope of this standard is limited only to ballistic resistance; and it does not include threats from knives and sharply pointed instruments. In addition, the standard does not include armor that incorporates inserts, or variations in construction of the ballistic panel over small areas of the torso, used for increasing the basic level of protection of the armor (whether ballistic or blunt trauma on localized areas.

  8. Standard NIJ 0115.00 za testiranje otpornosti zaštitnih prsluka na ubode nožem i predmetima sa oštrim vrhom / NIJ 0115.00 standard for testing stab resistance of body armor

    Directory of Open Access Journals (Sweden)

    Đuro Jovanić

    2008-04-01

    Full Text Available Standard NIJ 0115.00 (prema Nacionalnom institutu pravde SAD, namenjen je za utvrđivanje minimuma tehničkih zahteva i metoda ispitivanja otpornosti zaštitnih prsluka, koji treba da zaštite gornji deo tela od uboda nožem i predmetima sa oštrim vrhom. Područje primene ovog standarda ograničeno je samo na pretnje ubodima, a ne na balističke pretnje, poput onih koje su obuhvaćene standardom NIJ 0101.04 za testiranje balističke otpornosti zaštitnih prsluka. / In this work made presentation of NIJ 0115.04. (National Institute of Justice standard, witch purpose is to establish minimum performance requirements and methods of testing for the stab resistance of body armor intended to protect the torso against slash and stab threats. The scope of the standard is limited to stab resistance only; the standard does not address ballistic threats, as those are covered by NIJ Standard 0101.04. Ballistic Resistance of Personal Body Armor.

  9. Softver za proračun uzdužne statičke stabilnosti i upravljivosti aviona za osnovnu obuku pilota / Software for calculation of an axial static stability and management of airplanes for basic pilot training

    Directory of Open Access Journals (Sweden)

    Dalibor Petrović

    2006-07-01

    Full Text Available U ovom radu opisan je softver za proračun uzdužne statičke stabilnosti i upravljivosti aviona za osnovnu obuku pilota. Softver je urađen sa numerom da konstruktorima omogući brzo i lako dobijanje potrebnih rezultata vezanih za stabilnost i upravljivost kod preliminarnih proračuna vezanih za ovu vrstu aviona. Program je urađen na osnovu analize velikog broja aviona iz ove klase, a njegova tačnost je testirana na avionu "Lasta". Rezultati koji su dobijeni ovim softverom bili su više od zadovoljavajućih, s obzirom na to da se radi o programu koji bi se koristio za preliminarni proračun. / This document introduced software for calculation of an axial static stability and management of airplanes for basic pilot training. The purpose of this software is to provide a quicker and an easier way of getting results regarding preliminary calculation of stability and management for these types of airplanes. The program is based upon analysis of data gathered from a large number of tested airplanes of this class. The accuracy of the program has been tested on the airplane type 'Lasta' and results were more than satisfying, especially regarding the fact that the program is meant to be used for preliminary calculation.

  10. Zaštitno-maskirni uređaj/Protective camouflage cover

    Directory of Open Access Journals (Sweden)

    Alexander Ivanovich Golodyaev

    2014-10-01

    Full Text Available Jednolikost kamuflažno-zaštitnih konstrukcija znatno povećava 'preživljavanje' tenkova u marševskom položaju - glavne udarne sile. Jer, prilikom primene ove konstrukcije, protivnik će biti onemogućen da razlikuje tenk od automobila ili prazne prikolice. Cerada koja je izrađena od višeslojnog visokootpornog materijala obezbediće prevremeno detoniranje protivtenkovskih kumulativnih projektila. S obzirom na to da je većina projektila projektovana za napad na aktivni oklop, prva detonacija neće neposredno pogoditi oklop, već ceradu, a tek druga detonacija pogodiće aktivni oklop. Na taj način eksplozija aktivnog oklopa neutralisaće kumulativni mlaz. Ova konstrukcija je mnogo efikasnija od gumenih modela zaštite, a po ceni je znatno povoljnija. U članku je predočena analiza sredstava borbe s oklopnim vozilima i metode navođenja 'pametnih' projektila na cilj, kao i analiza metoda borbe sa sredstvima za napad. Takođe, opisani su načini borbe protiv 'pametnih' projektila, kao i način primene kamuflažno-zaštitne instalacije (uređaja. Članak sadrži podatke o patentu. / (ruski Edinoobrazie v maskirovočno-zaščitnyh konstrukcijah rezko uveličivajut vyživaemost' tankov na marše - osnovnoj udarnoj sily, t.k. pri ego primenenii budet složno otličit' tank ot av- tomobilja ili pustogo pricepa. Primenenie, pri ëtom, tenta iz mnogoslojnoj tkani vysokoj pročnosti obespečivaet preždevre- mennyj podryv protivotankovyh kumuljativnyh snarjadov. S uče- tom togo, čto bol'šaja čast' ëtih snarjadov rassčitana na aktiv- nuju bronju, pervyj vzryv budet ne na aktivnoj brone, a na tkani tenta, a vtoroj - osnovnoj vzryv proizojdet uže na aktivnoj brone, i kumuljativnaja struja budet razrušena vzryvom aktivnoj broni. Stoimost' konstrukcii značitel'no niže naduvnyh mode- lej tehniki, a po ëffektivnosti značitel'no ih prevoshodit. V stat'e privoditsja analiz sredstv bor'by s bronete- hnikoj i metody navedenija na cel' 'umnyh

  11. The LLAMA 12 m mm/sub-mm radiotelescope in the Andes

    Science.gov (United States)

    Lepine, Jacques; Edemundo Arnal, Marcelo; de Graauw, Thijs; Abraham, Zulema; Gimenez de Castro, Guillermo; de Gouveia Dal Pino, Elisabete; Morras, Ricardo; Larrarte, Juan; Viramontes, José; Finger, Ricardo; Kooi, Jacob; Reeves, Rodrigo; Beaklini, Pedro

    2015-08-01

    LLAMA (Large Latin American Millimetric Array) is a joint Argentinean-Brazilian project of a 12m mm/sub-mm radio telescope similar to the APEX antenna, to be installed at a site at 4800 m altitude near San Antonio de Los Cobres in the Salta Province in Argentine, at 150 km from ALMA. The scientific cases for single dish and VLBI observations include black holes and accretion disks, the molecular evolution of interstellar clouds, the structure of the Galaxy, the formation of galaxies, and much more. The antenna was ordered to the company Vertex Antennentechnik in June 2014, and the construction is progressing quickly; it will be installed at the site in 2016. The radio telescope will be equipped with up to six receivers covering bands similar to those of ALMA. Cryostats with room for 3 cartridges, constructed by NAOJ (Tokyo,Japan), will be installed in each of the two Nasmyth cabins. Among the first receivers we will have an ALMA band 9 provided by NOVA (Groningen, Holland) and a band 5 from the Chalmers University (Sweden). Other receivers are still being discussed at the time of submission of this abstract,At high frequencies, VLBI observations at high frequencies could be made with ALMA, APEX and ASTE, and Northern radiotelescopes. In this way, LLAMA will be a seed for a Latin-American VLBI network.

  12. Failure analysis of large tube of maraging steel 350 (145 mm dia, 1 mm wall thickness)

    International Nuclear Information System (INIS)

    Shamim, A.

    1997-01-01

    A steady of opening mode of crack initiation in maraging steel 350 rotor tubes aged and rolled condition (1 mm thick sheet) has been constructed, with the aid of a (NEOPHOT 2) microscope. Observations were made from several orientations including the top view of the specimen which showed the profile and the edge view of the specimen which showed the entire notch front along the specimen thickness. It was found that the edge view exhibited the first signs of permanent deformation. These changes took the form of deformation bends which were aligned in direction of the tensile axis and apparently defined limiting regions of homogeneous slip. It is felt that the appearance of microcracks at loads approaching the breaking strength was of fundamental importance in the formation of the final fracture surface. Many of these microcracks were initiated at intermetallic particles and other metallurgically weak regions on the notch surface. (author)

  13. Research nuclear reactor RA - Annual Report 1990 with the comparative evaluation for the period 1986-1990; Istrazivacki nuklearni reaktor RA - Izvestaj za 1990. godinu uz uporedni pregled za period 1986 - 1990

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1990-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1990, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1990. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3705/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  14. Effects of minor scandium on as-cast microstructure, mechanical properties and casting fluidity of ZA84 magnesium alloy

    International Nuclear Information System (INIS)

    Pan Fusheng; Yang Mingbo; Cheng Liang

    2010-01-01

    The effects of minor Sc on the as-cast microstructure, mechanical properties and casting fluidity of the ZA84 magnesium alloy were investigated. The results indicate that the Mg 32 (Al,Zn) 49 phase in the ZA84 alloy is refined with the addition of 0.12-0.35 wt.% Sc, and the formation of the Mg 32 (Al,Zn) 49 phase is suppressed. An increase in Sc amount from 0.12 wt.% to 0.35 wt.% causes the morphology of the Mg 32 (Al,Zn) 49 phase to gradually change from coarse continuous and/or quasi-continuous net to relatively fine quasi-continuous and/or disconnected shapes. In addition, it is shown that the tensile and creep properties of the ZA84 alloy are improved, but the casting fluidity of the alloy is decreased with the addition of 0.12-0.35 wt.% Sc.

  15. Nadležnost upravnih sudova u zaštiti tržišnog natjecanja

    Directory of Open Access Journals (Sweden)

    Lidija Rostaš-Beroš

    2014-01-01

    Full Text Available U radu se razmatra nadležnost upravnih sudova kroz do sada donesene zakone o zaštiti tržišnog natjecanja u Republici Hrvatskoj. Kako su se mijenjali propisi kojima je uređivana zaštita tržišnog natjecanja, hrvatsko pravo tržišnog natjecanja sve se više usklađivalo s europskim pravom, što je bila i namjera s obzirom na pripreme, a zatim i ulazak Republike Hrvatske u članstvo Europske unije. Međutim, iz istog razloga je provedena i reorganizacija upravnog sudovanja pa su se mijenjali i upravni sudovi nadležni za ocjenjivanje zakonitosti akata donesenih u postupcima kontrole poštovanja pravila o tržišnom natjecanju.

  16. Prilog optimalnom projektovanju aktivnog sistema za oslanjanje vozila / A contribution to optimal design of vehicle active suspension system

    Directory of Open Access Journals (Sweden)

    Miroslav Demić

    2005-05-01

    Full Text Available U ovom radu prikazanje sistem za aktivno oslanjanje vozila, uz korišćenje ravanskog modela vozila, bez filtera u povratnim spregama sistema za regulaciju. Za optimizaciju parametara PI kontrolera korišćena je metoda stohastičke parametarske optimizacije. Cilj optimizacije bio je istovremeno minimiziranje vibracijskih ubrzanja oslonjene mase i standardnog odstupanja sila u kontaktima točkova i tla, što poboljšava udobnost i ponašanje vozila na putu. / In this paper, an active suspension system is developed by use of a vehicle plane model without feedback filters in control system. A method of stochastic parameters optimization has been utilized in order to optimize PI controller parameters. The basic optimization goal was a simultaneous minimization of sprung mass acceleration and standard deviation of forces in tire-to-ground contact area, so as to improve vehicle comfort and handling performances.

  17. Sporadic Creutzfeldt-Jakob Disease MM1+2C and MM1 are Identical in Transmission Properties.

    Science.gov (United States)

    Kobayashi, Atsushi; Matsuura, Yuichi; Iwaki, Toru; Iwasaki, Yasushi; Yoshida, Mari; Takahashi, Hitoshi; Murayama, Shigeo; Takao, Masaki; Kato, Shinsuke; Yamada, Masahito; Mohri, Shirou; Kitamoto, Tetsuyuki

    2016-01-01

    The genotype (methionine, M or valine, V) at polymorphic codon 129 of the PRNP gene and the type (1 or 2) of abnormal prion protein in the brain are the major determinants of the clinicopathological features of sporadic Creutzfeldt-Jakob disease (CJD), thus providing molecular basis for classification of sporadic CJD, that is, MM1, MM2, MV1, MV2, VV1 or VV2. In addition to these "pure" cases, "mixed" cases presenting mixed neuropathological and biochemical features have also been recognized. The most frequently observed mixed form is the co-occurrence of MM1 and MM2, namely MM1+2. However, it has remained elusive whether MM1+2 could be a causative origin of dura mater graft-associated CJD (dCJD), one of the largest subgroups of iatrogenic CJD. To test this possibility, we performed transmission experiments of MM1+2 prions and a systematic neuropathological examination of dCJD patients in the present study. The transmission properties of the MM1+2 prions were identical to those of MM1 prions because MM2 prions lacked transmissibility. In addition, the neuropathological characteristics of MM2 were totally absent in dCJD patients examined. These results suggest that MM1+2 can be a causative origin of dCJD and causes neuropathological phenotype similar to that of MM1. © 2015 International Society of Neuropathology.

  18. RA Research nuclear reactor - Annual report 1987; Istrazivacki nuklearni reaktor RA - Izvestaj o radu za 1987. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1987-12-15

    Annual report concerning the project 'RA research nuclear reactor' for 1987, financed by the Serbian ministry of science is divided into two parts. First part is concerned with RA reactor operation and maintenance, which is the task of the Division for reactor engineering of the Institute for multidisciplinary studies and RA reactor engineering. Second part deals with radiation protection activities at the RA reactor which is the responsibility of the Institute for radiation protection. Scientific council of the Institute for multidisciplinary studies and RA reactor engineering has stated that this report describes adequately the activity and tasks fulfilled at the RA reactor in 1989. The scope and the quality of the work done were considered successful both concerning the maintenance and reconstruction, as well as radiation protection activities. [Serbo-Croat] Godisnji izvestaj po projektu 'Istrazivacki nuklearni reaktor RA' za 1987. godinu, koji finansira republicka zajednica za nauku SR Srbije po ugovoru br. 3509/1 sastoji se iz dva dela. Prvi deo obuhvata pogon i odrzavanje nuklearnog reaktora RA, sto predstavlja obavezu Odeljenja za reaktorski inzenjering u sastavu OOUR Instituta za multidisciplinarna istrazivanja i inzenjering RA. Drugi deo obuhvata poslove zastite od zracenja na reaktoru RA, sto predstavlja obavezu OOUR Instituta za zastitu od zracenja 'Zastita'. Naucno vece Instituta za multidisciplinarna istrazivanja i inzenjjring RA ocenilo je da sadrzina ovog izvestaja odgovara izvrsenim poslovima na reaktoru RA u 1989. godini. Pozitivno se ocenjuje obim i kvalitet izvrsenih radova kako u pogledu odrzavanja i rekonstrukcije reaktora, tako i u pogledu poslova zastite od zracenja izvrsenih kod njega.

  19. Preparation of sup 125 I-creatine phosphokinase-MM

    Energy Technology Data Exchange (ETDEWEB)

    Jingxian, Su; Jingmin, Ma [Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy

    1988-09-01

    {sup 125}I-creatine phosphokinase-MM ({sup 125}I-CPK-MM) was prepared by {sup 125}I-labelled Bolton-Hunter reagent (HPNS). Iodinating conditions of HPNS and its conjugation to protein were studied. {sup 125}I-CPK-MM with immune activity was obtained and used to establish the {sup 125}I-CPK-MM radioimmunoassay method by the General Hospital of PLA. {sup 125}I-CPK-MM in PBS-G solution containing 0.015 mol/l ethyl mercaptan at 4-10 deg C can be used for one month.

  20. Vjera kao hod temeljnog povjerenja. Bitnost primarnih iskustava za razvoj religioznosti

    OpenAIRE

    Stengl, Ivan

    2013-01-01

    U dinamičnom sučeljavanju s rezultatima drugih društvenohumanističkih disciplina, teologija promišlja u njihovu svjetlu put rasta u vjeri i osmišljava planove religioznog odgoja i naobrazbe. Ne umanjujući pozitivne efekte i plodnu suradnju (jačanje senzibilnosti za dobne, kulturne, socijalne i razvojno-psihološke specifičnosti osobe vjernika) prilog ukazuje i na granice mišljenja, kako postoji neosporna paralela psihičkog i religioznog razvoja osobnosti, te da religioznos...

  1. INTERNET STVARI IN ANALIZA DODANE VREDNOSTI PAMETNE NAPRAVE ZA KONČNEGA UPORABNIKA

    OpenAIRE

    Čander, Tamara

    2016-01-01

    Če smo še pred nekaj leti govorili o svetovnem spletu kot o revoluciji, danes vemo, da to še nikakor ni vse. Priča smo novemu valu tehnološkega napredka, ki transformira naše okolje in vsakodnevne predmete v ekosistem informacij. Internet stvari je skupek tehnologij, ki povezujejo stvarnost z digitalnimi svetom preko senzorjev in značk, vgrajenih v naprave za vsakodnevno rabo. Čeprav si strokovnjaki o potencialni velikosti trga, ki ga ta fenomen odpira, niso povsem enotni, pa so vsi prepričan...

  2. MARKETINŠKA STRATEGIJA ZA SPLETNO TRGOVINO KUPONI.ENAA.COM

    OpenAIRE

    Marzidošek, Dean

    2016-01-01

    Marketinška strategija za spletne trgovine je precej drugačna od klasične marketinške strategije. Seveda upošteva enake zakonitosti, vendar so v večini primerov klasični oglaševalski kanali, kot so na primer televizija, radio, tisk in podobno, popolnoma odsotni. Na drugi strani jih nadomeščajo digitalni kanali v popolnosti, ki se jim je treba tudi bolj podrobno posvetiti v spletni strategiji. Prednost digitalnih kanalov je v zelo dobri in hitri merljivosti rezultatov, dostopnost takšnih oglaš...

  3. Uporaba službenih psov za različne namene delovnih procesov

    OpenAIRE

    Rejc, Sara

    2017-01-01

    Pred vami se nahaja diplomsko delo z naslovom Uporaba službenih psov za različne namene delovnih procesov. Glavni namen in cilj diplomskega dela je proučiti in opisati uporabo službenega psa, predvsem v policiji, vojski in zaporih, kar predstavlja jedro tega diplomskega dela. Želeli smo prikazati vsestransko uporabnost psov v svetu ljudi. Ugotovili smo, da je enota reševalnih psov pomemben del ekipe pri iskanju pogrešanih in poškodovanih oseb. Na tem mestu je podrobneje opisano šolanje psa in...

  4. UPORABA COBIT 5 ZA SPREMLJANJE IN VREDNOTENJE IT REŠITEV

    OpenAIRE

    Lončar, Tomaž

    2013-01-01

    V diplomskem delu so predstavljeni ključni pristopi za razumevanje spremljanja vrednotenja in ocenjevanja informacijske rešitve skeniranja evidenčnih listov o ravnanju z odpadki po priporočilih COBIT 5. Ključen prispevek dela predstavlja proučitev priporočil COBIT 5 in izvedba praktičnega primera na osnovi omenjenih priporočil. V teoretičnem delu se po poglavjih zvrstijo področja, ki opisujejo podjetje, kjer smo izvajali vrednotenje po COBIT 5 priporočilih, ter predstavitev samega COBIT-a....

  5. Pomen okoljske ozaveščenosti in sodelovanja javnosti za trajnostni razvoj

    Directory of Open Access Journals (Sweden)

    Metka Špes

    2008-12-01

    Full Text Available Pri trajnostnem razvoju, ki zahteva uravnoteženost med ekonomskimi, socialnimi in okoljskimi cilji, je ključnega pomen tudi najširša udeležba javnosti. Za poznavanje ekoloških in razvojnih odločitev pa je potrebno zagotoviti objektivne informacije in dvig splošne okoljske zavesti. Posameznik ali skupine ljudi bodo reakcije na negativne pojave v okolju gradili na njegovi percepciji, ki pa ne ustreza vedno objektivnemu stanju, ampak ga modificirajo različni dejavniki, med njimi tudi dostop do informacij in sodelovanje javnosti pri odločanju.

  6. Univerzalne vrednote multikulturnega sveta kot osnova za globalni novinarski etični kodeks

    OpenAIRE

    Belužić, Verena

    2016-01-01

    Hitre tehnološke spremembe so povzročile, da naš svet postaja vedno manjši. V preteklosti je novinarski etični kodeks segal do mej države v kateri je bil sprejet, danes teh mej ni več, zato se je pojavila potreba po globalni novinarski etiki, ki bi lahko pomenila rešitev za uspešno medkulturno novinarsko poročanje. Na osnovah idej kozmopolitizma in univerzalizma poskušajo nekateri strokovnjaki opredeliti globalno novinarsko etiko. Rezultat te diplome je primerjava novinarskih etičnih kodeksov...

  7. Ekspertni sistem za avtomatsko analizo lastnosti taktičnega radijskega omrežja

    OpenAIRE

    Klampfer, Saša

    2009-01-01

    V širokem razcvetu računalniške industrije in pridobitve velike procesorske moči, so se v različnih industrijskih panogah močno uveljavili izpopolnjeni računalniški sistemi. Le ti so dandanes človeku v veliko pomoč, v nekaterih primerih pa z implementirano umetno inteligenco nadomeščajo človeško bitje. Med sisteme, ki so v pomoč uporabniku, operaterju, delavcu ipd. spadajo ekspertni sistemi z omejenim naborom znanja, in so namenjeni razreševanju problemov iz dobro poznane domene. Znanje za ra...

  8. NAČRT MARKETINŠKEGA KOMUNICIRANJA ZA PRODAJNI PROGRAM, PAPIRNE KONFEKCIJE

    OpenAIRE

    Žižek, Tina

    2016-01-01

    POVZETEK Ko govorimo o marketinškem komuniciranju je potrebno paziti na dejstvo, da mora tisti, ki pošilja sporočilo dobro poznati okolje tistega, kateremu je sporočilo namenjeno. To pomeni, da mora upoštevati morebitne posebnosti, ki so osnova za razmišljanje o posameznih segmentih. Pri tem pa ni pomembno samo komuniciranje organizacije z okoljem ampak tudi interno komuniciranje in v njegovem okviru komuniciranje top managementa podjetja s svojimi zaposlenimi. Pravilne odločitve glede iz...

  9. DRŽAVNI ISPITI ZA SAMOSTALNO VOĐENJE ŠUMSKOG GOSPODARSTVA

    OpenAIRE

    uredništvo

    2015-01-01

    U prošlome smo se dvobroju Šumarskoga lista, obilježavajući 250. obljetnicu hrvatskoga šumarstva, osvrnuli na tekstove iz prvih godina njegovog tiskanja, povlačeći paralelu s današnjicom. Zbog uvida u povijesni slijed šumarske struke i interesantnost, pa i aktualnost tekstova, u ovome se dvobroju osvrćemo na tri teksta iz 1880. i 1881. god. vezana uz naslov. Prvi tekst odnosi se na „Naredbu c. k. ministarstva za poljodjelstvo od 13. veljače 1875, B 129/A. M., R.-G.-Bl. Br. 9, koja se odnosi n...

  10. PRIMERJALNA ANALIZA SPLETNEGA BANČNIŠTVA PROBANKE IN NLB ZA PREBIVALSTVO

    OpenAIRE

    Bunšek, Dejan

    2013-01-01

    V diplomskem delu sem primerjal spletno bančništvo Probanke in NLB za prebivalstvo. Omenjeni sistem se pri Probanki imenuje Prosplet, pri NLB-ju pa NLB Klik. V teoretičnem delu sem raziskal razlike med izrazoma spletna stran in spletni portal, da sem kasneje lažje naredil primerjavo spletnih strani Probanke in NLB-ja. V teoretičnem delu sem prav tako ugotavljal razlike med spletnim bančništvom in elektronskim bančništvom, da ne bi zamenjevali teh podobnih, a različnih pojmov. Spletno banč...

  11. VZROKI MLADOLETNIŠKEGA PRESTOPNIŠTVA IN UKREPI ZA NJEGOVO PREPREČEVANJE

    OpenAIRE

    Matija, Sabina

    2013-01-01

    Diplomska naloga obravnava mladoletniško prestopništvo. Osredotoča se na vzroke in ukrepe za preprečevanje oziroma zmanjševanje prestopništva mladih. Pozornost je posvečena še obravnavi tako mladoletnih storilcev kaznivih dejanj kot mladoletnih storilcev prekrškov. Mladoletniško prestopništvo obsega kazniva dejanja in druge oblike deviantnega, negativnega odklonskega vedenja otrok in mladoletnikov, vendar je pri nas sprejeto ožje pojmovanje omenjenega pojava. Po tem konceptu obravnava kaz...

  12. Razvoj močnostnega ojačevalnika za ultrazvočno pulzno stimulacijo

    OpenAIRE

    GRADIŠEK, MIHA

    2016-01-01

    Magistrsko delo opisuje izdelavo ojačevalnika električnih signalov sinusne oblike v ultrazvočnem spektru frekvenc do 1 MHz za namene vzbujanja ultrazvočne sonde. Delo zajema analizo visokofrekvenčnih pojavov in karakteristik sistema oddajnika ultrazvočnih valov, ki jih moramo upoštevati pri konstrukciji naprave z namenom maksimalne oddane moči ultrazvočnega oddajnika. Zasnova električnega vezja močnostnega ojačevalnika je bila sprva preverjena s simulatorjem LT Spice in kasneje nadgrajena ...

  13. Povezovanje logov, logotipov in sloganov v zaščitnih grafičnih znakih

    OpenAIRE

    Ambrožič, Maja

    2016-01-01

    Ne glede na velikost organizacije, letni plačilni promet, organizacijsko strukturo, organizacijsko kulturo, naprave v lasti organizacije, poslovne prostore, organizacijsko klimo, organizacijsko strategijo, poslanstvo, vizijo, število zaposlenih itd v očeh javnosti vedno šteje oziroma organizacijo popolno predstavlja njena celostna grafična podoba. Celostna grafična podoba je identiteta organizacije, ki vključuje vso zgoraj našteto vsebino, ki jo mora grafični oblikovalec povezati v zaščitni g...

  14. BOL I SMJERNICE ZA SUZBIJANJE BOLI PRI KRONIČNOJ RANI

    OpenAIRE

    PERSOLI-GUDELJ, MARIJANA; LONČARIĆ-KATUŠIN, MIRJANA; MIŠKOVIĆ, PETAR

    2016-01-01

    U ovom preglednom članku opisan je patomehanizam nastanka bolnog osjeta sa posebnim osvrtom na pojavu boli kod kronične rane. Prikazane su smjernice (preporuke) za njeno liječenje. U liječenju je stavljen naglasak na farmakoterapiju (analgetici). Kao temelj racionalne primjene analgetika preporuča se »trostupanjska» ljestvica SZO-e. Istaknuta je potreba kombinacije farmakoterapije s nefarmakološkim postupcima (kirurški, fi zikalni). Posebno je istaknut pozitivni učinak VIP svjetla na ubrza...

  15. Vpliv toplotnih mostov na porabo energije za ogrevanje na primeru osnovne šole

    OpenAIRE

    Megušar, Primož

    2015-01-01

    Na primeru Osnovne šole Dobrova sem preveril, kakšen vpliv imajo dejanski toplotni mostovi na porabo energije za ogrevanje. Iz načrtov stavbe sem evidentiral vse toplotne mostove, kateri vplivajo na porabo energije. Tem toplotnim mostovom sem nato v standardu SIST EN ISO 14683 poiskal ustrezne približke. Nato sem s programom TOST izvedel tri simulacije. V prvem primeru toplotnih mostov nisem upošteval. V drugem primeru sem toplotne mostove upošteval na poenostavljen način, v zadnjem primeru p...

  16. ANALIZA POSLOVNEGA OKOLJA PODJETJA GORENJE D.D. ZA GOSPODINJSKE APARATE V SLOVENIJI

    OpenAIRE

    Radić, Dragica

    2010-01-01

    Za uspešno poslovanje je ključnega pomena, da podjetje pozna poslovno okolje, da razume spremembe, ki nastajajo in da se zna z njimi primerno soočiti. Kontekstualno oz. širše zunanje okolje lahko analiziramo s PEST ali PESTEL analizo. V diplomski nalogi sem prikazala PESTEL analizo. Podjetje mora dobro poznati interesne skupine. Najpomembnejše interesne skupine podjetja Gorenje d.d so: delničarji, kupci, dobavitelji, zaposleni. Najpomembnejši konkurenti podjetja Gorenje d.d. so: GA gospodinjs...

  17. Vloga medicinske sestre pri skrbi za otroka z očesno protezo

    OpenAIRE

    Lukić, Maja

    2017-01-01

    Uvod: Retinoblastom je najpogostejši maligni tumor, ki se velikokrat pojavi v otroški dobi. Bolezen je sicer redka, a zelo nevarna, saj lahko uniči tako otrokovo oko kot tudi njegov vid. Pomembna je hitra prepoznava tega nevarnega tumorja, takojšna diagnostika in zdravljenje. Večje tveganje za nastanek retinoblastoma obstaja pri otrocih, katerih bolezen se je v družini že pojavila. Namen: Namen diplomskega dela je s pomočjo pregleda literature ugotoviti, na kakšen način in kako lahko medicins...

  18. Potresna analiza in analiza ojačitvenih ukrepov za grad Golnik

    OpenAIRE

    Ošterbenk, Jure

    2015-01-01

    V diplomskem delu je narejena seizmična analiza gradu Golnik in primerjalna študija ojačitvenih ukrepov, s katerimi povečujemo potresno odpornost obravnavane konstrukcije. Po začetnem kronološkem opisu stavbe sledi opis zasnove objekta in opis stanja poškodovanosti nosilnih elementov, ki temelji zgolj na vizualnem pregledu konstrukcije. V teoretičnem delu naloge je sprva na kratko predstavljeno obnašanje zidanih stavb med delovanjem potresa in opis različnih porušnih mehanizmov zidovja. Sl...

  19. III Regulations and instructions in case of emergency; III Propisi i uputstva za slucaj udesa

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    This chapter includes definition of the term accident as considered in this document, classification of accidents, and detailed instructions for evacuation in case of accident. A separate annex includes data about indicators which announce accidental events and detailed instructions for actions to be undertaken in case of each mentioned event. Ovo poglavlje sadrzi definiciju pojma udesa, klasifikaciju udesa, detaljna uputstva za evakuaciju u slucaju udesa. Poseban prilog sadrzi detaljne podatke o indikatorima koji registruju udesna stanja i mere koje se preduzimaju u svakom od navedenih slucajeva.

  20. Oblikovanje in izdelava embalaže za nakit Katja Koselj Jewellery

    OpenAIRE

    Gregorka, Nika

    2017-01-01

    Dandanes je vloga videza embalaže vedno pomembnejša in je zato eden izmed bistvenih elementov pri darilni embalaži. Ker embalaža s svojo podobo izraža tudi kakovost izdelka, je le-ta včasih še pomembnejša kot izdelek, ki ga predstavlja. Potemtakem je pomembno, da je kakovostna, preprosta, koristna in okolju prijazna. V diplomskem delu smo predstavili izdelavo in načrtovanje embalaže za slovenski ročno izdelani nakit oblikovalke Katje Koselj. V pregledu literature smo opisali pojem embalaže, n...

  1. Sistem za testiranje uporabniškega vmesnika vgradnega računalniškega sistema

    OpenAIRE

    VAČOVNIK, MARKO

    2017-01-01

    Grafični uporabniški vmesniki so zelo pomemben del naprav z zaslonom. Testiranje vmesnikov je v okviru razvoja programske opreme nepogrešljivo, kar pa predstavlja velik časovni in finančni vložek. Iz teh razlogov je smiselno kar se le da velik del testiranja avtomatizirati. Delo opisuje preverjanje pravilnosti prikaza receptov in njim pripadajočih nastavitev, ki so del uporabniškega vmesnika pečice z LCD zaslonom, občutljivim na dotik. Za preverjanje izpisanega besedila je uporabljen odprt...

  2. NOVI OBLICI RADA KAO SUVREMENI IZAZOV ZA RADNO PRAVO – SLUČAJ UBER

    OpenAIRE

    Bjelinski Radić, Iva

    2017-01-01

    Pod utjecajem brzog razvoja digitalnih tehnologija u posljednje vrijeme je došlo do pojave novih oblika fleksibilnog zapošljavanja koje karakterizira snažna ili prevladavajuća podrška informacijske i komunikacijske tehnologije. Online platforma Uber za pružanje usluge gradskog prijevoza putnika jedan je od široj javnosti najpoznatijih predstavnika navedenih promjena u svijetu rada. Imajući u vidu da je pojava Ubera izazvala brojne kontroverze i postavila nove suvremene regul...

  3. Izbor optimalnoga sustava deviznog tečaja za Republiku Hrvatsku

    OpenAIRE

    Koški, Dražen

    2008-01-01

    Cilj istraživanja, čiji su rezultati prikazani u ovome članku, bio je izabrati optimalan sustav deviznoga tečaja za Republiku Hrvatsku, dakako prije njezina ulaska u Europsku uniju. Analizirani su sustavi deviznoga tečaja – od sustava slobodno-fluktuirajućega deviznog tečaja do sustava bez domaće valute u optjecaju, naravno, uvažavajući klasifikaciju Međunarodnoga monetarnog fonda. Nakon toga provedena je komparacija temeljnih ekonomskih prednosti i nedostataka sustava fiksnoga de...

  4. Vrednotenje rešitve za prostoročno uporabo računalnika na osnovi naprave Emotiv EPOC++

    OpenAIRE

    Špindler, Matic

    2017-01-01

    Naprave in načini njihove uporabe za upravljanje računalnika se ne spreminjajo zelo pogosto. Z napredkom tehnologije se pojavljajo nove rešitve, ki so sedaj bolj dostopne in ponujajo nove načine interakcije z računalnikom. V tej magistrski nalogi bomo ovrednotili rešitev za prostoročno uporabo računalnika na osnovi možganskega komunikacijskega vmesnika (BCI) Emotiv EPOC+, ki nam omogoča upravljanje računalnika s pomočjo obrazne mimike in misli (EEG). Z raziskavo želimo preveriti uporabnost te...

  5. Uporaba JavaEE mikrostoritev pri razvoju celovite rešitve za upravljanje s spletnimi oglasi

    OpenAIRE

    ANDREJC, GAŠPER

    2017-01-01

    Diplomska naloga govori o procesu razvijanja celovite rešitve za sledenje in upravljanje s spletnimi oglasi, kot pomoč uporabniku pri nakupu želenega izdelka. Končni izdelek diplomske naloge je rešitev, ki je sestavljena iz spletne aplikacije, mobilne aplikacije, razširitve v spletnem brskalniku ter zalednega sistema. Diploma poleg idejne zasnove predstavlja tudi uporabo JavaEE mikrostoritev in ostalih tehnologij ter argumentira, zakaj so izbrani okvirji najprimernejši za takšno rešitev. Cilj...

  6. CT-based postimplant dosimetry of prostate brachytherapy. Comparison of 1-mm and 5-mm section CT

    International Nuclear Information System (INIS)

    Tanaka, Osamu; Hayashi, Shinya; Kanematsu, Masayuki; Matsuo, Masayuki; Hoshi, Hiroaki; Nakano, Masahiro; Maeda, Sanaho; Deguchi, Takashi; Hoshi, Hiroaki

    2007-01-01

    The aim of this study was to compare the outcomes between 1-mm and 5-mm section computed tomography (CT)-based postimplant dosimetry. A series of 21 consecutive patients underwent permanent prostate brachytherapy. The postimplant prostate volume was calculated using 1-mm and 5-mm section CT. One radiation oncologist contoured the prostate on CT images to obtain the reconstructed prostate volume (pVol), prostate V 100 (percent of the prostate volume receiving at least the full prescribed dose), and prostate D 90 (mean dose delivered to 90% of the prostate gland). The same radiation oncologist performed the contouring three times to evaluate intraobserver variation and subjectively scored the quality of the CT images. The mean ±1 standard deviation (SD) postimplant pVol was 20.17±6.66 cc by 1-mm section CT and 22.24±8.48 cc by 5-mm section CT; the difference in the mean values was 2.06 cc (P 100 was 80.44%±7.06% by 1-mm section CT and 77.33%±10.22% by 5-mm section CT. The mean postimplant prostate D 90 was 83.28%±10.81% by 1-mm section CT and 78.60%±15.75% by 5-mm section CT. In the evaluation of image quality, 5-mm section CT was assigned significantly higher scores than 1-mm section CT. In regard to intraobserver variation, 5-mm section CT revealed less intraobserver variation than 1-mm section CT. Our current results suggested that the outcomes of postimplant dosimetry using 1-mm section CT did not improved the results over those obtained using 5-mm section CT in terms of the quality of the CT image or reproducibility. (author)

  7. Perspective decisions of WWER nuclear fuel: Implementation at Russian NPPs

    International Nuclear Information System (INIS)

    Molchanov, V.

    2003-01-01

    The scientific and technical policy pursued by JSC TVEL has managed to create a new generation of fuel assembly design on the basis of solutions tested at various units of Russian NPPs - Kola NPP, Kalinin NPP, Unit 1, Balakovo NPP Unit 1. The requirements set for the new generation nuclear fuel for WWER are: 1) High fuel burnup - up to 70 MWxdays/kgU; 2) Extended operation cycle - up to 6 years; 3) Increase of uranium charge to the core; 4) Increased lateral stability - bow not more than 7 mm; 5) High level of operating reliability - fuel rod leakage not worse than 10-5 1/year; 6) Demountable fuel assembly design. Post-irradiation examination results of fuel assemblies discharged from WWER-1000 reactors demonstrate that fuel rods have substantial reserve in general characteristics including that of dealing with planned burnup. In order to meet the requirements, trials are started for: implementation of rigid skeleton (WWER-1000); fuel column length extension (WWER-1000 and WWER-440); increase of UO 2 charge (WWER-1000 and WWER-440); enhancing of operational reliability and demountable design. It is concluded that the Russian nuclear fuel for WWER-type reactors is competitive and enables the implementation of state-of-the-art cost effective fuel cycles

  8. Research nuclear reactor RA - Annual report 1992; Istrazivacki nuklearni reaktor RA - Izvestaj za 1992. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-12-01

    Research reactor RA Annual report for year 1992 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. First part includes 8 annexes describing reactor operation, activities of services for maintenance of reactor components and instrumentation, financial report and staffing. Second annex B is a paper by Z. Vukadin 'Recurrence formulas for evaluating expansion series of depletion functions' published in 'Kerntechnik' 56, (1991) No.6 (INIS record no. 23024136. Second part of the report is devoted to radiation protection issues and contains 4 annexes with data about radiation control of the working environment and reactor environment, description of decontamination activities, collection of radioactive wastes, and meteorology data. [Serbo-Croat] Godisnji izvestaj o radu nuklearnog reaktora RA za 1992. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA. Prvi deo sadrzi 8 priloga, koji opisuju rad reaktora i poslove sluzbi za odrzavanje opreme i komponenti, finansijski izvestaj, kadrovsku strukturu osoblja reaktora. Drugi prilog (B) je rad Z. Vukadina 'Recurrence formulas for evaluating expansion series of depletion functions' objavljen u casopisu Kerntechnik, 1991. Drugi deo izvestaja o poslovima zastite od zracenja sadrzi 4 priloga sa podacima radijacione kontrole radne sredine i okoline reaktora, opis poslova dekontaminacije i sakupljanja radioaktivnih materija, kao i meteoroloske podatke.

  9. Teknologi Proses Pembuatan Molecular Sieve TiZA Untuk Pemekatan Asam Nitrat

    Directory of Open Access Journals (Sweden)

    Ali Nurdin

    2017-10-01

    Full Text Available Molecular sieve zeolit dapat memurnikan campuran larutan yang bersifat azeotrop yang tidak bisa dilakukan menggunakan metode distilasi biasa. Namun, masih memiliki kelemahan dalam half life time molecular sieve tersebut, khususnya stabilitas bahan apabila digunakan pada larutan yang bersifat korosif seperti larutan asam atau basa. Pada penelitian ini telah  dilakukan pembuatan molecular sieve zeolit A yang dimodifikasi  dengan penambahan 10% titanium. Molecular sieve titanium - zeolit A (TiZA dibuat dengan dengan metode hidrotermal pada temperatur 110 °C dan kalsinasi pada temperatur 500 °C. Karakterisasi dilakukan antara lain menggunakan X-ray Diffraction (XRD, Scanning Electron Microscopy-Energy Dispersive X-ray Spectroscopy (SEM-EDX dan karakterisasi pori dengan metode physisorption menggunakan nitrogen pada temperatur 44 K. Molecular sieve TiZA yang dihasilkan stabil terhadap temperatur tinggi, dan larutan asam. Modifikasi zeolit A dengan titanium telah mampu meningkatkan stabilitas molecular sieve Ti-zeolit A dalam larutan asam nitrat selama 24 jam. Distribusi ukuran pori BJH (Barret Joyner Halenda  yang sempit menggambarkan ukuran yang homogen dengan didominasi oleh mikro porus dengan diameter rata-rata sekitar 4Å. Uji coba pemurnian asam nitrat dengan menggunakan molecular sieve secara single stage dapat meningkatkan kemurnian asam nitrat dari 70% hingga 85%.

  10. Internet of Things zařízení s podporou Bluetooth a COAP

    OpenAIRE

    Fuchs, Ondřej

    2016-01-01

    Tato bakalářská práce se zabývá v dnešní době velmi zmiňovaným pojmem Internet věcí. Hlavním cílem je definovat Internet věcí, popsat jeho historii vzniku, základní charakteristiku, vývoj, problematiku zabezpečení a rizika s tím spojená, trendy a možné využití. Dále pak popsat možné technologie a protokoly pro přenos dat, skupiny výrobců zařízení a následně nastínit budoucnost Internetu věcí. Práce také zahrnuje návrh, implementaci a testování zařízení spadajícího do kategorie Internetu věcí....

  11. Program za vođenje personalne evidencije / Application program for personnel files

    Directory of Open Access Journals (Sweden)

    Miroslav Stojanović

    2002-03-01

    Full Text Available U radu je opisan Program za multikorisnički rad u mrežnom okruženju, koji je namenjen za vođenje personalne evidencije u okviru jedinice. Program je razvijen tako da u mrežnom okruženju radi sa bazom podataka, Microsoft SQL Server, a kada je mreža nefunkcionalna da radi lokalno sa MS Access, i da omogući automatsko ažuriranje podataka iz lokalne u glavnu bazu podataka. Prva verzija programa razvijena je i nalazi se u fazi probnog rada. / The paper presents an application program for personnel files of a unit. The application works in multi-user and network environment. It is developed to work with the Microsoft SQL Server database in network environment and to work with the MS Access database when network is not functional and to allow data synchronization between the local and the main database. The alpha version of the application program is finished and it is on a test drive now.

  12. Research nuclear reactor RA - Annual Report 1991; Istrazivacki nuklearni reaktor RA - Izvestaj za 1991. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1992-01-01

    zahvat, koji se odnosi na zamenu celokupne instrumentacije je u toku, ali njegova realizacija u 1991. godini kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom ugovoru trebalo je da celokupna nova instrumentacija za reaktor RA bude isporucena Institutu u Vinci do kraja 1990. godine, ali je do septembra 1991. godine isporuceno svega 56% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju izrecena od strane ove organizacije Ujedinjenih nacija. U 1991. godini na reaktoru RA je demontirana postojeca instrumentacija u maksimalno mogucem obimu, kako bi se zadrzala neka osnovna merenja neophodna i u uslovima kada reaktor nije u pogonu. Pri kraju je izrada odredjenih konstrukcionih elemenata za novu instrumentaciju, koju je prihvatio da realizuje Institut u Vinci, kako bi se ubrzala realizacija ovog projekta. Ako sva predvijena oprema ne bude isporucena do kraja marta 1992. godine, nece moci da se otpocne sa probnim radom reaktora u prvoj polovini 1993. godine, kako je planirano. Na realizaciji projekta u 1991. godini ucestvovalo je efektivno 53 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova. Godisnji izvestaj o radu nuklearnog reaktora RA za 1992. godinu sastoji se od dva dela: prvi deo obuhvata pogon i odzavanje reaktora RA, a drugi poslove zastite od zracenja na reaktoru RA.

  13. Development of microstructure of steel for thermal power generation: Razvoj mikrostrukture jekel za termično generacijo energije:

    OpenAIRE

    Bevilaqua, T.; Fujda, M.; Kuskulic, T.; Kvackaj, Tibor; Pokorny, I.; Weiss, M.

    2007-01-01

    The evolution of microstructure during the reheating and cooling of steel for thermal power generation was investigated. On the basis of the microstructure produced during cooling a CCT diagram is proposed Raziskan je bil razvoj mikrostrukture pri segrevanju in ohlajanju jekel za toplotno generacijo energije. Na podlagi mikrostrukture, ki je nastala pri ohlajanju, je bil predložen CCT-diagram.

  14. Za fosilními dřevy do ománské pouště

    Czech Academy of Sciences Publication Activity Database

    Matysová, Petra

    89 /140/, č. 6 (2010), s. 360-363 ISSN 0042-4544 Institutional research plan: CEZ:AV0Z30460519 Keywords : silicified wood * Permian * moganite Subject RIV: DB - Geology ; Mineralogy www.vesmir.cz/abstrakt/za-fosilnimi-drevy-geologie-do-omanske-pouste

  15. Študija uporabnosti računalniških simulacij in animacija oblačil za potrebe manjših podjetij

    OpenAIRE

    Slakonja, Andreja

    2016-01-01

    Namen diplomskega dela je bil preučiti uporabnost računalniške simulacije in animacije oblačila za potrebe manjšega podjetja, izdelati kroj, simulacijo in animacijo oblačila na virtualnem parametričnem modelu v programu Marvelous Designer 3 ter zašiti realni model oblačila in ju primerjati. Nadalje je bil namen izdelati spletno stran za modno oblikovalko Barbaro F. V uvodnem delu je opisano modno oblikovanje in konstrukcija oblačil ter predstavitev oblikovalke Barbare F. V nadaljevanju so opi...

  16. Additional instructions related to VISA-2 experiment for instrumentation personnel on duty; Dodatak instrukcijama za dezurne instrumentatore u vezi eksperimenta VISA-2

    Energy Technology Data Exchange (ETDEWEB)

    Pavicevic, M; Nikolic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1963-01-15

    For measuring the temperature gradients between the inlet and outlet water in the reactor channels with VISA-2 irradiation capsules, the previously used platinum resistance thermometers are replaced by thermocouples. This document includes detailed instructions for using these new instruments for measuring the temperature gradients in each reactor channel during experiments. [Serbo-Croat] Za merenje razlike temperature ulazne i izlazne vode u tehnoloskim kanalima sa kapsulama VISA-2, nalaze se umesto dosadasnjih platinskim otpornih termometara, termoparovi koji mere razliku temperature po svakom kanalu. Ovaj dokument sadrzi detaljna uputstva za koriscenje novih instrumenata za merenje razlike temperature tokom eksperimenta.

  17. Modification of Hack Saw Blade Support 'REMOR 400' from the Length of 650 mm to 450 mm

    International Nuclear Information System (INIS)

    Sagino, Abdul-Hafid

    2005-01-01

    REMOR 400 type is the hack saw machine for cutting large work piece. The capacity of cutting is 310 mm diameter. The length of the blade is 650 mm (26 inches). For cutting small work piece (≤ 150 mm), the use of this blade is not efficient because the blade is relatively expensive. To solve this problem, the modification of the blade support is performed so that REMOR 400 machine can use the blade of 450 mm which is cheaper and easier to find in the market. (author)

  18. Initial results from 50mm short SSC dipoles at Fermilab

    International Nuclear Information System (INIS)

    Bossert, R.C.; Brandt, J.S.; Carson, J.A.; Coulter, K.; Delchamps, S.; Ewald, K.D.; Fulton, H.; Gonczy, I.; Gourlay, S.A.; Jaffery, T.S.; Kinney, W.; Koska, W.; Lamm, M.J.; Strait, J.B.; Wake, M.; Gordon, M.; Hassan, N.; Sims, R.; Winters, M.

    1991-03-01

    Several short model SSC 50 mm bore dipoles are being built and tested at Fermilab. Mechanical design of these magnets has been determined from experience involved in the construction and testing of 40 mm dipoles. Construction experience includes coil winding, curing and measuring, coil end part design and fabrication, ground insulation, instrumentation, collaring and yoke assembly. Fabrication techniques are explained and construction problems are discussed. Similarities and differences from the 40 mm dipole tooling and management components are outlined. Test results from the first models are presented. 19 refs., 12 figs

  19. „Ritualno” i „struktuirano” odbacivanje u arheološkim interpretacijama: primer sistema za vodosnabdevanje na lokalitetu „Kale” u Krševici

    Directory of Open Access Journals (Sweden)

    Ivan Vranić

    2016-11-01

    Full Text Available Pitanja vezana za rituale, kultove, religiju ili magiju predstavljaju važne ali u značajnoj meri zanemarene i teorijski nedovoljno precizno utemeljene teme u savremenim arheološkim interpretacijama. Cilj rada jeste da na konkretnim primerima potencijalno ritualnih aktivnosti vezanih za izgradnju i moguće „ritualno ubijanje” sistema za vodosnabdevanje na lokalitetu „Kale” u Krševici pokaže kako ovo zanemarivanje nije samo posledica aktuelnosti i trendova o odabiru istraživačkih tema, već se radi o ozbiljnijem problemu koji pokazuje određene nedostatke savremenih pristupa vezanih za arheologiju identiteta i koncepte struktuiranog ili simboličkog odbacivanja.

  20. Research nuclear reactor RA - Annual Report 1996; Istrazivacki nuklearni reaktor RA - Izvestaj za 1996. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1996-12-01

    Activities related to revitalisation of the RA reactor started in 1986, were continued in 1996. All the planned actions related to renewal of the reactor components were finished. The last, and at the same time most important action, related to exchange of complete reactor instrumentation is underway, delayed. The delivery of components from USSR is late. Production of this instruments is financed by the IAEA according to the contract signed in December 1988 with Russian Atomenergoexport. According to this contract, it has been planned that the RA reactor instrumentation should be delivered to the Vinca Institute by the end of 1990. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the temporary embargo imposed by the IAEA. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 43 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1996 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] U toku 1996. godine nastavljeni su poslovi na revitalizaciji reaktora RA, zapocetoj 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom

  1. ETIČNOST MENADŽERA ZA ODNOSE S JAVNOSTIMA: PROMJENE I IZAZOVI

    OpenAIRE

    Milohnić, Ines; Šustar, Maja

    2013-01-01

    Mnoga hotelska poduzeća prepoznala su ulogu i značaj etike i etičnosti koji sve više dobivaju na afirmaciji posebice u profesiji odnosa s javnošću. Etičke dileme s kojima se susreću su sve češće, a odstupanja od etičkih normi sve izraženija. Radom se nastoji ukazati značaj etike, poštivanje etičkog kodeksa organizacije kao i razine neetičnosti u svakodnevnom poslovanju. Istraživanje je poduzeto tijekom 2013. godine i to kao on-line istraživanje, a ciljnu su skupinu činili menadžeri za odnose ...

  2. Measurement of the $Z/A$ dependence of neutrino charged-current total cross-sections

    CERN Document Server

    Kayis-Topaksu, A; Van Dantzig, R; De Jong, M; Konijn, J; Melzer, O; Oldeman, R G C; Pesen, E; Van der Poel, C A F J; Spada, F R; Visschers, J L; Güler, M; Serin-Zeyrek, M; Kama, S; Sever, R; Tolun, P; Zeyrek, M T; Armenise, N; Catanesi, M G; De Serio, M; Ieva, M; Muciaccia, M T; Radicioni, E; Simone, S; Bülte, A; Winter, Klaus; El-Aidi, R; Van de Vyver, B; Vilian, P; Wilquet, G; Saitta, B; Di Capua, E; Ogawa, S; Shibuya, H; Artamonov, A V; Brunner, J; Chizhov, M; Cussans, D G; Doucet, M; Fabre, Jean-Paul; Hristova, I R; Kawamura, T; Kolev, D; Litmaath, M; Meinhard, H; Panman, J; Papadopoulos, I M; Ricciardi, S; Rozanov, A; Saltzberg, D; Tsenov, R V; Uiterwijk, J W E; Zucchelli, P; Goldberg, J; Chikawa, M; Arik, E; Song, J S; Yoon, C S; Kodama, K; Ushida, N; Aoki, S; Hara, T; Delbar, T; Favart, D; Grégoire, G; Kalinin, S; Makhlyoueva, I V; Gorbunov, P; Khovanskii, V D; Shamanov, V V; Tsukerman, I; Bruski, N; Frekers, D; Rondeshagen, D; Wolff, T; Hoshino, K; Kawada, J; Komatsu, M; Miyanishi, M; Nakamura, M; Nakano, T; Narita, K; Niu, K; Niwa, K; Nonaka, N; Sato, O; Toshito, T; Buontempo, S; Cocco, A G; D'Ambrosio, N; De Lellis, G; De Rosa, G; Di Capua, F; Ereditato, A; Fiorillo, G; Marotta, A; Messina, M; Migliozzi, P; Pistillo, C; Santorelli, R; Scotto-Lavina, L; Strolin, P; Tioukov, V; Nakamura, K; Okusawa, T; Dore, U; Loverre, P F; Ludovici, L; Maslennikov, A L; Righini, P; Rosa, G; Santacesaria, R; Satta, A; Barbuto, E; Bozza, C; Grella, G; Romano, G; Sirignano, C; Sorrentino, S; Sato, Y; Tezuka, I

    2003-01-01

    A relative measurement of total cross-sections is reported for polyethylene, marble, iron, and lead targets for the inclusive charged-current reaction nu_mu + N -> mu^- + X. The targets, passive blocks of ~100kg each, were exposed simultaneously to the CERN SPS wide-band muon-neutrino beam over a period of 18 weeks. Systematics effects due to differences in the neutrino flux and detector efficiency for the different target locations were minimised by changing the position of the four targets on their support about every two weeks. The relative neutrino fluxes on the targets were monitored within the same experiment using charged-current interactions in the calorimeter positioned directly downstream of the four targets. From a fit to the Z/A dependence of the total cross-sections a value is deduced for the effective neutron-to-proton cross-section ratio.

  3. Measurement of the Z/A dependence of neutrino charged-current total cross-sections

    CERN Document Server

    Kayis-Topasku, A; Dantzig, R V

    2003-01-01

    A relative measurement of total cross-sections is reported for polyethylene, marble, iron, and lead targets for the inclusive charged-current reaction nu submu + N -> mu sup - + X. The targets, passive blocks of propor to 100 kg each, were exposed simultaneously to the CERN SPS wide-band muon-neutrino beam over a period of 18 weeks. Systematic effects due to differences in the neutrino flux and detector efficiency for the different target locations were minimised by changing the position of the four targets on their support about every two weeks. The relative neutrino fluxes on the targets were monitored within the same experiment using charged-current interactions in the calorimeter positioned directly downstream of the four targets. From a fit to the Z/A dependence of the total cross-sections a value is deduced for the effective neutron-to-proton cross-section ratio. (orig.)

  4. Riziková analýza vodovodu obecního typu

    OpenAIRE

    Potyšová, Petra

    2012-01-01

    Cílem diplomové práce bylo analyzovat vodovodní síť v obci Klobouky u Brna pomocí softwarové aplikace WaterRisk za použití jednoduché a komplexní metodiky. Na vodovodní síti bylo provedeno měření zákalu jako praktická podpora nežádoucích stavů. Rovněž byl proveden podrobný průzkum obce Klobouky u Brna. Přidanou hodnotou diplomové práce byla konzultace s provozním technikem ve společnosti Vodovody a kanalizace Hodonín, a.s. o zdroji vody a úpravně vody, ze které se voda přebírá pro obec Klobou...

  5. Deniss Karpak piirdus MM-il 26. kohaga

    Index Scriptorium Estoniae

    2008-01-01

    Vt. ka Linnaleht : Tallinn : na russkom jazõke, Linnaleht : Tartu 13. veebr., lk. 6. Austraalias Terrigalis purjetamise Laser-klassi MM-il lõpetas Deniss Karpak 26. kohal. Vt. ka Linnaleht : Tartu 14.veebr.

  6. Eksplozivne materije za neosetljiva ubojna sredstva / Explosive substances for insensitive munitions

    Directory of Open Access Journals (Sweden)

    Radun Jeremić

    2005-03-01

    Full Text Available U skladu sa sve strožim zahtevima za očuvanje životne sredine i većom bezbednošću, tendencije u razvoju suvremenih ubojnih sredstava (UbS, pored povećanja pouzdanosti i efikasnosti, usmerene su i na povećanje sigurnosti pri njihovoj proizvodnji, skladištenju, manipulaciji i upotrebi. Na taj način dobijena je nova kategorija UbS, tzv. neosetljiva UbS, kod kojih je verovatnoća neželjenog aktiviranja pod dejstvom spoljnih impulsa svedena na minimum. Suština rešavanja ovog problema je primena eksplozivnih materija koje su mnogo manje osetljive na spoljne uticaje u odnosu na standardne. Osnovni zahtev koji se pri tome postavlja je da taktičko-tehničke karakteristike ostanu na nivou ili budu bolje u odnosu na postojeća UbS. U radu je ukratko objašnjen koncept razvoja neosetljivih UbS i dat pregled najznačajnijih rezultata istraživanja u oblasti eksplozivnih materija koje zadovoljavaju zahteve za primenu u neosetljivim UbS. / According to severe environment protection and safety requirements, tendencies in development of modern munitions, besides of increasing reliability and efficiency, are directed to decreasing of danger during their processing, storing, handling and operating. In that manner the new category of munitions has been obtained, named insensitive munitions, with a minimum probability of unplanned activating. The best method for solving this problem is using of explosive substances that are more insensitive according to standard ones. The main requirement is the tactical and technical characteristics stay at the level or to be better according to the existing munitions. In this paper the developing concept of insensitive munitions is shortly explained and presented a review of most important research results of explosive materials that fulfill requirements for applying in insensitive munitions.

  7. QM/MM investigations of organic chemistry oriented questions.

    Science.gov (United States)

    Schmidt, Thomas C; Paasche, Alexander; Grebner, Christoph; Ansorg, Kay; Becker, Johannes; Lee, Wook; Engels, Bernd

    2014-01-01

    About 35 years after its first suggestion, QM/MM became the standard theoretical approach to investigate enzymatic structures and processes. The success is due to the ability of QM/MM to provide an accurate atomistic picture of enzymes and related processes. This picture can even be turned into a movie if nuclei-dynamics is taken into account to describe enzymatic processes. In the field of organic chemistry, QM/MM methods are used to a much lesser extent although almost all relevant processes happen in condensed matter or are influenced by complicated interactions between substrate and catalyst. There is less importance for theoretical organic chemistry since the influence of nonpolar solvents is rather weak and the effect of polar solvents can often be accurately described by continuum approaches. Catalytic processes (homogeneous and heterogeneous) can often be reduced to truncated model systems, which are so small that pure quantum-mechanical approaches can be employed. However, since QM/MM becomes more and more efficient due to the success in software and hardware developments, it is more and more used in theoretical organic chemistry to study effects which result from the molecular nature of the environment. It is shown by many examples discussed in this review that the influence can be tremendous, even for nonpolar reactions. The importance of environmental effects in theoretical spectroscopy was already known. Due to its benefits, QM/MM can be expected to experience ongoing growth for the next decade.In the present chapter we give an overview of QM/MM developments and their importance in theoretical organic chemistry, and review applications which give impressions of the possibilities and the importance of the relevant effects. Since there is already a bunch of excellent reviews dealing with QM/MM, we will discuss fundamental ingredients and developments of QM/MM very briefly with a focus on very recent progress. For the applications we follow a similar

  8. Valuing spectrum at mm wavelengths for cellular networks

    OpenAIRE

    Shaw, B. A.; Beltrán, H. F.; Sowerby, K. W.

    2017-01-01

    This paper investigates the economic value of spectrum at mm wavelengths. The analysis uses four techniques to value spectrum, namely a benchmarking comparison, a discounted cash flow analysis, a real options approach and a deprival method. The methods to calculate spectrum value presented in this paper can be used for any spectrum band and in any country. However, to determine the value of mm wavelengths for cellular networks, we have used data from New Zealand, specifically for the existing...

  9. A comparative study of shadow shield whole body monitor incorporated with 203 mm dia. x 102 mm thick and 102 mm dia. x 76 mm thick NaI(TI) detectors

    International Nuclear Information System (INIS)

    Sankhla, Rajesh; Singh, I.S.; Rao, D.D.

    2016-01-01

    The whole body counting using Shadow Shield Whole Body Monitor (SSWBM) proved to be a popular method for assessment of internal contamination due to high energy gamma (E>200 keV) emitting radio nuclides that got inadvertently incorporated in the occupational workers. Currently ∼ 5 SSWBMs are operational at various DAE nuclear facilities throughout the country. The shielding of SSWBMs are said to be designed for 102 mm x 76 mm NaI(Tl) detector and over a period of time, the same concept is being followed. At present, the number of subjects monitored per annum has increased significantly compared to earlier years due to the increase in nuclear facilities at different sites and also increase in number of contract personnel. Aim of this study is to develop/upgrade the existing SSWBMs to increase their capabilities in terms of throughput without compromising on sensitivity. This work includes response studies of individual detectors of sizes 102 mm x 76 mm and 203 mm x 102 mm housed in SSWBM in terms of background, efficiency and Minimum Detection Activity (MDA) for different gamma emitting radio nuclides using Bhabha Atomic Research Centre reference Bottle Mannequin ABsorption (BOMAB) phantom

  10. QM/MM free energy simulations: recent progress and challenges

    Science.gov (United States)

    Lu, Xiya; Fang, Dong; Ito, Shingo; Okamoto, Yuko; Ovchinnikov, Victor

    2016-01-01

    Due to the higher computational cost relative to pure molecular mechanical (MM) simulations, hybrid quantum mechanical/molecular mechanical (QM/MM) free energy simulations particularly require a careful consideration of balancing computational cost and accuracy. Here we review several recent developments in free energy methods most relevant to QM/MM simulations and discuss several topics motivated by these developments using simple but informative examples that involve processes in water. For chemical reactions, we highlight the value of invoking enhanced sampling technique (e.g., replica-exchange) in umbrella sampling calculations and the value of including collective environmental variables (e.g., hydration level) in metadynamics simulations; we also illustrate the sensitivity of string calculations, especially free energy along the path, to various parameters in the computation. Alchemical free energy simulations with a specific thermodynamic cycle are used to probe the effect of including the first solvation shell into the QM region when computing solvation free energies. For cases where high-level QM/MM potential functions are needed, we analyze two different approaches: the QM/MM-MFEP method of Yang and co-workers and perturbative correction to low-level QM/MM free energy results. For the examples analyzed here, both approaches seem productive although care needs to be exercised when analyzing the perturbative corrections. PMID:27563170

  11. The mm-wave compact component of AGN

    Science.gov (United States)

    Behar, Ehud; Vogel, Stuart; Baldi, Ranieri D.; Smith, Krista L.; Mushotzky, Richard F.

    2018-05-01

    mm-wave emission from Active Galactic Nuclei (AGN) may hold the key to understanding the physical origin of their radio cores. The correlation between radio/mm and X-ray luminosity may suggest a similar physical origin of the two sources. Since synchrotron self absorption decreases with frequency, mm-waves probe smaller length scales than cm-waves. We report on 100 GHz (3 mm) observations with CARMA of 26 AGNs selected from the hard X-ray Swift/BAT survey. 20/26 targets were detected at 100 GHz down to the 1 mJy (3σ) sensitivity, which corresponds to optically thick synchrotron source sizes of 10-4 - 10-3 pc. Most sources show a 100 GHz flux excess with respect to the spectral slope extrapolated from low frequencies. This mm spectral component likely originates from smaller scales than the few-GHz emission. The measured mm sources lie roughly around the Lmm (100 GHz) ˜10-4LX (2-10 keV) relation, similar to a few previously published X-ray selected sources, and hinting perhaps at a common coronal origin.

  12. Broadband Mm-Wave OFDM Communications in Doubly Selective Channel: Performance Evaluation Using Measured Mm-Wave Channel

    DEFF Research Database (Denmark)

    Chen, Xiaoming; Fan, Wei; Pedersen, Gert F.

    2018-01-01

    In this work, we evaluate the performance of the broadband millimeter-wave (mm-wave) OFDM system in the presence of phase noise (PN) of phase-locked loop based oscillator and delay spread of measured mm-wave channel. It is shown, using Akaike's information criterion, that the channel tap...... coefficients of the broadband mm-wave channel do not follow Gaussian distribution due to the broad bandwidth. It is also shown that, given a cyclic prefix (CP) length for a certain delay spread, an effective PN mitigation scheme enables a PN corrupted OFDM system to function with small subcarrier spacing and...

  13. Safety analysis for testing operation of the RA reactor in the Boris Kidric Institute, Vinca; Analiza sigurnosti rada reaktora 'RA' za probni rad u Institutu za nuklearne nauke 'Boris Kidric' - Vinca

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-09-15

    This safety report covers detailed description of the RA reactor core, reactor components, coolant system, control system, safety system, reactor building including site characteristics. A separate chapter is devoted to radiation protection and radioactive waste management. Organizational structure od the reactor staff as well as training program are included. The last chapter includes detailed emergency plans for three accidents classified in three categories. [Serbo-Croat] Ovaj izvestaj sadrzi detaljan opis reaktora RA, sistema za hladjenje, kontolno-sigurnosnog sistema, elektricnog sistema, zgrade sa instalacijama, ukljucujuci karakteristike lokacije. Posebno poglavlje opisuje sistem zastite od zracenja i rukovanje radioaktivnim otpadom. Opisana je organizacija rada i program obuke osoblja. Poslednje poglavlje sadrzi detaljan plan mera za slucaj udesa klasifikovanih u tri kategorije.

  14. QM/MM Calculations with deMon2k

    Directory of Open Access Journals (Sweden)

    Dennis R. Salahub

    2015-03-01

    Full Text Available The density functional code deMon2k employs a fitted density throughout (Auxiliary Density Functional Theory, which offers a great speed advantage without sacrificing necessary accuracy. Powerful Quantum Mechanical/Molecular Mechanical (QM/MM approaches are reviewed. Following an overview of the basic features of deMon2k that make it efficient while retaining accuracy, three QM/MM implementations are compared and contrasted. In the first, deMon2k is interfaced with the CHARMM MM code (CHARMM-deMon2k; in the second MM is coded directly within the deMon2k software; and in the third the Chemistry in Ruby (Cuby wrapper is used to drive the calculations. Cuby is also used in the context of constrained-DFT/MM calculations. Each of these implementations is described briefly; pros and cons are discussed and a few recent applications are described briefly. Applications include solvated ions and biomolecules, polyglutamine peptides important in polyQ neurodegenerative diseases, copper monooxygenases and ultra-rapid electron transfer in cryptochromes.

  15. Activity of the Service for maintenance of mechanical structures of the RA reactor - Report for 1980, Annex II; Prilog II - Rad sluzbe za odrzavanje masinske opreme reaktora RA - Izvestaj za 1980. god

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1980-12-15

    Service for mechanical components at the RA reactor includes: control and maintenance of utility components, mechanical workshop, hot cells and storage. Control and maintenance of main components covers: reactor core, heavy water system, technical water system, gas system. This service is responsible for the following auxiliary systems: transportation units; spent fuel storage pool; special ventilation system; personal protection appliances; hot cells. Maintenance of the reactor building, ventilation, heating, water supply, sewage, fire protection devices, gas and compressed air systems are included. [Serbo-Croat] Sluzba za masinsku opremu nuklearnog reaktora RA obuhvata: kontrolu i odrzavanje masinske opreme postrojenja, masinsku radionicu, vruce komore i prirucni magacin. Kontrola i odrzavanje osnovnih sistema obuhvata centralno telo reaktora, sistem teske vode, sistem tehnicke vode, gasni sistem. Pomocni sistemi koji spadaju u delatnost ove sluzbe su: transportna oprema, bazen za odlezavanje ozracenog goriva, sistem specijalne ventilacije, licna zastitna sredstva, vruce komore. Odrzavanje zgrade reaktora, ventilacije i grejanja, vodovoda i kanalizacije, opreme za protivpozarnu zastitu, instalacije gasa i komprimovanog vazduha su takode zadatak ove Sluzbe.

  16. Wear Characteristics of Hybrid Composites Based on Za27 Alloy Reinforced With Silicon Carbide and Graphite Particles

    Directory of Open Access Journals (Sweden)

    S. Mitrović

    2014-06-01

    Full Text Available The paper presents the wear characteristics of a hybrid composite based on zinc-aluminium ZA27 alloy, reinforced with silicon-carbide and graphite particles. The tested sample contains 5 vol.% of SiC and 3 vol.% Gr particles. Compocasting technique has been used to prepare the samples. The experiments were performed on a “block-on-disc” tribometer under conditions of dry sliding. The wear volumes of the alloy and the composite were determined by varying the normal loads and sliding speeds. The paper contains the procedure for preparation of sample composites and microstructure of the composite material and the base ZA27 alloy. The wear surface of the composite material was examined using the scanning electronic microscope (SEM and energy dispersive spectrometry (EDS. Conclusions were obtained based on the observed impact of the sliding speed, normal load and sliding distance on tribological behaviour of the observed composite.

  17. RA Research reactor, Annual report 1972; Istrazivacki nuklearni reaktor RA - Izvestaj za 1972. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1972-12-15

    During 1972, the total production was 31151 MWh which is 3.8% higher than planned. The reactor was used for irradiation and experiments according to the demand of 381 users, of which 340 from the Institute and 41 external users. This report contains detailed data about reactor power and experiments performed in 1972. Discrepancies from the action plan, meaning higher production was achieved due to special demands of the users. Total number of interruptions was lower than during all the previous years, and were caused mainly due to announced power cuts. There was only on scram shutdown during this year caused by a false signal of the reactor control instrumentation. There were no longer interruptions. One shorter interruption (shorter than 24 hours) caused by removal of a UO{sub 2} capsule from the core, placed there for measuring heat transfer. Total personnel exposure dose was lower than during previous years. One accident caused contamination with gases and aerosols containing mainly shot-living isotopes. Decontamination od surfaces was less than during previous years. Practically there was no surface contamination that would demand action of the decontamination team, except for the regular decontamination after refueling. It was concluded that the successful operation in 1972 has a special significance having taking in account the financial crisis caused by the unresolved status of the reactor. It is emphasised, in the plan for the next year that there is an urgent need of making a long-term plan of rector application. It is indispensable to finish preparatory tasks for replacing the fuel with the highly enriched fuel elements by 1974, and building the core emergency cooling system. [Serbo-Croat] Ukupni rad Reaktora RA je u 1972. godini iznosio je 31151 MWh odnosno 3,8% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 381 korisnika od cega 340 iz Instituta i 41 za korisnike izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i

  18. RA Research reactor, Annual report 1968 - Operation and maintenance; Istrazivacki nuklearni reaktor RA - Izvestaj za 1968. godinu - Pogon i odrzavanje

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, D et al. [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1968-12-15

    During 1968, the RA Reactor was operated at nominal power of 6.5 MW for 190 days, and during 50 days at lower power levels. Total production amounted to 31051 MWh which is 3.5% higher than planned. reactor was used for irradiation and experiments according to the demand of 600 users, of which 517 from the Institute and 83 externals users. This report contains detailed data about reactor power and experiments performed in 1968. It is concluded that the reactor operation was more successful than during previous years. There was only one longer interruption which lasted 27 hours because of the power cut on the cable for the pump station on Danube. Number of safety shutdowns were at the same level as during last year. The only significant incident in 1968 was air contamination with the radioactive argon in the reactor hall. The reactor operation was not interrupted although the hall was evacuated for two hours. The was no significant exposure of the staff. In April and September the integral dosed were higher than during other months because of the accident during refueling (mixing the slugs with irradiated and fresh fuel). There was no significant surface contamination, i.e. the decontaminated surface were negligible. Due to 'mixing' refueling scheme. [Serbo-Croat] Reaktor RA je u 1968. godini radio na nominalnoj snazi od 6,5 MW 190 dana i 50 dana na manjim snagama. Ukupni rad iznosio je 31051 MWh odnosno 3,5% vise od planiranog. Reaktor je koriscen za ozracivanja i eksperimente za 600 korisnika od cega 517 iz Instituta i 83 za korisnika izvan Instituta. Ovaj izvestaj sadrzi detaljne podatke o radu i eksperimentima koji su obavljani. Zakljucuje se da je reaktor radio uspesnije nego prethodnih godina. U toku 1968. godine samo je jedan duzi prekid u radu od 27 casova izazvan zbog proboja kablovske glave na odvodu za pumpnu stanicu na Dunavu. Sigurnosna zaustavljanja bila su na proslogodisnjem nivou. Jedini znacajniji incident u 1968. godini, bio je kontaminacija vazduha

  19. PODJETNIŠTVO ZA ŽENSKE - VPLIV PODJETNIŠKEGA UDEJSTVOVANJA NA ŽIVLJENSKO ZADOVOLJSTVO

    OpenAIRE

    Velcer, Maja

    2016-01-01

    Podjetništvo že od nekdaj velja za specifični način kariernega udejstvovanja, katerega se lotijo tisti posamezniki, ki še posebej cenijo neodvisnost in svobodo pri življenjskih odločitvah. V tem smislu podjetništvo ni zgolj način kariernega delovanja, pač pa gre za način življenja, ki podjetniku omogoča izpolnjevanje lastnega potenciala na najvišjem nivoju. Če je torej podjetništvo način življenja, potem nas zanima ali je lahko tudi pomemben dejavnik pri doseganju življenjskega zadovo...

  20. Experimentally stabilized superconducting magnet with inner diameter of 700 mm

    Energy Technology Data Exchange (ETDEWEB)

    Vetlitskii, I A; Belonogov, A V; Dobrov, V M; Krylov, V L; Lebedev, A V; Lomkatsi, G S; Nilov, A F; Smolyankin, V T

    1974-05-01

    An experimental magnet, SPM-70, with the following characteristics was constructed. The inner diameter of the winding was 730 mm; outer diameter of the winding 1000 mm; height of winding 310 mm; magnetic induction at the center of the magnet 1.45 T; maximum magnetic induction 2.4 T; operation current 820 A; ampere-turns 1.07 x 10/sup 6/; design current density 2560 A/cm/sup 2/; stored energy 500 kJ; superconducting alloy Nb+50% Zr; weight of superconductor 23 kg; weight of copper 210 kg; resistivity of the copper in the strips at T = 4.2 K, B = 2.5 T, 2.6 x 10/sup -8/ ..cap omega.. cm.

  1. Trace analysis for 300 MM wafers and processes with TXRF

    International Nuclear Information System (INIS)

    Nutsch, A.; Erdmann, V.; Zielonka, G.; Pfitzner, L.; Ryssel, H.

    2000-01-01

    Efficient fabrication of semiconductor devices is combined with an increasing size of silicon wafers. The contamination level of processes, media, and equipment has to decrease continuously. A new test laboratory for 300 mm was installed in view of the above mentioned aspects. Aside of numerous processing tools this platform consist electrical test methods, particle detection, vapor phase decomposition (VPD) preparation, and TXRF. The equipment is installed in a cleanroom. It is common to perform process or equipment control, development, evaluation and qualification with monitor wafers. The evaluation and the qualification of 300 mm equipment require direct TXRF on 300 mm wafers. A new TXRF setup was installed due to the wafer size of 300 mm. The 300 mm TXRF is equipped with tungsten and molybdenum anode. This combination allows a sensitive detection of elements with fluorescence energy below 10 keV for tungsten excitation. The molybdenum excitation enables the detection of a wide variety of elements. The detection sensitivity for the tungsten anode excited samples is ten times higher than for molybdenum anode measured samples. The system is calibrated with 1 ng Ni. This calibration shows a stability within 5 % when monitored to control system stability. Decreasing the amount of Ni linear results in a linear decrease of the measured Ni signal. This result is verified for a range of elements by multielement samples. New designs demand new processes and materials, e.g. ferroelectric layers and copper. The trace analysis of many of these materials is supported by the higher excitation energy of the molybdenum anode. Reclaim and recycling of 300 mm wafers demand for an accurate contamination control of the processes to avoid cross contamination. Polishing or etching result in modified surfaces. TXRF as a non-destructive test method allows the simultaneously detection of a variety of elements on differing surfaces in view of contamination control and process

  2. 450mm wafer patterning with jet and flash imprint lithography

    Science.gov (United States)

    Thompson, Ecron; Hellebrekers, Paul; Hofemann, Paul; LaBrake, Dwayne L.; Resnick, Douglas J.; Sreenivasan, S. V.

    2013-09-01

    The next step in the evolution of wafer size is 450mm. Any transition in sizing is an enormous task that must account for fabrication space, environmental health and safety concerns, wafer standards, metrology capability, individual process module development and device integration. For 450mm, an aggressive goal of 2018 has been set, with pilot line operation as early as 2016. To address these goals, consortiums have been formed to establish the infrastructure necessary to the transition, with a focus on the development of both process and metrology tools. Central to any process module development, which includes deposition, etch and chemical mechanical polishing is the lithography tool. In order to address the need for early learning and advance process module development, Molecular Imprints Inc. has provided the industry with the first advanced lithography platform, the Imprio® 450, capable of patterning a full 450mm wafer. The Imprio 450 was accepted by Intel at the end of 2012 and is now being used to support the 450mm wafer process development demands as part of a multi-year wafer services contract to facilitate the semiconductor industry's transition to lower cost 450mm wafer production. The Imprio 450 uses a Jet and Flash Imprint Lithography (J-FILTM) process that employs drop dispensing of UV curable resists to assist high resolution patterning for subsequent dry etch pattern transfer. The technology is actively being used to develop solutions for markets including NAND Flash memory, patterned media for hard disk drives and displays. This paper reviews the recent performance of the J-FIL technology (including overlay, throughput and defectivity), mask development improvements provided by Dai Nippon Printing, and the application of the technology to a 450mm lithography platform.

  3. Microcoaxial cataract surgery outcomes: comparison of 1.8 mm system and 2.2 mm system.

    Science.gov (United States)

    Lee, Kyung-Min; Kwon, Hyung-Goo; Joo, Choun-Ki

    2009-05-01

    To compare clinical outcomes of a 1.8 mm and a 2.2 mm microcoaxial cataract surgery system. Department of Ophthalmology and Visual Science, Kangnam St. Mary's Hospital, College of Medicine, Catholic University of Korea, Seoul, Korea. In a prospective study, eyes were randomly selected to have phacoemulsification using a Stellaris system or an Intrepid Infiniti system. The initial incision size was 1.8 mm and 2.2 mm, respectively. Measured intraoperative parameters included phacoemulsification time, mean cumulative dissipated ultrasound energy (CDE), change in incision size at each step of surgery, and total volume of balanced salt solution (BSS) used. The best corrected visual acuity (BCVA), corneal astigmatism, corneal thickness, and endothelial cell count were evaluated preoperatively and postoperatively. The study evaluated 86 eyes of 78 patients (43 eyes in each group). There were no significant differences in postoperative BCVA, surgically induced astigmatism, or amount of BSS used between the 2 systems (P >.05). However, for high-density cataracts, the 1.8 mm group had a greater change between the initial incision size and the incision size after phacoemulsification (P = .019, nuclear opalescence [NO] NO3; P = .001, NO4), a longer phacoemulsification time (P = .013, NO3), greater mean CDE (P = .005, NO3; P = .001, NO4), and greater corneal endothelial cell loss (P = .003, NO4). Both systems were safe and effective in microcoaxial phacoemulsification. The 1.8 mm system performed better with cortical-type cataract and the 2.2 mm system, with high-density nuclear-type cataract.

  4. Ra reactor operation plan for 1976 - Annex 6; Prilog 6 - Plan rada reaktora RA za 1976. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Martinc, R [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    Contrary to previous years the RA reactor operation plan for 1976 is conditioned by more uncertainties than ever for the following reasons. It is planned for February to repair the components in order to eliminate the consequences of leaking from the vertical experimental channel VK-4 which happened in december 1975. Apart from this, measurements related to transfer of the core to highly enriched fuel under minimum power are foreseen to be performed in February. In April, it would be indispensable to locate the point of He gas leaking and its prevention. Core transfer to highly enriched fuel is planned for April for testing of the fuel elements under operating conditions and step by step increase of the power density up to the nominal power. Complete plan for core transfer would be available by the end of February 1976. It is planned to make-up for the mentioned delays from May-December 1976. [Serbo-Croat] Za razliku od prethodnih godina izrada plana rada reaktora RA za 1976. godinu vezana je za mnogo vise neizvesnosti nego ikada ranije iz sledecih razloga. U februaru se vrsi remont opreme i uklanjanja posledica procurivanja vertikalnog eksperimentalog kanala VK-4, koje se dogodilo decembra 1975. Sem toga u februaru se vrse merenja na minimalnim snagama u sklopu priprema za prelazak na novo gorivo. U aprilu ce biti neophodno lociranje mesta gde istice He gas kao i otklanjanje uzroka ovog curenja. Planirano je da se u aprilu ubaci novo gorivo u jezgro u cilju testiranja pod radnim uslovima uz postepeno povecanje snage do nominalne. Planirano je da se smanjeni obim rada usled navedenih uslova nadoknadi u potpunosti u periodu maj-decembar 1976.

  5. Exploring the Potentials of Lysinibacillus sphaericus ZA9 for Plant Growth Promotion and Biocontrol Activities against Phytopathogenic Fungi

    Directory of Open Access Journals (Sweden)

    Zakira Naureen

    2017-08-01

    Full Text Available There is an ongoing hunt for biologically active compounds that can combat phytopathogenic fungi and improve plant growth without causing any hazards to the environment. Consequently the present study aims at deciphering the plant growth promotion and antifungal capability of Lysinibacillus sphaericus ZA9. The bacterium was previously isolated and identified in our laboratory from maize rhizosphere using 16S rRNA gene sequencing. The test bacterium L. sphaericus ZA9 was found to produce high quantity of IAA (697 μg/ mL; siderophores (195.79 μg/ mL, HCN and hydrolytic enzyme as compared to the reference strain Bacillus sphaericus Z2-7. The bacterium was also capable of solubilizing silicates (Si, phosphates (P, and potassium (K. The bacterium enhanced the seedling vigor and germination of seeds pretreated with it and promoted the shoot length of both cucumber and tomato seeds in greenhouse experiment. L. sphaericus ZA9 and its cell free culture supernatant showed varied antagonistic behavior against Alternaria alternata, Curvularia lunata, Aspergillus sp., Sclerotinia sp., Bipolaris spicifera, Trichophyton sp. Fermentation broth culture of L. sphaericus ZA9 was then used to isolate antifungal metabolites by silica column chromatography. Identification and determination of antifungal compounds was carried out by Thin-layer chromatography (TLC followed by NMR spectroscopy. Two compounds were isolated and identified as 2-pentyl-4-quinolinecarboxylic acid (C15H17NO2 which is a quinoline alkaloid and 1- methylcyclohexene which is a cycloalkene. Compound 1; 2-Penthyl-4-quinolinecarboxylic acid was found to be highly antagonistic against most of the fungi tested as compared to the bacterium itself. Its activity was comparable to that of fungicide Benlate, while compound 2; 1- methylcyclohexene did not show any antifungal activity.

  6. Combined quantum and molecular mechanics (QM/MM).

    Science.gov (United States)

    Friesner, Richard A

    2004-12-01

    We describe the current state of the art of mixed quantum mechanics/molecular mechanics (QM/MM) methodology, with a particular focus on modeling of enzymatic reactions. Over the past decade, the effectiveness of these methods has increased dramatically, based on improved quantum chemical methods, advances in the description of the QM/MM interface, and reductions in the cost/performance of computing hardware. Two examples of pharmaceutically relevant applications, cytochrome P450 and class C β-lactamase, are presented.: © 2004 Elsevier Ltd . All rights reserved.

  7. MM-rallin vaikutus Toyotan brändiin

    OpenAIRE

    Laurila, Heini

    2017-01-01

    Tämän insinöörityön tarkoituksena oli selvittää, millainen vaikutus MM-ralliin palaamisella on Toyotan brändiin Suomessa. Insinöörityö toteutettiin yhteistyössä Suomen Toyotan ja Lexuksen maahantuojayrityksen, Toyota Auto Finland Oy:n sekä AKK Sports Oy:n kanssa. AKK Sports Oy on vastuussa vuosittaisen Suomen MM-ralliosakilpailun, Neste Rallin, järjestämisestä. Tutkimuksen taustatyönä tutustuttiin ensin brändejä ja markkinointia koskevaan kirjallisuuteen. Sen lisäksi käytiin läpi Toyotan ...

  8. Computational Modeling in Plasma Processing for 300 mm Wafers

    Science.gov (United States)

    Meyyappan, Meyya; Arnold, James O. (Technical Monitor)

    1997-01-01

    Migration toward 300 mm wafer size has been initiated recently due to process economics and to meet future demands for integrated circuits. A major issue facing the semiconductor community at this juncture is development of suitable processing equipment, for example, plasma processing reactors that can accomodate 300 mm wafers. In this Invited Talk, scaling of reactors will be discussed with the aid of computational fluid dynamics results. We have undertaken reactor simulations using CFD with reactor geometry, pressure, and precursor flow rates as parameters in a systematic investigation. These simulations provide guidelines for scaling up in reactor design.

  9. Piezoelectric ultrasonic micromotor with 1.5 mm diameter.

    Science.gov (United States)

    Dong, Shuxiang; Lim, Siak P; Lee, Kwork H; Zhang, Jingdong; Lim, Leong C; Uchino, Kenji

    2003-04-01

    A piezoelectric ultrasonic micromotor has been developed using a lead zirconate titanate (PZT) ceramic/metal composite tube stator that was 1.5 mm in diameter and 7 mm in length. The micromotor was operated in its first bending vibration mode (approximately 70 kHz), producing speeds from hundreds to over 2000 rpm in both rotational directions. The maximum torque-output was 45 microN-m, which is far superior to previous PZT thin film-based micromotors. This micromotor showed good reliability and stability for more than 300 hours of continued operation.

  10. QM/MM hybrid calculation of biological macromolecules using a new interface program connecting QM and MM engines

    Energy Technology Data Exchange (ETDEWEB)

    Hagiwara, Yohsuke; Tateno, Masaru [Graduate School of Pure and Applied Sciences, University of Tsukuba, Tennodai 1-1-1, Tsukuba Science City, Ibaraki 305-8571 (Japan); Ohta, Takehiro [Center for Computational Sciences, University of Tsukuba, Tennodai 1-1-1, Tsukuba Science City, Ibaraki 305-8577 (Japan)], E-mail: tateno@ccs.tsukuba.ac.jp

    2009-02-11

    An interface program connecting a quantum mechanics (QM) calculation engine, GAMESS, and a molecular mechanics (MM) calculation engine, AMBER, has been developed for QM/MM hybrid calculations. A protein-DNA complex is used as a test system to investigate the following two types of QM/MM schemes. In a 'subtractive' scheme, electrostatic interactions between QM/MM regions are truncated in QM calculations; in an 'additive' scheme, long-range electrostatic interactions within a cut-off distance from QM regions are introduced into one-electron integration terms of a QM Hamiltonian. In these calculations, 338 atoms are assigned as QM atoms using Hartree-Fock (HF)/density functional theory (DFT) hybrid all-electron calculations. By comparing the results of the additive and subtractive schemes, it is found that electronic structures are perturbed significantly by the introduction of MM partial charges surrounding QM regions, suggesting that biological processes occurring in functional sites are modulated by the surrounding structures. This also indicates that the effects of long-range electrostatic interactions involved in the QM Hamiltonian are crucial for accurate descriptions of electronic structures of biological macromolecules.

  11. Test of freonless operation of resistive plate chambers with glass electrodes--1 mm gas gap vs 2 mm gas gap

    CERN Document Server

    Sakaue, H; Takahashi, T; Teramoto, Y

    2002-01-01

    Non-freon gas mixtures (Ar/iso-C sub 4 H sub 1 sub 0) were tested as the chamber gas for 1 and 2 mm gas gap Resistive Plate Chambers (RPCs) with float glass as the resistive electrodes, operated in the streamer mode. With the narrower (1 mm) gas gap, streamer charge is reduced (approx 1/3), which reduces the dead time (and dead area), associated with each streamer, improving the detection efficiency. The best performance was obtained for two cases: Ar/iso-C sub 4 H sub 1 sub 0 =50/50 and 60/40. For the 50/50 mixture, a detection efficiency of better than 98% was obtained for the 1 mm gap RPC, while the efficiency was 95% for the 2 mm gap RPC, each operated as a double-gap RPC. The measured time resolution (rms) was 1.45+-0.05 (2.52+-0.09) ns for the 1 (2) mm gap RPC for the 50/50 mixture.

  12. Influence of Striking Edge Radius (2 mm versus 8 mm) on Instrumented Charpy Data and Absorbed Energies

    Energy Technology Data Exchange (ETDEWEB)

    Lucon, E.

    2008-08-15

    The most commonly used test standards for performing Charpy impact tests (ISO 148 and ASTM E 23) envisage the use of strikers having different radii of the striking edge, i.e. 2 mm (ISO) and 8 mm (ASTM). The effect of striker geometry on Charpy results was extensively studied in the past in terms of absorbed energy measured by the machine encoder, but few investigations are available on the influence of striker configuration on the results of instrumented Charpy tests (characteristic forces, displacements and integrated energy). In this paper, these effects are investigated based on the analysis of published results from three interlaboratory studies and some unpublished Charpy data obtained at SCK-CEN. The instrumented variables which are the most sensitive to the radius of the striking edge are the maximum force and its corresponding displacement, with 8mm-strikers providing systematically higher values. Absorbed energies, obtained both from the instrumented trace and from the pendulum encoder, are almost insensitive to the type of striker up to 200 J. For higher energy levels, the values obtained from 8mm strikers become progressively larger. Data scatter is generally higher for 2mm-strikers.

  13. QM/MM-MD simulations of conjugated polyelectrolytes

    DEFF Research Database (Denmark)

    Sjöqvist, Jonas; Linares, Mathieu; Mikkelsen, Kurt Valentin

    2014-01-01

    A methodological development is reported for the study of luminescence properties of conjugated polyelectrolytes, encompassing systems in which dihedral rotational barriers are easily overcome at room temperature. The components of the model include (i) a molecular mechanics (MM) force field desc...

  14. Film Editing Handbook; Technique of 16mm Film Cutting.

    Science.gov (United States)

    Churchill, Hugh B.

    Designed to help the film student with the complexities of 16mm film cutting, this handbook catalogs the mechanical procedures of both picture and sound cutting and supplies step-by-step explanations of these procedures. Because the handbook was organized so that it could be used while working at the cutting bench, common cutting problems and…

  15. Millimeter wave VAlidation STandard (mm-VAST) antenna

    DEFF Research Database (Denmark)

    Kim, Oleksiy S.

    This document summarizes the main results of the project “Millimeter wave VAlidation STandard (mm-VAST) antenna” completed by the Technical University of Denmark (DTU) in collaboration with Danish company TICRA for the European Space Agency (ESA) under ESA contract no. 4000109866/13/NL/MH....

  16. Millimeter wave VAlidation STandard (mm-VAST) antenna. Abstract

    DEFF Research Database (Denmark)

    Kim, Oleksiy S.

    This document outlines the background, objectives and the main results of the project “Millimeter wave VAlidation STandard (mm-VAST) antenna” completed by the Technical University of Denmark (DTU) in collaboration with Danish company TICRA for the European Space Agency (ESA) under ESA contract no...

  17. Radioimmunoassay of creatine kinase isoenzymes in human serum: isoenzyme MM

    International Nuclear Information System (INIS)

    Van Steirteghem, A.C.; Zweig, M.H.; Schechter, A.N.

    1978-01-01

    Measurement of the mass concentration of serum enzymes by radioimmunoassay provides direct quantitation of specific isoenzymes and may be less subject to some of the limitations of traditional assay procedures for enzymes. We describe the development of a sensitive and specific radioimmunoassay for the muscle isoenzyme of creatine kinase, CK-MM, in human serum. CK-MM, purified from human skeletal muscle, was used to raise high-titer antisera and for iodination by the Chloramine T method. The radioimmunoassay required 50 μl of sample, utilized a double-antibody separation method, and was completed in 24 h. Cross reactivity with CK-BB was virtually zero, 3 to 17 percent with CK-MB. The mass concentration of CK-MM in the serum of healthy subjects ranged from 36 to 1668 μg/liter and correlated closely with total CK enzymatic activity. Serum concentrations of CK-MM from casually selected patients correlated less well with total CK enzymatic activity, suggesting the existence of other CK isoenzymes or the presence of inactive forms

  18. Performance of 4mm impact sprinklers at different spacing within ...

    African Journals Online (AJOL)

    Irrigation Engineers in Zimbabwe use the 12 m x 18 m spacing for the design of the sprayline, using 4 mm nozzle sprinklers. A study was conducted to determine performance and cost effectiveness of other spacings that can be used in sprinkler irrigation systems design. The main targeted spacings were a square layout of ...

  19. Two-port laparoscopic ovarian cystectomy using 3-mm instruments

    Directory of Open Access Journals (Sweden)

    Naoyuki Yoshiki

    2016-05-01

    Conclusion: Two-port laparoscopic ovarian cystectomy using 3-mm instruments is a feasible and safe approach by which surgeons expert in conventional multiport laparoscopy achieve minimally invasive surgery with low morbidity and a low rate of conversion to the conventional approach.

  20. Research nuclear reactor RA - Annual Report 1994; Istrazivacki nuklearni reaktor RA - Izvestaj za 1994. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1994-12-01

    pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije je u toku, ali njegova realizacija u 1994. godini kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Izradu ove opreme finansira Medjunarodna agencija za atomsku energiju kroz ugovor sklopljen decembra 1988. godine sa moskovskom firmom Atomenergoexport. Prema tom ugovoru trebalo je da celokupna nova instrumentacija za reaktor RA bude isporucena Institutu u Vinci do kraja 1990. godine, ali je do septembra 1991. godine isporuceno svega 56% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju izrecena od strane ove organizacije Ujedinjenih nacija. U 1991. godini na reaktoru RA je demontirana postojeca instrumentacija u maksimalno mogucem obimu, kako bi se zadrzala neka osnovna merenja neophodna i u uslovima kada reaktor nije u pogonu. U 1994. godini nastavljen je rad na razradi i dopuni sovjetskog projekta. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Veoma obiman remont sekundarnog kola hladjenja reaktora privodi se kraju i bice okoncan u prvoj polovini 1995. a u skladu postojecim zakonskim propisima i sa preporukama MAAE. Kontrola goriva od strane inspektora MAAE obavljana je jedanput mesecno. Na reaktoru RA u 1994. godini radilo je prosecno 47 radnika, sto je dovoljan broj u uslovima remontnih i investicionih radova.

  1. Broadband Mm-Wave OFDM Communications in Doubly Selective Channel: Performance Evaluation Using Measured Mm-Wave Channel

    DEFF Research Database (Denmark)

    Chen, Xiaoming; Fan, Wei; Pedersen, Gert F.

    2018-01-01

    coefficients of the broadband mm-wave channel do not follow Gaussian distribution due to the broad bandwidth. It is also shown that, given a cyclic prefix (CP) length for a certain delay spread, an effective PN mitigation scheme enables a PN corrupted OFDM system to function with small subcarrier spacing and......In this work, we evaluate the performance of the broadband millimeter-wave (mm-wave) OFDM system in the presence of phase noise (PN) of phase-locked loop based oscillator and delay spread of measured mm-wave channel. It is shown, using Akaike's information criterion, that the channel tap......, therefore, small CP overhead, with only slight degradation of the error rate performance....

  2. Mineralogic Model (MM3.0) Analysis Model Report

    Energy Technology Data Exchange (ETDEWEB)

    C. Lum

    2002-02-12

    The purpose of this report is to document the Mineralogic Model (MM), Version 3.0 (MM3.0) with regard to data input, modeling methods, assumptions, uncertainties, limitations and validation of the model results, qualification status of the model, and the differences between Version 3.0 and previous versions. A three-dimensional (3-D) Mineralogic Model was developed for Yucca Mountain to support the analyses of hydrologic properties, radionuclide transport, mineral health hazards, repository performance, and repository design. Version 3.0 of the MM was developed from mineralogic data obtained from borehole samples. It consists of matrix mineral abundances as a function of x (easting), y (northing), and z (elevation), referenced to the stratigraphic framework defined in Version 3.1 of the Geologic Framework Model (GFM). The MM was developed specifically for incorporation into the 3-D Integrated Site Model (ISM). The MM enables project personnel to obtain calculated mineral abundances at any position, within any region, or within any stratigraphic unit in the model area. The significance of the MM for key aspects of site characterization and performance assessment is explained in the following subsections. This work was conducted in accordance with the Development Plan for the MM (CRWMS M&O 2000). The planning document for this Rev. 00, ICN 02 of this AMR is Technical Work Plan, TWP-NBS-GS-000003, Technical Work Plan for the Integrated Site Model, Process Model Report, Revision 01 (CRWMS M&O 2000). The purpose of this ICN is to record changes in the classification of input status by the resolution of the use of TBV software and data in this report. Constraints and limitations of the MM are discussed in the appropriate sections that follow. The MM is one component of the ISM, which has been developed to provide a consistent volumetric portrayal of the rock layers, rock properties, and mineralogy of the Yucca Mountain site. The ISM consists of three components: (1

  3. Mineralogic Model (MM3.0) Analysis Model Report

    International Nuclear Information System (INIS)

    Lum, C.

    2002-01-01

    The purpose of this report is to document the Mineralogic Model (MM), Version 3.0 (MM3.0) with regard to data input, modeling methods, assumptions, uncertainties, limitations and validation of the model results, qualification status of the model, and the differences between Version 3.0 and previous versions. A three-dimensional (3-D) Mineralogic Model was developed for Yucca Mountain to support the analyses of hydrologic properties, radionuclide transport, mineral health hazards, repository performance, and repository design. Version 3.0 of the MM was developed from mineralogic data obtained from borehole samples. It consists of matrix mineral abundances as a function of x (easting), y (northing), and z (elevation), referenced to the stratigraphic framework defined in Version 3.1 of the Geologic Framework Model (GFM). The MM was developed specifically for incorporation into the 3-D Integrated Site Model (ISM). The MM enables project personnel to obtain calculated mineral abundances at any position, within any region, or within any stratigraphic unit in the model area. The significance of the MM for key aspects of site characterization and performance assessment is explained in the following subsections. This work was conducted in accordance with the Development Plan for the MM (CRWMS M and O 2000). The planning document for this Rev. 00, ICN 02 of this AMR is Technical Work Plan, TWP-NBS-GS-000003, Technical Work Plan for the Integrated Site Model, Process Model Report, Revision 01 (CRWMS M and O 2000). The purpose of this ICN is to record changes in the classification of input status by the resolution of the use of TBV software and data in this report. Constraints and limitations of the MM are discussed in the appropriate sections that follow. The MM is one component of the ISM, which has been developed to provide a consistent volumetric portrayal of the rock layers, rock properties, and mineralogy of the Yucca Mountain site. The ISM consists of three components

  4. Systematic Quantum Mechanical Region Determination in QM/MM Simulation.

    Science.gov (United States)

    Karelina, Maria; Kulik, Heather J

    2017-02-14

    Hybrid quantum mechanical-molecular mechanical (QM/MM) simulations are widely used in enzyme simulation. Over ten convergence studies of QM/MM methods have revealed over the past several years that key energetic and structural properties approach asymptotic limits with only very large (ca. 500-1000 atom) QM regions. This slow convergence has been observed to be due in part to significant charge transfer between the core active site and the surrounding protein environment, which cannot be addressed by improvement of MM force fields or the embedding method employed within QM/MM. Given this slow convergence, it becomes essential to identify strategies for the most atom-economical determination of optimal QM regions and to gain insight into the crucial interactions captured only in large QM regions. Here, we extend and develop two methods for quantitative determination of QM regions. First, in the charge shift analysis (CSA) method, we probe the reorganization of electron density when core active site residues are removed completely, as determined by large-QM region QM/MM calculations. Second, we introduce the highly parallelizable Fukui shift analysis (FSA), which identifies how core/substrate frontier states are altered by the presence of an additional QM residue in smaller initial QM regions. We demonstrate that the FSA and CSA approaches are complementary and consistent on three test case enzymes: catechol O-methyltransferase, cytochrome P450cam, and hen eggwhite lysozyme. We also introduce validation strategies and test the sensitivities of the two methods to geometric structure, basis set size, and electronic structure methodology. Both methods represent promising approaches for the systematic, unbiased determination of quantum mechanical effects in enzymes and large systems that necessitate multiscale modeling.

  5. Charpy impact test results on five materials and NIST verification specimens using instrumented 2-mm and 8-mm strikers

    International Nuclear Information System (INIS)

    Nanstad, R.K.; Sokolov, M.A.

    1995-01-01

    The Heavy-Section Steel Irradiation Program at Oak Ridge National Laboratory is involved in two cooperative projects, with international participants, both of which involve Charpy V-notch impact tests with instrumented strikers of 2mm and 8mm radii. Two heats of A 533 grade B class I pressure vessel steel and a low upper-shelf (LUS) submerged-arc (SA) weld were tested on the same Charpy machine, while one heat of a Russian Cr-Mo-V forging steel and a high upper-shelf (HUS) SA weld were tested on two different machines. The number of replicate tests at any one temperature ranged from 2 to 46 specimens. Prior to testing with each striker, verification specimens at the low, high, and super high energy levels from the National Institute of Standards and Technology (NIST) were tested. In the two series of verification tests, the tests with the 2mm striker met the requirements at the low and high energy levels but not at the super high energy. For one plate, the 2mm striker showed somewhat higher average absorbed energies than those for the 8-mm striker at all three test temperatures. For the second plate and the LUS weld, however, the 2mm striker showed somewhat lower energies at both test temperatures. For the Russian forging steel and the HUS weld, tests were conducted over a range of temperatures with tests at one laboratory using the 8mm striker and tests at a second laboratory using the 2mm striker. Lateral expansion was measured for all specimens and the results are compared with the absorbed energy results. The overall results showed generally good agreement (within one standard deviation) in energy measurements by the two strikers. Load-time traces from the instrumented strikers were also compared and used to estimate shear fracture percentage. Four different formulas from the European Structural Integrity Society draft standard for instrumented Charpy test are compared and a new formula is proposed for estimation of percent shear from the force-time trace

  6. Research nuclear reactor RA - Annual Report 1997; Istrazivacki nuklearni reaktor RA - Izvestaj za 1997. godinu

    Energy Technology Data Exchange (ETDEWEB)

    Sotic, O [Vinca Institute of Nuclear Sciences, Beograd (Serbia and Montenegro)

    1997-12-01

    RA reactor is not in operation since 1984, activities related to revitalisation of the RA reactor started in 1986. The planned actions related to renewal of the reactor components were finished except for the most important action, related to exchange of complete reactor instrumentation which was delayed. Only 80% of the instrumentation was delivered until September 1991. Since then any delivery of components to Yugoslavia was stopped because of the sanctions imposed to our country. The existing RA reactor instrumentation was dismantled. Control and maintenance of the reactor components was done regularly and efficiently. Fuel inspection by the IAEA safeguards inspectors was done on a monthly basis. There have been on the average 42 employees at the RA reactor which is considered sufficient for maintenance and repair conditions. The problem of financing the reactor activities and maintenance remains unsolved. Research reactor RA Annual report for year 1997 is divided into two main parts to cover: (1) operation and maintenance and (2) activities related to radiation protection. [Serbo-Croat] Reaktor RA nije u pogonu od 1984, aktivnosti na revitalizaciji, rekostrukciji i modernizaciji reaktorski sistema zapocete su 1986. godine. Okoncan je niz zahvata na opremi postrojenja kojima ce se u narednom periodu omoguciti kontinualan i pouzdan rad ovog reaktora. Poslednji, i ujedno najveci zahvat, koji se odnosi na zamenu celokupne instrumentacije kasni zbog zastoja u isporuci opreme koja se izradjuje u Sovjetskom savezu. Do septembra 1991. godine isporuceno svega 80% od predvidjene kolicine. Od tada je svaka isporuka obustavljena, a razlog je privremena zabrana na sve isporuke opreme za Jugoslaviju usled sankcija uvedenih od strane organizacije Ujedinjenih nacija. Demontirana je postojeca instrumentacija. Kontrola i odrzavanje celopkupne opreme postrojenja, kao i remontni radovi izvrsavani su redovno i efikasno. Kontrola goriva od strane safeguard inspektora MAAE obavljana

  7. A Piezoelectric Micromotor with a Stator of φ=1.6 mm and l=4 mm Using Bulk PZT

    Science.gov (United States)

    Cagatay, Serra; Koc, Burhanettin; Moses, Paul; Uchino, Kenji

    2004-04-01

    The smallest discrete piezoelectric ultrasonic motor using bulk ceramics was developed. We are proposing basically a two-part motor: stator and rotor. The stator of the present motor consists of a hollow metal brass tube with outer diameter of 1.6 mm, inner diameter of 0.8 mm and length of only 4 mm with 2 PZT plates bonded onto it. Owing to the asymmetrical stator surface, two degenerated orthogonal bending modes were slightly split, resulting in a wobbling motion. Thus, the motor can be driven by a single driving source. The rotor is a spring, which is basically different from previous designs, pressed at both ends to the stator by a pair of ferrules. Consequently, the length of the whole motor assembly was reduced significantly; a final motor length of only 5 mm was obtained. The working frequency under zero load was approximately 227-233 kHz. Although the size is small, relatively high power was obtained under an optimized load condition: torque of 0.06 mNm, maximum power of 3.2 mW with a speed of 118 rad/s, and maximum efficiency of 11% under 48 Vrms at 221 kHz.

  8. A 300-nm compact mm-wave linac FEL design

    Energy Technology Data Exchange (ETDEWEB)

    Nassiri, A.; Kustom, R.L.; Kang, Y.W. [Argonne National Lab., IL (United States)

    1995-12-31

    Microfabrication technology offers an alternative method for fabricating precision, miniature-size components suitable for use in accelerator physics and commercial applications. The original R&D work at Argonne, in collaboration with the University of Illinois at Chicago, has produced encouraging results in the area of rf accelerating structure design, optical and x-ray masks production, deep x-ray lithography (LIGA exposures), and precision structural alignments. In this paper we will present a design study for a compact single pass mm-linac FEL to produce short wavelength radiation. This system will consists of a photocathode rf gun operated at 30 GHz, a 50-MeV superconducting constant gradient structure operated at 60 GHz, and a microundulator with 1-mm period. Initial experimental results on a scale model rf gun and microundulator will be presented.

  9. Introduction to statistics using interactive MM*Stat elements

    CERN Document Server

    Härdle, Wolfgang Karl; Rönz, Bernd

    2015-01-01

    MM*Stat, together with its enhanced online version with interactive examples, offers a flexible tool that facilitates the teaching of basic statistics. It covers all the topics found in introductory descriptive statistics courses, including simple linear regression and time series analysis, the fundamentals of inferential statistics (probability theory, random sampling and estimation theory), and inferential statistics itself (confidence intervals, testing). MM*Stat is also designed to help students rework class material independently and to promote comprehension with the help of additional examples. Each chapter starts with the necessary theoretical background, which is followed by a variety of examples. The core examples are based on the content of the respective chapter, while the advanced examples, designed to deepen students’ knowledge, also draw on information and material from previous chapters. The enhanced online version helps students grasp the complexity and the practical relevance of statistical...

  10. 9th IFToMM International Conference on Rotor Dynamics

    CERN Document Server

    2015-01-01

    This book presents the proceedings of the 9th IFToMM International Conference on Rotor Dynamics. This conference is a premier global event that brings together specialists from the university and industry sectors worldwide in order to promote the exchange of knowledge, ideas, and information on the latest developments and applied technologies in the dynamics of rotating machinery. The coverage is wide ranging, including, for example, new ideas and trends in various aspects of bearing technologies, issues in the analysis of blade dynamic behavior,  condition monitoring of different rotating machines, vibration control, electromechanical and fluid-structure interactions in rotating machinery, rotor dynamics of micro, nano, and cryogenic machines, and applications of rotor dynamics in transportation engineering. Since its inception 32 years ago, the IFToMM International Conference on Rotor Dynamics has become an irreplaceable point of reference for those working in the field, and this book reflects the high qua...

  11. Udtrækning af 10 mm ankerbolte

    DEFF Research Database (Denmark)

    Hansen, Lars Pilegaard

    Denne rapport beskriver forsøg med udtrækning af 10 mm ankerbolte udført af Laboratoriet for Bærende Konstruktioner, Instituttet for Bygningsteknik, Aalborg Universitet. Forsøgene blev udført d. 19. og 21. juni 2001. Forsøgene blev udført dels på Hjørring Sygehus og dels på Laboratoriet.......Denne rapport beskriver forsøg med udtrækning af 10 mm ankerbolte udført af Laboratoriet for Bærende Konstruktioner, Instituttet for Bygningsteknik, Aalborg Universitet. Forsøgene blev udført d. 19. og 21. juni 2001. Forsøgene blev udført dels på Hjørring Sygehus og dels på Laboratoriet....

  12. Tracking chamber made of 15-mm mylar drift tubes

    Science.gov (United States)

    Kozhin, A.; Borisov, A.; Bozhko, N.; Fakhrutdinov, R.; Plotnikov, I.

    2017-05-01

    We are presenting a drift chamber composed from three layers of mylar drift tubes with outer diameter 15 mm. The pipe is made of strip of mylar film 125 micrometers thick covered with aluminium from the both sides. A strip of mylar is wrapped around the mandrel. Pipe is created by ultrasonic welding. A single drift tube is self-supported structure withstanding 350 g wire tension without supports and internal overpressure. About 400 such tubes were assembled. Design, quality control procedures of the drift tubes are described. Seven chambers were glued from these tubes of 560 mm length. Each chamber consists of 3 layers, 16 tubes per layer. Several chambers were tested with cosmic rays. Results of the tests, counting rate plateau and coordinate resolution are presented.

  13. Tracking chamber made of 15-mm mylar drift tubes

    International Nuclear Information System (INIS)

    Kozhin, A.; Borisov, A.; Bozhko, N.; Fakhrutdinov, R.; Plotnikov, I.

    2017-01-01

    We are presenting a drift chamber composed from three layers of mylar drift tubes with outer diameter 15 mm. The pipe is made of strip of mylar film 125 micrometers thick covered with aluminium from the both sides. A strip of mylar is wrapped around the mandrel. Pipe is created by ultrasonic welding. A single drift tube is self-supported structure withstanding 350 g wire tension without supports and internal overpressure. About 400 such tubes were assembled. Design, quality control procedures of the drift tubes are described. Seven chambers were glued from these tubes of 560 mm length. Each chamber consists of 3 layers, 16 tubes per layer. Several chambers were tested with cosmic rays. Results of the tests, counting rate plateau and coordinate resolution are presented.

  14. Fusion plasma diagnostics with mm-waves an introduction

    CERN Document Server

    Hartfuss, Hans-Jürgen

    2013-01-01

    Filling a gap in the literature, this introduction to the topic covers the physics of the standard microwave diagnostics established on modern fusion experiments, and the necessary technological background from the field of microwave engineering. Written by well-known mm-wave diagnosticians in the field of fusion physics, the textbook includes such major diagnostic techniques as electron cyclotron emission, interferometry, reflectometry, polarimetry, and scattering.

  15. 1st International Conference of IFToMM Italy

    CERN Document Server

    Gasparetto, Alessandro

    2017-01-01

    This volume contains the Proceedings of the First International Conference of IFToMM Italy (IFIT2016), held at the University of Padova, Vicenza, Italy, on December 1-2, 2016. The book contains contributions on the latest advances on Mechanism and Machine Science. The fifty-nine papers deal with such topics as biomechanical engineering, history of mechanism and machine science, linkages and mechanical controls, multi-body dynamics, reliability, robotics and mechatronics, transportation machinery, tribology, and vibrations.

  16. Cerenkov maser operation at lower-mm wavelengths

    International Nuclear Information System (INIS)

    Garate, E.; Cook, R.; Heim, P.; Layman, R.; Walsh, J.

    1985-01-01

    The basic operating principles of Cerenkov maser oscillators are briefly reviewed and the experimental performance of a 3-mm device is discussed. A power level of approximately 100 kW was achieved at 88 GHz and voltage tuning from 84 to 128 GHz on the fundamental TM 01 mode was observed. Operation on higher-order modes at frequencies up to 300--320 GHz was demonstrated, and a two-stage buncher-amplifier configuration was investigated

  17. Tribological and Corrosion Properties of Coatings Produced by Plasma Electrolytic Oxidation on the ZA27 Alloy

    Science.gov (United States)

    Li, Guangyin; Mao, Yifan; Li, Zhijian; Wang, Linlin; DaCosta, Herbert

    2018-05-01

    In this paper, a continuous and dense coating was deposited on samples of the ZA27 alloy through the plasma electrolytic oxidation (PEO) process to improve its wear and corrosion performance. A nontoxic and environmentally friendly inorganic salt, Na2SiO3, is chosen as electrolytes with different concentrations. The effect of the concentration of Na2SiO3 aqueous solutions on the coating performances was investigated. The coatings with 3Al2O3·2SiO2 (mullite), Zn2SiO4 and Al2O3 (either crystal phase or with some amorphous SiO2 phases) were formed by the PEO processes. It was found that the coating thickness increased with the increase in electrolyte concentration. However, the wear and corrosion resistance performance of the coatings did not improve as the coating's thickness increased. This was due to the fact that the coating produced with electrolytes of 10 g/L has a porous structure with large pore size. Among all the samples, coating produced by 15 g/L Na2SiO3 has the best wear and corrosion resistance, which is attributed to its continuous and dense structure with thickness of about 47 μm.

  18. Tribological and Corrosion Properties of Coatings Produced by Plasma Electrolytic Oxidation on the ZA27 Alloy

    Science.gov (United States)

    Li, Guangyin; Mao, Yifan; Li, Zhijian; Wang, Linlin; DaCosta, Herbert

    2018-04-01

    In this paper, a continuous and dense coating was deposited on samples of the ZA27 alloy through the plasma electrolytic oxidation (PEO) process to improve its wear and corrosion performance. A nontoxic and environmentally friendly inorganic salt, Na2SiO3, is chosen as electrolytes with different concentrations. The effect of the concentration of Na2SiO3 aqueous solutions on the coating performances was investigated. The coatings with 3Al2O3·2SiO2 (mullite), Zn2SiO4 and Al2O3 (either crystal phase or with some amorphous SiO2 phases) were formed by the PEO processes. It was found that the coating thickness increased with the increase in electrolyte concentration. However, the wear and corrosion resistance performance of the coatings did not improve as the coating's thickness increased. This was due to the fact that the coating produced with electrolytes of 10 g/L has a porous structure with large pore size. Among all the samples, coating produced by 15 g/L Na2SiO3 has the best wear and corrosion resistance, which is attributed to its continuous and dense structure with thickness of about 47 μm.

  19. Evidence of flow stabilization in the ZaP Z pinch experiment

    International Nuclear Information System (INIS)

    Shumlak, U.; Crawford, E.; Golingo, R.P.; Nelson, B.A.; Zyrmpas, A.; Den Hartog, D.J.; Holly, D.J.

    2001-01-01

    The stabilizing effect of an axial flow on the m = 1 kink instability in Z pinches has been studied numerically with a linearized ideal MHD model to reveal that a sheared axial flow stabilizes the kink mode when the shear exceeds a threshold. The sheared flow stabilizing effect is investigated with the flow-through Z pinch experiment, ZaP. An azimuthal array of surface mounted magnetic probes located at the midplane of the 50 cm long pinch plasma measures the fluctuation levels of the azimuthal modes m=1, 2, and 3. After pinch formation a quiescent period is found where the mode activity is reduced to a few percent of the average field. Optical images from a fast framing camera and a HeNe interferometer also indicate a stable pinch plasma during this time. Doppler shift measurements of a C-III line correspond to an axial flow velocity of 9.6x10 4 m/s internal to the pinch. During the time when the axial plasma flow is high, the plasma experiences a quiescent period which lasts approximately 800 exponential growth times predicted by linear theory for a static plasma. (author)

  20. Ispitivanje pogodnosti za održavanje elektronskih uređaja / Demonstration and verification of the maintainability of electronic devices

    Directory of Open Access Journals (Sweden)

    Dragan Ćosović

    2003-11-01

    Full Text Available Ispitivanje pogodnosti za održavanje, u toku razvoja uređaja, sastavni je deo Programa i plana pogodnosti za održavanje. U toku ispitivanja proveravaju se kvantitativni i kvalitativni parametri pogodnosti za održavanje. Ispitivanje kvantitativnih parametara vrši se primenom određenih statističkih metoda. U radu je dat primer primene statističkih metoda za ispitivanje pogodnosti za korektivno održavanje jednog elektronskog uređaja i analizirani su rezultati ispitivanja. / The demonstration and verification of maintainability during the development of a device is an integral part of the Maintainability Plan and Programme. During the demonstration and verification, the quantitative and qualitative parameters of maintainability are checked. The demonstration and verification of the maintainability parameters are done by applying certain statistical methods. An example of applying a statistical methods for testing the maintainability of corrective maintenance of radio is given in the work and the results of the demonstration and verification are analyzed.

  1. Metoda ispitivanja kompatibilnosti sredstava lične NHB zaštite / Method of testing compatibility of personal NBC protection devices

    Directory of Open Access Journals (Sweden)

    Dušan Rajić

    2009-07-01

    Full Text Available Na primeru izabranih sredstava lične NHB zaštite demonstrirana je primena metode procene kompatibilnosti, kao vrlo bitne taktičko-tehničke karakteristike za svako novouvedeno sredstvo naoružanja i vojne opreme (NVO u Vojsci Srbije. Utvrđeno je da zaštitno filtrirajuće odelo, zaštitni laki ogrtač i zaštitne rukavice ispunjavaju postavljene kriterijume kompatibilnosti. Opisana metoda provere kompatibilnosti može da se primenjuje i na druga sredstva NVO u fazama razvoja, proizvodnje i eksploatacije. / The selected personal NBC protection devices have served as an example for demonstrating the application of the compatibility evaluation method as a very important tactical-technical characteristic of each newly introduced item of weapon and military equipment in the Serbian army. It has been determined that a filtering protective suit, a light protective coat and protective gloves meet the required criteria of compatibility. The described method of testing compatibility can be also applied to other weapons and military equipment in stages of development, production and exploitation.

  2. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1996-03-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking. 73 refs, 3 tabs

  3. Safety issues and their ranking for WWER-1000 model 320 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1997-04-01

    The objective of this report is to present a consolidated list of safety deficiencies, called safety issues, ranked according to their safety significance and the corrective measures to improve overall safety. It is intended for use as a reference to facilitate the development of plant specific safety improvement programmes and to serve as a basis for reviewing their implementation. To the extent that information was made available to the IAEA, the country/plant specific status with respect to each safety issue is described. Section 2 provides an overview of the impact of the relevant issues on the main safety functions in different operational conditions and other aspects important to overall plant safety. A summary of the safety issues and their respective ranking is given in Tables 1 and 2 at the end of Section 2. Section 3 deals with individual safety issues identified in the design which are presented according to the structure below. Section 4 presents the safety issues related to operational safety according to a similar structure but without the ranking

  4. HTS Nested magnet wound with 12 mm GdBCO tape and 4.4 mm YBCO tape

    International Nuclear Information System (INIS)

    Kang, Myung Hun; Ku, Myung Hwan; Cha, Guee Soo; Lim, Hyoung Woo

    2015-01-01

    The properties of High Temperature Superconducting (HTS) tapes are progressing, as HTS tapes evolve from 1st generation to 2nd generation. This paper presents design and construction of a 2nd generation HTS magnet consisting of two nested GdBCO and YBCO pancake coils. Two HTS tapes of different widths were used to wind the HTS nested magnet. Considering that a higher magnetic field is applied to the inner magnet than to the outer magnet, 12 mm GdBCO tape was used for winding the inner magnet, which consisted of four single pancake windings. Eight double pancake windings wound with 4.4 mm YBCO tapes were used for the outer magnet. The test results show that the central magnetic field of the HTS nested magnet was 920 mT. The measured critical currents of the inner and outer magnet at 77K were 80.8 A and 32.6 A, respectively

  5. Results from a partial lifetime test of a 40 mm-aperture 17 mm SSC model dipole

    International Nuclear Information System (INIS)

    Radusewicz, P.; Devred, A.; Bush, T.; Coombes, R.; DiMarco, J.; Goodzeit, C.; Kuzminski, J.; Ogitsu, T.; Potter, J.; Puglisi, M.; Sanger, P.; Schermer, R.; Tompkins, J.; Yu, Y.; Zhao, Y.; Zheng, H.; Anerella, M.; Cottingham, J.; Ganetis, G.; Garber, M.; Ghosh, A.; Greene, A.; Gupta, R.; Jain, A.; Kahn, S.; Kelly, E.; Morgan, G.; Muratore, J.; Prodell, A.; Rehak, M.; Roher, E.P.; Sampson, W.; Shutt, R.; Thomas, R.; Thompson, P.; Wanderer, P.; Willen, E.; Bleadon, M.; Hanft, R.; Kuchnir, M.; Mantsch, P.; Mazur, P.O.; Orris, D.; Peterson, T.; Strait, J.; Royett, J.; Scanlan, R.; Taylor, C.

    1992-03-01

    A 40-mm-aperture, 17-m-long Superconducting Super Collider (SSC) model dipole was assembled at Brookhaven National Laboratory (BNL) and tested initially at Fermi National Accelerator Lab (FNAL) and later at BNL. At BNL an extended cycle test was devised to examine the magnet's performance through numerous cold tests and thermal cycles. This paper discusses the magnet's mechanical and quench performance and magnet field measurements during the tests

  6. End design of the SSC 58 mm High Gradient Quadrupole

    International Nuclear Information System (INIS)

    Caspi, S.

    1992-01-01

    The ''end'' design of the High Gradient Quad. was done with consideration to the integrated field harmonics, the iron contribution, and the maximum field at the conductor. Magnetic analysis was done on the return end only, however the physical dimension of the lead end were determined as well. Using the cross-section of the windings and Cook's program BEND, we generated the physical end windings around the return end. Placing a single wire at the center of each turn the integrated gradient was computed and iterating on the end block spacers the integrated harmonics minimized. The final geometry was then used for more, extensive calculations, such as the field at the conductor and the 3D field harmonics. For this detailed calculation we have placed a single line current at the center of each strand and included the iron contribution (μ = ∞), see Appendix C. With the termination of the iron serving as a reference, the maximum length of the inner and outer layers are 182 mm and 215 mm respectively. The magnetic length of the end was computed from the gradient function A 2 and was found to be 142 mm. In reality we expect the physical length of the end to be somewhat larger, however this should have little or no effect on the magnetic length. The gradient in the straight section is 212.44 T/m at 7000 A and the integrated value of the gradient is -3.01665 E5 (G) in the end region marked by the magnetic length of the end. The respective integrated harmonics for the end 12 pole and 20 pole are -10.6658 (G/CM 4 ) and 0.7279 (G/cm 8 ) corresponding to b 6 = 0.351 , b 10 = -0.024 units. The above was computed from the values of A 2 , A 6 , and A 10

  7. Advanced accelerator and mm-wave structure research at LANL

    Energy Technology Data Exchange (ETDEWEB)

    Simakov, Evgenya Ivanovna [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-22

    This document outlines acceleration projects and mm-wave structure research performed at LANL. The motivation for PBG research is described first, with reference to couplers for superconducting accelerators and structures for room-temperature accelerators and W-band TWTs. These topics are then taken up in greater detail: PBG structures and the MIT PBG accelerator; SRF PBG cavities at LANL; X-band PBG cavities at LANL; and W-band PBG TWT at LANL. The presentation concludes by describing other advanced accelerator projects: beam shaping with an Emittance Exchanger, diamond field emitter array cathodes, and additive manufacturing of novel accelerator structures.

  8. Living with Omniback and the 8mm drive

    Energy Technology Data Exchange (ETDEWEB)

    Jones, M.C.

    1990-01-01

    Apollo's OmniBack backup system provides a convenient and effective way of storing network backup information on 8mm tape. In addition it has a journaling facility to write extensive log files, recording the backup process in almost any degree of detail desired. The directory structure and file names used are logical and well-defined. Summary files announce the degree of success of the backup as specified in the work file. The system will run unattended under the UNIX cron command, allowing the backup to be performed during the night when user demands on the network are small and most user files are free.

  9. Activities of the Service for maintenance of the RA reactor electronic equipment in 1979 - Report - Annex IV; Prilog IV Rad sluzbe za odrzavanje elektronske opreme reaktora RA u 1979. godini - Izvestaj -

    Energy Technology Data Exchange (ETDEWEB)

    Milosevic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1979-12-15

    Within the organizational structure of the RA reactor staff, the Service for instrumentation maintenance has the following tasks: maintenance of the existing electronic equipment; participating in experiments planning and preparation of electronic equipment; purchasing new equipment, spare parts and components; construction of new equipment for internal needs; implementation of new equipment. Basic instrumentation of the reactor facility includes: control and protection system, and dosimetry system. [Serbo-Croat] U okviru organizacione seme OOUR nuklearni reaktor RA sluzba za odrzavanje instrumentacije postrojenja ima sledece zadatke: odrzavanje postojece elektronske opreme; ucesce u planiranju eksperimenata i priprema elektronske opreme; nabavka nove opreme, rezervnih delova i komponenti; rad na izradi elektronske opreme i uredjaja za sopstvene potrebe i izrada projekata u domenu reaktorske opreme i ucesce u ugradnji nove opreme. Osnovna instrumentacija postrojenja obuhvata: sistem za upravljanje i zastitu, sistem za tehnolosku kontrolu i sistem za dozimetrijsku kontrolu.

  10. Šola kot "pripravljalnica" za nadaljnje učenje. Odnos šole do vseživljenjskega učenja

    Directory of Open Access Journals (Sweden)

    Maša Mlinarič

    2003-12-01

    Full Text Available V informacijski druzbi ucenje in izobrazevanje skozi vse zivljenje ni 'modna zapoved' izobrazevalnih teoretikov ali celo politikov, marvec prezivetvena pot reba. V evropskem prostoru, kjer tekmovalnost pogojuje uspeh vse druzbe, sta ucenje in izobrazevanje skozi vse zivljenje steber gospodarskega, druzbenega pa tudi politicnega razvoja. Tako naj bi vsakdo imel dostop do ustreznega in kakovostnega solskega izobrazevanja in izobrazevanja odraslih. Dostopnost solskega izobrazevanja in njegova kakovost pasta ob vplivu druzine temeljni pogo} za to, da se Clovek sploh ze li izobraze vati vse zivljenje. v ta namen potrebujemo kurikulume, ki bodo zmogli zagotoviti najpomembnejsa znanja in spretnosti za delo in seveda zivljenje. Potrebujemo pa tudi usposobljene ucitelje, da bodo motivirali otroke in mlade za ucenje skozi vse zivljenje.

  11. IV Training program for the staff of the laboratory for the RA reactor exploitation; IV Programi obuke osoblja Laboratorije za eksploataciju reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-07-01

    All the staff members of the laboratory for RA reactor exploitation are obliged to learn the following: fundamental properties of the RA reactor, the role and functionality of the reactor components, basic and auxiliary reactor systems, basics of radioactivity, measures for preventing contamination. The personnel working in shifts must be acquainted with the regulations and instructions for reactor operation. Training programs for reactor operators, mechanics, electricians, instrumentators and dosimetrysts are described separately. Svi saradnici Laboratorije za eksploataciju reaktora RA moraju poznavati sledece oblasti: Osnovne karakeristike reaktora RA, princip rada, ulogu i funkcionisanje komponenti reaktora, osnovnih i pomocnih sistema reaktora; osnovne pojmove o radioaktivnom zracenju, mere za sprecavanje kontaminacije. Osoblje koje radi u smenama mora dodatno poznavati propise i uputstva za rad reaktora. Posebno je naveden program obuke operatora reaktora, mehanicara, electricara, instrumentatora, dozimetrista.

  12. Za koncept vseživljenjskega izobraževanja in vseživljenjskega učenja je koncept izobraževanja odraslih vitalnega pomena

    Directory of Open Access Journals (Sweden)

    Dušana Findeisen

    2012-03-01

    Full Text Available Sredi finančne krize se vse bolj izgublja spomin na to, kaj nam je Evropska unija dala doslej in nam daje zdaj, tudi na področju izobraževanja odraslih, zato je morebiti prav, da se vrnemo k preglednim vtisom s konference, ki je zaznamovala deseti rojstni dan programa Grundtvig. Konference Deset let programa Grundtvig ali deset let inovativnosti in inovacij v izobraževanju odrasli v Bruslju sem se resda udeležila kot predstavnica AGE Platform Europe, vodilne evropske organizacije za vprašanja starejših, kjer delujem kot izvedenka za zaposlovanje in izobraževanje starejših. Uradno sicer ne, v resnici pa sem na tej konferenci zagovarjala tudi stališča slovenske univerze za tretje življenjsko obdobje in seveda stališča, ki smo jih razvili v slovenski andragogiki.

  13. Stress relaxation in SSC 50mm dipole coils

    International Nuclear Information System (INIS)

    Rogers, D.; Markley, F.

    1992-04-01

    We are measuring the stress relaxation of SSC 50mm outer coils with the goal of predicting how much of the coil prestress will be lost while the coils are warehoused between manufacture and cooldown. We manufacture 3 inch (76.2mm) long segments of coil with the same materials and techniques that have been used for prototype coils. We are running four simultaneous tests in an attempt to separate the contributions of the different coil materials. Test one is a completely insulated coil section where the insulation is the all polyamide system being tested at Brookhaven; test two is a wire stack insulated only with the normal Kapton overwrap; test three is a stack of bare cable; and test four is a completely insulated normal coil section. All, except for the bare cable, include the ground insulation. The insulated coil sections are carefully dried before loading and testing in order to eliminate stress changes due to varying moisture content. The temperature dependence of the stress relaxation is being studied separately. Three companion papers presented at this conference will be: (1) ''Temperature dependence of the viscoelastic properties of SSC coil insulation'' (2) ''Measurement of the elastic modulus of Kapton perpendicular to the plane of the film at room and cryogenic temperatures'' (3) ''Theoretical methods for creep and stress relaxation studies of SSC coil.''

  14. QM/MM Molecular Dynamics Studies of Metal Binding Proteins

    Directory of Open Access Journals (Sweden)

    Pietro Vidossich

    2014-07-01

    Full Text Available Mixed quantum-classical (quantum mechanical/molecular mechanical (QM/MM simulations have strongly contributed to providing insights into the understanding of several structural and mechanistic aspects of biological molecules. They played a particularly important role in metal binding proteins, where the electronic effects of transition metals have to be explicitly taken into account for the correct representation of the underlying biochemical process. In this review, after a brief description of the basic concepts of the QM/MM method, we provide an overview of its capabilities using selected examples taken from our work. Specifically, we will focus on heme peroxidases, metallo-β-lactamases, α-synuclein and ligase ribozymes to show how this approach is capable of describing the catalytic and/or structural role played by transition (Fe, Zn or Cu and main group (Mg metals. Applications will reveal how metal ions influence the formation and reduction of high redox intermediates in catalytic cycles and enhance drug metabolism, amyloidogenic aggregate formation and nucleic acid synthesis. In turn, it will become manifest that the protein frame directs and modulates the properties and reactivity of the metal ions.

  15. Ralstonia eutropha's Poly(3-hydroxybutyrate)(PHB) polymerase PhaC1 and PHB depolymerase PhaZa1 are phosphorylated in vivo.

    Science.gov (United States)

    Jüngert, Janina R; Patterson, Cameron; Jendrossek, Dieter

    2018-04-20

    In this study, we screened PHB synthase PhaC1 and PHB depolymerase PhaZa1 of Ralstonia eutropha for the presence of phosphorylated residues during the PHB accumulation and PHB degradation phase. Thr373 of PHB synthase PhaC1 was phosphorylated in the stationary growth phase but was not modified in the exponential and PHB accumulation phases. Ser35 of PHB depolymerase PhaZa1 was identified in phosphorylated form both in the exponential and in the stationary growth phase. Additional phosphosites were identified for both proteins in sample-dependent forms. Site-directed mutagenesis of the codon for Thr373 and other phosphosites of PhaC1 revealed a strong negative impact on PHB synthase activity. Modification of Thr26 and Ser35 of PhaZa1 reduced the ability of R. eutropha to mobilize PHB in the stationary growth phase. Our results show that phosphorylation of PhaC1 and PhaZa1 can be important for modulation of the activities of PHB synthase and PHB depolymerase. Importance Polyhydroxybutyrate (PHB) and related polyhydroxyalkanoates (PHAs) are important intracellular carbon and energy storage compounds in many prokaryotes. The accumulation of PHB or PHAs increases the fitness of cells during periods of starvation and other stress conditions. The simultaneous presence of poly(3-hydroxybutyrate) (PHB) synthase (PhaC1) and PHB depolymerase (PhaZa1) on synthesized PHB granules in Ralstonia eutropha (alternative designation Cupriavidus necator ) has been previously shown in several laboratories. These findings imply that the activities of PHB synthase and PHB depolymerase should be regulated to avoid a futile cycle of simultaneous synthesis and degradation of PHB. Here, we addressed this question by identifying phosphorylation sites on PhaC1 and PhaZa1 and by site-directed mutagenesis of identified residues. Furthermore, we conducted in vitro and in vivo analysis of PHB synthase activity and PHB contents. Copyright © 2018 American Society for Microbiology.

  16. Izgradnja podatkovnega skladišča v družbi za trgovanje z električno energijo

    OpenAIRE

    PINTAR, MATEJ

    2017-01-01

    Namen diplomskega dela je predstaviti projekt »Izgradnja podatkovnega skladišča v družbi za trgovanje energije«. Diplomsko delo je razdeljeno na tri sklope. V prvem sklopu so, z namenom boljšega razumevanja tematike v nadaljevanju diplomskega dela, na kratko predstavljene značilnosti trga z električno energijo na primeru slovenskega trga z električno energijo. V drugem sklopu (tretje poglavje) so v ospredju osnove podatkovnega skladišča, razlike med dimenzijskim in normaliziranim pod...

  17. Kjubrikovo čitanje Bardžisa: Značaj kostima za razumevanje Paklene pomorandže

    OpenAIRE

    Dijana Metlić

    2016-01-01

    Roman Paklena pomorandža Entonija Bardžisa, objavljen 1962. godine, postao je jedno od kultnih književnih dela XX veka, pre svega zahvaljujući istoimenom filmu Stenlija Kjubrika iz 1971. Okarakterisan kao dekadentno i nihilističko ostvarenje, snimljen tako da gledaoci „uživaju“ u scenama nasilja, Kjubrikov film bio je, uz prekide, u distribuciji u Britaniji do 1974. godine kada je povučen na zahtev reditelja zbog optužbi koje su ga implicitno teretile za povećanje stepena delinkventskog nasil...

  18. IZBIRA REŠITVE ZA UPRAVLJANJE ODNOSOV S STRANKAMI NA PRIMERU ŠTAJERSKEGA TEHNOLOŠKEGA PARKA

    OpenAIRE

    Šumandl Kostov, Tea

    2015-01-01

    V poslovnem svetu je že dolgo znano, da so kupci jedro posla ter da uspeh podjetja temelji na učinkovitem upravljanju odnosov z njimi. Vsi cilji so osredotočeni na zadovoljevanje strank, tako da se te rade vračajo. Pogosto pa ti cilji predstavljajo oviro za podjetja, ki nimajo ustreznih orodij, opreme in metod. V današnjem času tehnologija podjetjem ponuja sisteme, ki zaposlenim omogočajo, da hitro pridobijo vse podatke o strankah. Ta koncept se imenuje upravljanje odnosov s strankami (v nada...

  19. RA reactor action plan for 1977 - Annex VI; Prilog VI - Plan rada reaktora RA za 1977. godinu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-12-15

    In the RA reactor action plan for 1977 it is foreseen that the reactor would be operated for 181 days, mostly at nominal power of 6.5 MW. It is planned to produce 28236 MWh in total. Five reactor core exchanges (refuelling) are planned. The plan includes time for repair of components as well as for cooling. [Serbo-Croat] Plan rada reaktora RA predvidja rad tokom 181 dana, vecim delom na nominalnoj snazi od 6,5 MW tokom 1977. godine. Planirano je da ukupni rad iznosi 28236 MWh. Planom je predvidjeno i pet izmena goriva kao i vreme potrebno za remont opreme i hladjenje.

  20. Report of the Service for maintenance of mechanical structures - Annex 2; Prilog 2 - Rad sluzbe za odrzavanje masinske opreme

    Energy Technology Data Exchange (ETDEWEB)

    Radivojevic, J [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1976-01-15

    This Annex 2 describes the organizational structure and activities of the Service for maintenance of the mechanical structures of the RA reactor, inspection and maintenance of of reactor components, workshop and storage of spare parts at the reactor. Mechanical structures of the RA reactor included are: heavy water system, gas systems, technical water system, reactor core, and transportation equipment. [Serbo-Croat] Pored opisa organizacije rada sluzbe za odrzavanje masinske opreme reaktora RA, ovaj prilog sadrzi: podatke o stanju, reviziji i remontu masinske opreme reaktora RA, prirucne radionice i magacina. Masinska oprema reaktora RA obuhvata: sistem teske vode, gasne sisteme, sistem tehnicke vode, centralno telo reaktora, transportnu opremu.