WorldWideScience

Sample records for supply system nuclear

  1. Nuclear steam supply system and method of installation

    International Nuclear Information System (INIS)

    Tower, S.N.; Christenson, J.A.; Braun, H.E.

    1989-01-01

    This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

  2. Optimization of heat supply systems employing nuclear power plants

    International Nuclear Information System (INIS)

    Urbanek, J.

    1988-01-01

    Decision making on the further development of heat supply systems requires optimization of the parameters. In particular, meeting the demands of peak load ranges is of importance. The heat supply coefficient α and the annual utilization of peak load equipment τ FS have been chosen as the characteristic quantities to describe them. The heat price at the consumer, C V , offers as the optimization criterion. The transport distance, temperature spread of the heating water, and different curves of annual variation of heat consumption on heat supply coefficient and heat price at the consumer. A comparison between heat supply by nuclear power plants and nuclear heating stations verifies the advantage of combined heat and power generation even with longer heat transport distances as compared with local heat supply by nuclear district heating stations based on the criterion of minimum employment of peak load boilers. (author)

  3. The role of nuclear energy system for Korean long-term energy supply strategy

    International Nuclear Information System (INIS)

    Chae, K.N.; Lee, D.G.; Lim, C.Y.; Lee, B.W.

    1995-01-01

    The energy supply optimization model MESSAGE-III is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Emphasis is placed on the potential contribution of nuclear energy in case of environmental constraints and energy resource limitation. The time horizon is 1993-2040. A program to forecast useful energy demand is developed, and optimization is performed from the overall energy system to the nuclear energy system. Reactor and fuel cycle strategy and the expanded utilization options for nuclear energy system are suggested. FBRs, HTGRs and thorium fuel cycle would play key roles in the long run. The most important factors for nuclear energy in Korean energy supply strategy would be the availability of fossil fuels, CO 2 reduction regulation, and the supply capability of nuclear energy. (author)

  4. Research on assurance system of nuclear fuel supply (Contract research)

    International Nuclear Information System (INIS)

    Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

    2010-08-01

    Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer States, supplier States, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier States on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

  5. Research on assurance system of nuclear fuel supply (Contract research)

    International Nuclear Information System (INIS)

    Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

    2010-03-01

    Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding unnecessary spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we gave an overview of discussions on AOS since World War II, and elaborated on some of current proposals. We have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer states, supplier states, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier states on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

  6. Development for a multi-purpose nuclear energy supply system

    International Nuclear Information System (INIS)

    Narabayashi, Tadashi; Shimazu, Yoichiro; Sato, Kotaro; Imamura, Mitsuru; Tsuji, Masashi

    2009-01-01

    Hokkaido is one of the four largest island of Japan located in the northern, most of the area, where the atmospheric temperature goes lower than the other area in winter. Thus, an average energy consumption per capita is larger in amount during cold seasons. Nowadays this energy is supplied by fossil fuels. On the other hand, problem of the green house gas emission should be controlled as much as possible in order to avoid global warming. From this point of view, the authors have discussed with local people on the possibility to utilize nuclear clean energy in the daily life in Hokkaido district. Recently some leaders in local towns become interested to such activities and they want information about nuclear energy and related systems. It is a very good chance for us to exchange information on nuclear energy with regards to public acceptance, fears of nuclear power or radiation, the extent of satisfaction to be sure for construction of urban nuclear plants and requirements for such plants. We prepared technical presentation materials and visited a selected towns and continued discussion in various aspects. For example, proposal of a proto type design concept of a small reactor, safety, heat energy supply system. The audience was mainly representatives of the towns firstly and gradually ordinal people also attended the meetings. Based on the information, it could be expected to establish a concept for such district energy supply system. In this paper, some examples and results through these activities are presented. (author)

  7. Hybrid district heating system with heat supply from nuclear source

    International Nuclear Information System (INIS)

    Havelka, Z.; Petrovsky, I.

    1987-01-01

    Several designs are described of heat supply from large remote power sources (e.g., WWER-1000 nuclear power plants with a 1000 MW turbine) to localities where mainly steam distribution networks have been built but only some or none networks for hot water distribution. The benefits of the designs stem from the fact that they do not require the conversion of the local steam distribution system to a hot water system. They are based on heat supply from the nuclear power plant to the consumer area in hot water of a temperature of 150 degC to 200 degC. Part of the hot water heat will be used for the production of low-pressure steam which will be compressed using heat pumps (steam compressors) to achieve the desired steam distribution network specifications. Water of lower temperature can be used in the hot water network. The hot water feeder forms an automatic pressure safety barrier in heat supply of heating or technological steam from a nuclear installation. (Z.M.). 5 figs., 9 refs

  8. Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant

    International Nuclear Information System (INIS)

    Reis Martins Junior, L.L. dos.

    1980-01-01

    The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author)

  9. Nuclear reactor power supply system

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

    The redundant signals from the sensor assemblies measuring the process parameters of a nuclear reactor power supply are transmitted each in its turn to a protection system which operates to actuate the protection apparatus for signals indicating off-process conditions. Each sensor assembly includes a number of like sensors measuring the same parameters. The sets of process signals derived from the sensor assemblies are each in its turn transmitted from the protection system to the control system which impresses control signals on the reactor or its components to counteract the tendency for conditions to drift off-normal status requiring operation of the protection system. A parameter signal selector prevents a parameter signal which differs from the other parameter signals of the set by more than twice the allowable variation from passing to the control system. Test signals are periodically impressed by a test unit on a selected pair of a selection unit and control channels. This arrangement eliminates the possibility that a single component failure which may be spurious will cause an inadvertent trip of the reactor during test. (author)

  10. A protection system of low temperature thermo-supply nuclear reactor

    International Nuclear Information System (INIS)

    Jiang Binsen

    1988-09-01

    A Protection system of low temperature thermo-supply nuclear reactor is introduced. It is the first protection system, which is designed and manufactred on the basis of Chinese National Standard GB 4083-83 'General Safety Principle of Nuclear Reactor Protection System', to be considered under the circumstances of industry level in China. Advantages of the protection system are as follows: 1)The single failure criteria can fully be fulfilled by the protection system. 2) On-line testing system can be used for detecting all of failure components and quick identifying the failure points in the system. 3) It is convenience for maintenacnce of the system. To complete this project is very important and helpful in promoting the development of the protection system and safety operation of nuclear reactor in China

  11. Application of nuclear steam supply system of NIKA series for seawater desalination

    International Nuclear Information System (INIS)

    Adamovich, L.A.; Achkasov, A.N.; Grechko, G.I.; Pavlov, V.L.; Shishkin, V.A.

    1998-01-01

    The nuclear steam supply system (NSSS) NIKA has been developed on the basis of experience available in Russia in designing, construction and operation of similar systems for ship propulsion reactors. Major systems and equipment of the NSSS are designed to take advantage of the proven engineering features and to meet Russian regulations, standards, practices and up-to-date safety philosophy. NSSS NIKA-75 has been designed for arrangement on barge. This permits to manufacture all NSSS equipment at the factory and to deliver it to the exploitation area ready for operation. NSSS NIKA-300 is designed for erection on land. It seems very interesting to use those NSSS types for seawater desalination. The main technical solutions, concept statements, technical and economical evaluations of NIKA series nuclear steam supply systems for seawater desalination are described. (author)

  12. A self-consistent nuclear energy supply system

    International Nuclear Information System (INIS)

    Fujii-e, Y.; Morita, T.; Kawakami, H.; Arie, K.; Suzuki, M.; Iida, M.; Yamazaki, H.

    1992-01-01

    A self-consistent nuclear energy supply system (SCNESS) is investigated for a Fast Reactor. SCNESS is proposed as a future stable energy supplier with no harmful influence on humans or environment for the ultimate goal of nuclear energy development. SCNESS should be inherently safe, be able to breed fissionable material, and transmute long-lived radioactive nuclides (i.e., minor actinides and long-lived fission products). The relationship between these characteristics and the spatial assignment of excess neutrons (v-1) for each characteristic are analyzed. The analysis shows that excess neutrons play an intrinsic role in realizing SCNESS. The reactor concept of SCNESS is investigated by considering utilization of excess neutrons. Results show that a small-size axially double-layered annular core with metal fuel is a choice candidate for SCNESS. SCNESS is concluded feasible. (author). 4 refs., 9 figs

  13. Improvements to the sodium supply system of a nuclear reactor core

    International Nuclear Information System (INIS)

    Chevallier, Rene; Marchais, Christian.

    1981-01-01

    This invention concerns an improvement to the sodium supply system of a nuclear reactor core and, in particular, concerns the area included between the outlet of the primary circulation pumps and the core proper. A simplified structure and a lightening of all this linking area between the circulation pumps and the distribution tank under the core is achieved and this results in a very significant reduction in the risks of deterioration and in a definite increase in the reliability of the reactor. The invention is therefore an improvement to the sodium supply system of the nuclear reactor core vessel with incorporated exchangers, in which the cool sodium, after passing through the primary exchangers, is collected in a ring compartment from whence it is taken up by the pumps and moved to at least one pipe reaching a distribution tank located under the reactor core [fr

  14. Unattended nuclear systems for local energy supply

    International Nuclear Information System (INIS)

    Lynch, G.F.; Bancroft, A.R.; Hilborn, J.W.; McDougall, D.S.; Ohta, M.M.

    1988-02-01

    This paper describes recent developments in a small nuclear heat and electricity production system - the SLOWPOKE Energy System - that make it possible to locate the system close to the load, and that could have a major impact on local energy supply. The most important unique features arising from these developments are walk-away safety and the ability to operate in an unattended mode. Walk-away safety means that radiological protection is provided by intrinsic characteristics and does not depend on either engineered safety systems or operator intervention. This, in our view, is essential to public acceptance. The capability for unattended operation results from self-regulation; however, the performance can be remotely monitored. The SLOWPOKE Energy System consists of a water-filled pool, operating at atmospheric pressure, which cools and moderates a beryllium-reflected thermal reactor that is fuelled with 100 to 400 kg of low-enriched uranium. The pool water also provides shielding from radioactive materials trapped in the fuel. Heat is drawn from the pool and transferred either to a building hot-water distribution system or to an organic liquid which is converted to vapour to drive a turbine-generator unit. Heating loads between 2 qnd 10 MWt, and electrical loads up to 1 MWe can be satisfied. SLOWPOKE is a dramatic departure from conventional nuclear power reactors. Its nuclear heat source is intrinsically simple, having only one moving part: a solid neutron absorber which is slowly withdrawn from the reactor to balance the fuel burnup. Its power is self-regulated and excessive heat production cannot occur, even for the most severe combinations of system failure. Cooling of the fuel is assured by natural physical processes that do not depend on mechanical components such as pumps. These intrinsic characteristics assure public safety and ultra high reliability

  15. Unattended nuclear systems for local energy supply

    International Nuclear Information System (INIS)

    Lynch, G.F.; Bancroft, A.R.; Hilborn, J.W.; McDougall, D.S.; Ohta, M.M.

    1986-10-01

    This paper describes recent developments in a small nuclear heat and electricity production system - the SLOWPOKE energy system - that make it possible to locate the system close to the load, and that could have a major impact on local energy supply. The most important unique features arising from these developments are walk-away safety and the ability to operate in an unattended mode. Walk-away safety means that radiological protection is provided by intrinsic characteristics and does not depend on either engineered safety systems or operator intervention. This, in our view, is essential to public acceptance. The capability for unattended operation results from self-regulation, however the performance can be remotely monitored. The SLOWPOKE energy system consists of a water-filled pool, operating at atmospheric pressure, which cools and moderates a beryllium-reflected thermal reactor that is fuelled with 100 to 400 kg of low enriched uranium. The pool water also provides shielding from radioactive materials trapped in the fuel. Heat is drawn from the pool and transferred either to a building hot-water distribution system or to an organic liquid which is converted to vapour to drive a turbine-generator unit. Heating loads between 2 and 10 MWt, and electrical loads up to 1 MWe can be satisfied. SLOWPOKE is a dramatic departure from conventional nuclear power reactors. Its nuclear heat source is intrinsically simple, having only one moving part: a solid neutron absorber which is slowly withdrawn from the reactor to balance the fuel burnup. Its power is self-regulated and excessive heat production cannot occur, even for the most severe combinations of system failure. Cooling of the fuel is assured by natural physical processes that do not depend on mechanical components such as pumps. These intrinsic characteristics assure public safety and ultra high reliability. (author)

  16. An autonomous nuclear power plant with integrated nuclear steam supply system designed for electric power and heat supply in remote areas with difficult access

    International Nuclear Information System (INIS)

    Adamovich, L.A.; Grechko, G.I.; Lapin, B.D.; Ulasevich, V.K.; Shishkin, V.A.

    1997-01-01

    The paper contains basic conceptual principles used to develop the technical assignment for an autonomous nuclear power plant with integrated nuclear steam supply system (NSSS) designed to provide heat and electricity for areas which are remote with difficult access. The paper also describes technical procedures and equipment, NPP thermal hydraulic flow chart, steam generator design, safety aspects as well as operational and maintenance procedures. (author)

  17. Electricity supplies in a French nuclear power station

    International Nuclear Information System (INIS)

    2011-01-01

    As the operation of a nuclear power station requires a power supply system enabling this operation as well as the installation safety, this document describes how such systems are designed in the different French nuclear power stations to meet the requirements during a normal operation (when the station produces electricity) or when it is stopped, but also to ensure power supply to equipment ensuring safety functions during an incident or an accident occurring on the installation. More precisely, these safety functions are provided by two independent systems in the French nuclear power stations. Their operation is briefly described. Two different types of nuclear reactors are addressed: pressurised water reactors (PWR) of second generation, EPR (or PWR of third generation)

  18. The role of nuclear energy for Korean long-term energy supply strategy : application of energy demand-supply model

    International Nuclear Information System (INIS)

    Chae, Kyu Nam

    1995-02-01

    An energy demand and supply analysis is carried out to establish the future nuclear energy system of Korea in the situation of environmental restriction and resource depletion. Based on the useful energy intensity concept, a long-term energy demand forecasting model FIN2USE is developed to integrate with a supply model. The energy supply optimization model MESSAGE is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Long-term demand for useful energy used as an exogeneous input of the energy supply model is derived from the trend of useful energy intensity by sectors and energy carriers. Supply-side optimization is performed for the overall energy system linked with the reactor and nuclear fuel cycle strategy. The limitation of fossil fuel resources and the CO 2 emission constraints are reflected as determinants of the future energy system. As a result of optimization of energy system using linear programming with the objective of total discounted system cost, the optimal energy system is obtained with detailed results on the nuclear sector for various scenarios. It is shown that the relative importance of nuclear energy would increase especially in the cases of CO 2 emission constraint. It is concluded that nuclear reactor strategy and fuel cycle strategy should be incorporated with national energy strategy and be changed according to environmental restriction and energy demand scenarios. It is shown that this modelling approach is suitable for a decision support system of nuclear energy policy

  19. Introduction to deaerator in auxiliary water supply system of nuclear power plant

    International Nuclear Information System (INIS)

    Dong Jianguo; Zhou Xia; Lei Yongxia

    2015-01-01

    The paper introduces the operation theory and thermal calculation and verification requirements for the deaerator in the auxiliary water supply system of nuclear power plant. In addition, it describes the key factors in terms of function, structure, design and fabrication of equipment. (authors)

  20. Modification of the Japanese first nuclear ship reactor for a regional energy supply system

    International Nuclear Information System (INIS)

    Sato, K.; Shimazu, Y.; Narabayashi, T.; Tsuji, M.

    2008-01-01

    Nuclear Ship Mutsu was developed as the first experimental nuclear ship of Japan. It has several advantages as a prototype for regional energy supply system. Considering the attractive advantages of the Mutsu reactor, we investigated the feasibility of development of a small regional energy system by adopting the Mutsu reactor as a starting model. The system could supply with not only electricity but also heat. Heat could be used for hot-water supply, a heating system of a house, melting snow and so on, especially for those in northern part of Japan. The system should satisfy the requirements for GEN IV systems and the current regulations. From this point of view, the modification of the reactor was initiated by taking into improvements and technology of the state of arts to fulfill the requirements such as (1) Longer core life without refueling, (2) Reactivity adjustment for load change without control rods or soluble boron, (3) Simpler operations for load changes and (4) Ultimate safety with sufficient passive capability. Currently it is assumed to use basic standard 17x17 fuel assembly design for WH type PWRs. Nuclear design calculations are carried out by 'SRAC 2002 ', which has been developed in Japan Atomic Energy Agency. Several problems have not been solved yet, but we confirmed the proposed core has about 10 years life time. So the proposed core has a possibility to be used for a small regional energy system. (authors)

  1. Optimum design of a nuclear heat supply

    International Nuclear Information System (INIS)

    Borel, J.P.

    1984-01-01

    This paper presents an economic analysis for the optimum design of a nuclear heat supply to a given district-heating network. First, a general description of the system is given, which includes a nuclear power plant, a heating power plant and a district-heating network. The heating power plant is fed with steam from the nuclear power plant. It is assumed that the heating network is already in operation and that the nuclear power plant was previously designed to supply electricity. Second, a technical definition of the heat production and transportation installations is given. The optimal power of these installations is examined. The main result is a relationship between the network capacity and the level of the nuclear heat supply as a substitute for oil under the best economic conditions. The analysis also presents information for choosing the best operating mode. Finally, the heating power plant is studied in more detail from the energy, technical and economic aspects. (author)

  2. Nuclear steam supply system KLT-40 enhanced safety as independent power supply source. Employment prospects

    International Nuclear Information System (INIS)

    Polunichev, V.I.; Sayanov, D.G.; Ardabievsky, A.A.

    1993-01-01

    High quality of KLT-40 nuclear steam supply system (NSSS) providing enhanced safety is attained owing to the development and operation experience of equipments and systems in Soviet nuclear icebreakers. First of all they are the operating nuclear-powered icebreakers open-quotes Arktikaclose quotes, open-quotes Sibirclose quotes, open-quotes Rossiyaclose quotes, open-quotes Sovetsky Soyuzclose quotes, the limited draught icebreakers of joint Soviet-Finnish manufacturing open-quotes Taimyrclose quotes open-quotes Vaigachclose quotes. 30-years trouble-free operation of icebreaker open-quotes Leninclose quotes, the ancestor of nuclear powered fleet, is unprecedented. Operation life of individual equipment items amounts to 107000 hours, that testifies to high reliability and life characteristics of NSSS. Trouble-free operation of the nuclear-powered icebreakers' reactor plants (RPs) exceeded 130 reactor years, that proves high quality of design decisions being underlain in the basis of the KLT-40 NSSS for the lighter-cargo carrier open-quotes Sevmorputclose quotes, which was put into operation into 1988. Besides it testifies to the expediency of KLT-40 NSSS employment as a power source in different power installations. The KLT-40 is a reactor plant with a pwr type reactor. The design is described in detail with diagrams

  3. Operating experience feedback on lose of offsite power supply for nuclear power plant

    International Nuclear Information System (INIS)

    Jiao Feng; Hou Qinmai; Che Shuwei

    2013-01-01

    The function of the service power system of a nuclear power plant is to provide safe and reliable power supply for the nuclear power plant facilities. The safety of nuclear power plant power supply is essential for nuclear safety. The serious accident of Fukushima Daiichi nuclear power plant occurred due to loss of service power and the ultimate heat sink. The service power system has two independent offsite power supplies as working power and auxiliary power. This article collected events of loss of offsite power supply in operating nuclear power plants at home and abroad, and analyzed the plant status and cause of loss of offsite power supply events, and proposed improvement measures for dealing with loss of offsite power supply. (authors)

  4. Small nuclear power reactor emergency electric power supply system reliability comparative analysis

    International Nuclear Information System (INIS)

    Bonfietti, Gerson

    2003-01-01

    This work presents an analysis of the reliability of the emergency power supply system, of a small size nuclear power reactor. Three different configurations are investigated and their reliability analyzed. The fault tree method is used as the main tool of analysis. The work includes a bibliographic review of emergency diesel generator reliability and a discussion of the design requirements applicable to emergency electrical systems. The influence of common cause failure influences is considered using the beta factor model. The operator action is considered using human failure probabilities. A parametric analysis shows the strong dependence between the reactor safety and the loss of offsite electric power supply. It is also shown that common cause failures can be a major contributor to the system reliability. (author)

  5. Water supply impacts of nuclear fall

    International Nuclear Information System (INIS)

    Hobbs, B.F.; Luo, Y.; Maciejowski, M.E.; Chester, C.V.

    1989-01-01

    Nuclear winter,” more properly called “nuclear fall,” could be caused by injection of large amounts of dust into the atmosphere. Besides causing a decrease in temperature, it could be accompanied by “nuclear drought,” a catastrophic decrease in precipitation. Dry land agriculture would then be impossible, and municipal, industrial, and irrigation water supplies would be diminished. It has been argued that nuclear winter/fall poses a much greater threat to human survival than do fall out or the direct impacts of a conflict. However, this does not appear to be true, at least for the U.S. Even under the unprecedented drought that could result from nuclear fall, water supplies would be available for many essential activities. For the most part, ground water supplies would be relatively invulnerable to nuclear drought, and adequate surface supplies would be available for potable uses. This assumes that conveyance facilities and power supplies survive a conflict largely intact or can be repaired

  6. Nuclear power: energy security and supply assurances

    International Nuclear Information System (INIS)

    Rogner, H.H.; McDonald, A.

    2008-01-01

    Expectations are high for nuclear power. This paper first summarizes recent global and regional projections for the medium-term, including the 2007 updates of IAEA projections plus International Energy Agency and World Energy Technology Outlook projections to 2030 and 2050. One driving force for nuclear power is concern about energy supply security. Two potential obstacles are concerns about increased nuclear weapon proliferation risks, and concerns by some countries about potential politically motivated nuclear fuel supply interruptions. Concerning supply security, the paper reviews different definitions, strategies and costs. Supply security is not free; nor does nuclear power categorically increase energy supply security in all situations. Concerning proliferation and nuclear fuel cut-off risks, the IAEA and others are exploring possible 'assurance of supply' mechanisms with 2 motivations. First, the possibility of a political fuel supply interruption is a non-market disincentive discouraging investment in nuclear power. Fuel supply assurance mechanisms could reduce this disincentive. Second, the risk of interruption creates an incentive for a country to insure against that risk by developing a national enrichment capability. Assurance mechanisms could reduce this incentive, thereby reducing the possible spread of new national enrichment capabilities and any associated weapon proliferation risks. (orig.)

  7. Sustainablility of nuclear and non-nuclear energy supply options in Europe

    International Nuclear Information System (INIS)

    Kirchsteiger, C.

    2007-01-01

    In the course of the current discussion on promoting the economical competitiveness of sustainable energy systems, especially renewable and non-CO 2 -intensive ones, interest in nuclear energy has re-awakened in Europe (''nuclear renaissance''). This paper starts with presenting the concept of energy sustainability and its main elements. Next, an overview of the main results of sustainability assessments for different energy supply options (nuclear, fossil, renewables) covering full energy chains is given. Nuclear energy's typical strong and weak points are identified from a sustainability point of view. On the basis of these results, it is argued that more emphasis on nuclear energy's (very good) total cost performance, i.e. incl. externalities, rather than on its (very good) contribution to combating climate change would stronger benefit its ''renaissance''. Finally, the development of an overall EU-wide framework is proposed in order to assess the sustainability performance of alternative energy supply options, incl. nuclear, across their lifecycle and thus support decision making on developing sustainable energy mixes. (orig.)

  8. Alternative off-site power supply improves nuclear power plant safety

    International Nuclear Information System (INIS)

    Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

    2014-01-01

    Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

  9. Simulation of a Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant. Simulacao do sistema nuclear de geracao de vapor de uma central PWR

    Energy Technology Data Exchange (ETDEWEB)

    Reis Martins Junior, L.L. dos.

    1980-01-01

    The following work intends to perform the digital simulation, of the Nuclear Steam Supply System (NSSS) of a PWR nuclear power plant for control systems design and analysis purposes. There are mathematical models for the reactor, the steam generator, the pressurizer and for transport lags of the coolant in the primary circuit. Nevertheless no one control system has been considered to permit any user the inclusion in the more convenient way of the desired control systems' models. The characteristics of the system in consideration are fundamentally equal to the ones of Almirante Alvaro Alberto Nuclear Power Plant, Unit I (Angra I) obtained in the Final Safety Analysis Report at Comissao Nacional de Energia Nuclear. (author).

  10. Evaluation of Control and Protection System for Loss of Electrical Power Supply System of Water-Cooling Nuclear Power Plant

    International Nuclear Information System (INIS)

    Suhaemi, Tjipta; Djen Djen; Setyono; Jambiar, Riswan; Rozali, Bang; Setyo P, Dwi; Tjahyono, Hendro

    2000-01-01

    Evaluation of control and protection system for loss of electrical power supply system of water-cooled nuclear power plant has been done. The loss of electrical power supply. The accident covered the loss of external electrical load and loss of ac power to the station auxiliaries. It is analysed by studying and observing the mechanism of electrical power system and mechanism of related control and protection system. The are two condition used in the evaluation i e without turbine trip and with turbine trip. From the evaluation it is concluded that the control and protection system can handled the failure caused by the loss of electrical power system

  11. Supply assurance in the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Neff, T.L.; Jacoby, H.D.

    1979-01-01

    Nuclear fuel assurance, in the face of world and political uncertainties, is interrelated with nuclear technology development plans and international safeguards considerations. This has led some countries to accelerate their commitments to nuclear commercialization faster than necessary and has made non-proliferation policies harder to enforce. Fuel assurance is described on a national basis in three time scales: short-term, or resilience to supply interruptions; mid-term, or contract conditions in which governments make commitments to purchase or deliver; and long-term, or resource adequacy. A review of former assurance problems and current trends in the enrichment and uranium markets indicates that supplier concentration is no longer the major problem so much as non-proliferation actions. The present state of unstable equilibrium is expected to move in the direction of less fuel-supply assurance for countries having a small market or not subscribing to non-proliferation criteria. The authors, while generally optimistic that the fuel-supply system will function, express concern that policies for fuel stockpiles and the condition of uranium markets need improvement. 21 references

  12. A “Grammar” for assessing the performance of power-supply systems: Comparing nuclear energy to fossil energy

    International Nuclear Information System (INIS)

    Diaz-Maurin, François; Giampietro, Mario

    2013-01-01

    This article illustrates an innovative approach for the characterization and comparison of the performance of power-supply systems. The concept of ‘grammar’ forces to declare the pre-analytical decisions about: (i) semantic and formal categories used for the accounting – primary energy sources (PES), energy carriers (EC), and production factors; (ii) the set of functional and structural elements of the power-supply system included in the analysis. After having tamed the systemic ambiguity associated with energy accounting, it becomes possible to generate a double assessment referring to: (i) external constraints – the consumption of PES and the generation of waste and pollution; and (ii) internal constraints – the requirements of production factors such as human labor, power capacity, internal consumption of EC for making EC. The case study provided compares the production of EC (electricity) with “nuclear energy” and “fossil energy”. When considering internal constraints, nuclear energy requires about twice as much power capacity (5.9–9.5 kW/GWh vs. 2.6–2.9 kW/GWh) and 5–8 times more labor (570–640 h/GWh vs. 80–115 h/GWh). Things do not improve for nuclear energy when looking at external constraints – e.g. the relative scarcity of PES. This may explain the difficulties faced by nuclear energy to gain interest from investors. -- Highlights: ► A new approach to assess the performance of power-supply systems is provided. ► A biophysical analysis of the production process is based on the concept of grammar. ► A grammar is capable of handling the inherent ambiguity associated with energy. ► The performance of nuclear energy and fossil energy is compared using this grammar. ► Nuclear energy demonstrates a lower performance than fossil energy in making electricity.

  13. Electric power system / emergency power supply

    International Nuclear Information System (INIS)

    Dorn, P.G.

    1980-01-01

    One factor of reliability of reactor safety systems is the integrity of the power supply. The purpose of this paper is a review and a discussion of the safety objectives required for the planning, licensing, manufacture and erection of electrical power systems and components. The safety aspects and the technical background of the systems for - the electric auxiliary power supply system and - the emergency power supply system are outlined. These requirements result specially from the safety standards which are the framework for the studies of safety analysis. The overall and specific requirements for the electrical power supply of the safety systems are demonstrated on a 1300 MW standard nuclear power station with a pressurized water reactor. (orig.)

  14. Target study of heat supply from Northern Moravia nuclear power plant

    International Nuclear Information System (INIS)

    Pospisil, V.

    The construction is envisaged in Northern Moravia of a nuclear power plant near Blahutovice in the Novy Jicin district. Heat produced by the nuclear power plant will only be used for district heating; process heat will be supplied from local steam sources. An example is discussed of the Prerov locality which currently is supplied from the Prerov heating and power plant (230 MW), a heating plant (36 MW) and from local sources (15 NW). The study estimates that a thermal power of 430 MW will be required at a time of the start of heat supplies from the nuclear power plant. All heat supply pipelines will be designed as a two-tube system divided into sections with section pipe fittings. The number and location of pipe fittings will be selected depending on the terrain configuration. Water of the maximum outlet temperature of 150 degC will be used as a coolant. The control of the system for Northern Moravia is briefly described. (J.P.)

  15. AC power supply systems

    International Nuclear Information System (INIS)

    Law, H.

    1987-01-01

    An ac power supply system includes a rectifier fed by a normal ac supply, and an inverter connected to the rectifier by a dc link, the inverter being effective to invert the dc output of the receiver at a required frequency to provide an ac output. A dc backup power supply of lower voltage than the normal dc output of the rectifier is connected across the dc link such that the ac output of the rectifier is derived from the backup supply if the voltage of the output of the inverter falls below that of the backup supply. The dc backup power may be derived from a backup ac supply. Use in pumping coolant in nuclear reactor is envisaged. (author)

  16. Nuclear fuel cycle and its supply industrial system

    Energy Technology Data Exchange (ETDEWEB)

    Takei, M [Japan Energy Economic Research Inst., Tokyo

    1976-04-01

    This paper discusses problems about the supply and costs of nuclear fuel cycle referring to the discussions of IAEA's Advisory Group Meeting. As for natural uranium resources, prospect is given to the demand, supply, and cost trend up to 2000. As for uranium enrichment, the increasing capacity is compared with the projected demand. The comparison of cost characteristics between diffusion and centrifuge plants is presented with respect to plant scale, investment cost, electric power cost, and operation and maintenance cost. The fabrication cost for fuel is analyzed, and it is suggested that some cost down can be expected for the future. As for the mixed oxide fuel fabrication, the capacity in each country and the estimated fabrication costs for PWR, prototype fast breeder reactor and commercial fast breeder reactor are presented. As for reprocessing, the shortage of supply capacity and the needs for more storage capacity are emphasized. The estimated reprocessing cost for a new plant is also presented. Finally, the present status and future trend of fuel storage in each major country are reviewed.

  17. Concept of voltage monitoring for a nuclear power plant emergency power supply system (PWR 1300 MWe)

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1988-01-01

    Voltage monitoring concept for a Nuclear Power Plant Emergency Power Supply Systems (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and 3 NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  18. Report on emergency electrical power supply systems for nuclear fuel cycle and reactor facilities security systems

    International Nuclear Information System (INIS)

    1977-01-01

    The report includes information that will be useful to those responsible for the planning, design and implementation of emergency electric power systems for physical security and special nuclear materials accountability systems. Basic considerations for establishing the system requirements for emergency electric power for security and accountability operations are presented. Methods of supplying emergency power that are available at present and methods predicted to be available in the future are discussed. The characteristics of capacity, cost, safety, reliability and environmental and physical facility considerations of emergency electric power techniques are presented. The report includes basic considerations for the development of a system concept and the preparation of a detailed system design

  19. Report on emergency electrical power supply systems for nuclear fuel cycle and reactor facilities security systems

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    The report includes information that will be useful to those responsible for the planning, design and implementation of emergency electric power systems for physical security and special nuclear materials accountability systems. Basic considerations for establishing the system requirements for emergency electric power for security and accountability operations are presented. Methods of supplying emergency power that are available at present and methods predicted to be available in the future are discussed. The characteristics of capacity, cost, safety, reliability and environmental and physical facility considerations of emergency electric power techniques are presented. The report includes basic considerations for the development of a system concept and the preparation of a detailed system design.

  20. Nuclear information access system

    International Nuclear Information System (INIS)

    Ham, C. H.; Yang, M. H.; Yoon, S. W.

    1998-01-01

    The energy supply in the countries, which have abundant energy resources, may not be affected by accepting the assertion of anti-nuclear and environment groups. Anti-nuclear movements in the countries which have little energy resources may cause serious problem in securing energy supply. Especially, it is distinct in Korea because she heavily depends on nuclear energy in electricity supply(nuclear share in total electricity supply is about 40%).The cause of social trouble surrounding nuclear energy is being involved with various circumstances. However, it is very important that we are not aware of the importance of information access and prepared for such a situation from the early stage of nuclear energy's development. In those matter, this paper analyzes the contents of nuclear information access system in France and Japan which have dynamic nuclear development program and presents the direction of the nuclear access regime through comparing Korean status and referring to progresses of the regime

  1. A study on the international cooperation in the nuclear liability system related to the supply of nuclear power plants to North Korea

    Energy Technology Data Exchange (ETDEWEB)

    Ham, Chul Hoon.; Kim, Tae Myeong [The Catholic University, Seoul (Korea)

    2001-12-01

    System of nuclear damage compensation was prepares to protect the interested parties in the implementation of nuclearenterprise and conciliate the conflicts of interests of them. The Light-water Reactor (LWR) Project to supply two units of light-water reactors to North Korea faced difficulties concerning nuclear damage compensation system due to decline of the international reliability and aggravation of economic condition of North Korea. It is necessary to study the special nuclear damage compensation system of the LWR Project to promote the Project and peaceful uses of atomic energy in northeast Asia. The contents and scope of the study is composed as follows; 1. Background of the LWR Project . the pending issues of them and the necessary of the special nuclear damage compensation system 2. Investigation of nuclear damage compensation system of United States, Japan, German, France and Korea 3. Account of conventions on liability for nuclear damage, especially Vienna Convention and its Protocols 4. Searching for issues of the nuclear damage compensation system of the LWR Project and its resolution 5. Comprehensive arrangement on the main issues through the study. 4 tabs. (Author)

  2. Study of a nuclear energy supplied steelmaking system for near-term application

    International Nuclear Information System (INIS)

    Yan, Xing L.; Kasahara, Seiji; Tachibana, Yukio; Kunitomi, Kazuhiko

    2012-01-01

    Conventional steelmaking processes involve intensive fossil fuel consumption and CO 2 emission. The system resulting from this study ties a steelmaking plant to a nuclear plant. The latter supplies the former all energy and feedstock with the exception of iron ore. The actual design takes on a multi-disciplinary approach: The nuclear plant employs a proven next-generation technology of fission reactor with 950 °C outlet temperature to produce electricity and heat. The plant construction saving and high efficiency keep the cogeneration cost down. The steelmaking plant employs conventional furnaces but substitutes hydrogen and oxygen for hydrocarbons as reactant and fuel. Water decomposition through an experimentally-demonstrated thermochemical process manufactures the feedstock gases required. Through essential safety features, particular a fully-passive nuclear safety, the design achieves physical proximity and yet operational independence of the two plants to facilitate inter-plant energy transmission. Calculated energy and material balance of the integrated system yields slightly over 1000 t steel per 1 MWt yr nuclear thermal energy. The steel cost is estimated competitive. The CO 2 emission amounts to 1% of conventional processes. The sustainable performance, economical potential, robust safety, and use of verified technological bases attract near-term deployment of this nuclear steelmaking system. -- Highlights: ► A steelmaking concept is proposed based on multi-disciplinary approach. ► It ties advanced nuclear fission reactor and energy conversion to thermochemical manufacture and direct iron making. ► Technological strength of each area is exploited to integrate a final process. ► Heat and material balance of the process is made to predict performance and cost. ► The system rules out fossil fuel use and CO 2 emission, and is near-term deployable.

  3. Expert systems for analysis and management assistance of nuclear reactor electrical power supplies

    International Nuclear Information System (INIS)

    Evrard, J.M.; Souchet, Y.

    1988-01-01

    Electrical power supplies of nuclear plants are very complex systems. They are studied in many ways: failure consequences, probabilistic risk assessement, failure diagnosis, corrective actions in case of incident ... Knowledge base technology (expert systems) is very suited to solve these problems. A common structural representation can generate specific functional representations; thus we get coherency and easy evolution. This paper shows a two facet methodology: the plant description (both static and dynamic) and reasoning about it. Current applications are developed for pressurized water reactors and gas cooled reactors, using the SPIRAL expert system shell buil at CEA [fr

  4. Defence in depth for electric power supplies in Indian nuclear power plants

    International Nuclear Information System (INIS)

    Gupta, S.K.; Srivasista, K.; Solanki, R.B.

    2009-01-01

    The purpose of electric power supply system in a nuclear power plant is to supply and distribute reliable electric power to safety related systems and systems important to safety in various forms, arrangements and combinations of redundancy and diversity in order to perform safety functions required during operational states and design basis events (DBE) such as shutting down the reactor, maintaining the reactor in safe shutdown state, containment isolation and reactor core cooling preventing significant release of radioactive material to the environment. Hence the design basis of electric power supply systems includes identification of DBE that require power supplies, adequacy of redundancy and diversity, environmental conditions to which electric equipment are qualified, identification of loads requiring interrupted and uninterrupted power supplies, time sequence in which emergency loads are to be supplied in case of interruption, provisions for maintaining and testing, consideration for minimum duration capability of emergency power supplies during station blackout etc. Based on operation experience, results of probability safety assessment and certain weaknesses noticed in defence in depth of electric power supply systems, several continuous design improvements have been made in Indian nuclear power plants during operating phase and life extension. Instituting various tests during initial commissioning, subsequent operation and life extension has ensured high standards of performance of electric power supplies. Some of these aspects are highlighted in this paper

  5. Power supply trip control for nuclear reactor

    International Nuclear Information System (INIS)

    Hager, R.E.; Gutman, Jerzy.

    1987-01-01

    A control system for a trip coil in a switchgear mechanism controls the supply of electrical power to a process control device and ensures de-energization of the trip coil shortly after the trip coil is energized. The trip coil is energized not by an independent dc source as in prior art, but from rectified power from a step down transformer supplied from the switchgear output side. The transformer feeds a rectifier which is connected to the trip coil via a trip activation device. The output of the rectifier can be monitored using an optical converter to determine the ability of the control system to activate the trip coil and the condition of the power supplied to the process control device. The control device may be a rod positioner in a pressurised water nuclear reactor. (author)

  6. Transient evaluation using EMTP at single open phase with the offsite power transformer for the emergency power supply systems of nuclear power plants

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2017-01-01

    The emergency power supply systems of nuclear power plants, as the objects of this research, are critical in supplying stable electric power to such systems as the emergency core cooling system (ECCS), and in maintaining safety of the nuclear power reactor; this was apparent in the accident at the Fukushima Daiichi Nuclear Power Station. The Nuclear Regulatory Commission (USNRC) issued regulatory documents (BL 2012-011, IN 2012-032), and has commenced evaluations on newly discovered vulnerability in the design of power supply systems which cannot be detected with under-voltage protection relays, with certain kinds of configuration of coils and iron core structures, such as when the offsite power supply side is a Y-connection and the load side is a ⊿-connection etc., when the detection of single open phase fault with the circuit of a transformer which is without a ground fault connected to the offsite power supply system. This report uses simulation by the electro magnetic transients program (EMTP) and clearly describe the response at the time of the power supply single open phase without ground fault for various configuration of coils and various iron core structures of the three-phase transformer, and identify the important issues in the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the single open phase fault occurred without ground fault. This report describes the results of the simulations of operations of the protection relays of the emergency power supply systems and the safety related components of representative a domestic PWR plant with EMTP. This report explains the method to detect open-phase when the transformer is no-load which United States Electric Power Research Institute (EPRI) developed. As the detailed analyses data from EPRI related to the detection method concerned have not been disclosed officially yet, in this paper, the quantitative and detailed verification results

  7. An analysis of international nuclear fuel supply options

    Science.gov (United States)

    Taylor, J'tia Patrice

    As the global demand for energy grows, many nations are considering developing or increasing nuclear capacity as a viable, long-term power source. To assess the possible expansion of nuclear power and the intricate relationships---which cover the range of economics, security, and material supply and demand---between established and aspirant nuclear generating entities requires models and system analysis tools that integrate all aspects of the nuclear enterprise. Computational tools and methods now exist across diverse research areas, such as operations research and nuclear engineering, to develop such a tool. This dissertation aims to develop methodologies and employ and expand on existing sources to develop a multipurpose tool to analyze international nuclear fuel supply options. The dissertation is comprised of two distinct components: the development of the Material, Economics, and Proliferation Assessment Tool (MEPAT), and analysis of fuel cycle scenarios using the tool. Development of MEPAT is aimed for unrestricted distribution and therefore uses publicly available and open-source codes in its development when possible. MEPAT is built using the Powersim Studio platform that is widely used in systems analysis. MEPAT development is divided into three modules focusing on: material movement; nonproliferation; and economics. The material movement module tracks material quantity in each process of the fuel cycle and in each nuclear program with respect to ownership, location and composition. The material movement module builds on techniques employed by fuel cycle models such as the Verifiable Fuel Cycle Simulation (VISION) code developed at the Idaho National Laboratory under the Advanced Fuel Cycle Initiative (AFCI) for the analysis of domestic fuel cycle. Material movement parameters such as lending and reactor preference, as well as fuel cycle parameters such as process times and material factors are user-specified through a Microsoft Excel(c) data spreadsheet

  8. Power supply for nuclear power plant home consumption using inverter sources

    International Nuclear Information System (INIS)

    Stepar, V.; Tvrdik, J.

    1988-01-01

    A description is presented of the system configuration of a nuclear power plant with WWER-440 and WWER-1000 units and of a system of guaranteed power supply for the plant home consumption network for a WWER-440 power plant. The power supply network consists of 6 inverter supplies for safety systems, 4 supplies for nonsystem facilities and of a minimum of three power supplies for facilities outside the units. A diagram is shown and the principle described of the currently used ABP 1500 power supply system of Soviet origin. Using the experience from its operation, a Czechoslovak inverter supply system was designed featuring parallel operation of the inverter units. The principles are given for the design of a power supply system of an output of 75 kVA, the diagram is shown and the principle described. The design allows implementing and using the system without redundancy or in redundant operation of the 2 from 3 type at an installed capacity of 66%, or of the 1 from 2 type at an installed capacity of 50% of the output. The system is undergoing tests that should verify its reliability. (J.B.). 3 figs., 1 tab

  9. Siting studies for an asymptotic U.S. energy supply system based primarily on nuclear energy

    International Nuclear Information System (INIS)

    Burwell, C.C.

    1977-01-01

    The nuclear energy center (NEC) concept is an approach to siting wherein nuclear facilities would be clustered in and delimited to a relatively small number of locations throughout the United States. These designated centers would be concurrently developed to their full capability over several decades, at which time, they would be several times larger than the largest nuclear power stations in existence today. The centers would be permanently dedicated to nuclear operations including the future decommissioning of functionally obsolescent facilities as well as the commissioning of their replacements. The criteria for and characteristics of an acceptable nuclear energy system that could supply most of the U.S. energy requirements in the distant future are discussed. The time period is unspecified but occurs when fossil-fuel resources are depleted to such an extent that their use is economic only in special situations, and is not economic, in general, for use as fuel

  10. Concept of voltage and frequency monitoring for a nuclear power plant normal power supply system - PWR 1300 MWe

    International Nuclear Information System (INIS)

    Andrade, R.B. de

    1990-01-01

    Voltage and frequency monitoring concept for a Nuclear Power Plant Normal Power Supply System (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and e NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

  11. The Security of Energy Supply and the Contribution of Nuclear Energy

    International Nuclear Information System (INIS)

    2011-01-01

    What contribution can nuclear energy make to improve the security of energy supply? This study, which examines a selection of OECD member countries, qualitatively and quantitatively validates the often intuitive assumption that, as a largely domestic source of electricity with stable costs and no greenhouse gas emissions during production, nuclear energy can make a positive contribution. Following an analysis of the meaning and context of security of supply, the study uses transparent and policy-relevant indicators to show that, together with improvements in energy efficiency, nuclear energy has indeed contributed significantly to enhanced energy supply security in OECD countries over the past 40 years. Content: Foreword; Executive Summary; 1. The Security of Energy Supply and the Contribution of Nuclear Energy - Concepts and Issues: - Energy supply security: An introduction, - Why security of energy supply remains a policy issue in OECD countries, - The external dimension: import dependence, resource exhaustion and carbon policy, - The internal dimension: economic, financial and technical considerations for energy supply security - Orientations for government policies to enhance the security of energy supply, - Conclusions; 2. Indicators and Models for Measuring Security of Energy Supply Risks: - Introduction, - Different approaches towards designing the Supply/Demand Index, - A detailed review of selected security of supply indicators, - Comprehensive models for assessing the security of energy supply, - The Supply/Demand Index, - Concluding observations; 3. Evolution of the Security of Energy Supply in OECD Countries: - Time-dependent quantification of the security of energy supply, - Changes in security of supply in selected OECD countries, - Electricity generation and the security of energy supply, - The contribution of nuclear energy and energy intensity to the security of energy supply, - The geographical distribution of SSDI values, - Conclusions; 4. Public

  12. Nuclear Fuel Supply Arrangements through the IAEA

    International Nuclear Information System (INIS)

    Phuong, Ha-Vinh

    1981-10-01

    By virtue of its statutory functions, the International Atomic Energy Agency may be the depositary and also the supplier of nuclear materials made available to it by Member States, and these may then be stored in facilities it has acquired or which it has established under its control. However, this possibility did not materialize, mainly because the supplying states -few in number- do not want an international organization to become directly involved in bilateral transactions in that field. This paper analyses in particular the provisions of supply agreements concluded with the United Kingdom, the USA and the USSR. The Annex contains a Table of Agreements on supply of nuclear fuel and equipment concluded between supplying and consumer states through the IAEA. (NEA) [fr

  13. Nuclear power and ratepayer protest: The Washington Public Power Supply System crisis

    International Nuclear Information System (INIS)

    Sugai, W.H.

    1986-01-01

    In early 1982, the Washington Public Power Supply System (WPPSS) terminated two nuclear projects, triggering an episode of mass ratepayer insurgency throughout the state. In this survey of the crisis, the author analyzes the political and economic conditions that precipitated the protest and examines citizen opposition to the WPPSS nuclear venture between 1976 and 1981. The review of the public initiative campaigns aimed at the Northwest utility establishment by local antinuclear forces and the role of key individuals and organizations involved in anti-KPPSS activism are central to the discussion. By emphasizing the organizational dynamics of citizen opposition, the analysis clarifies the influence of antinuclear protest in bringing about the WPPSS crisis, which is still in litigation over disputed financial and management liability claims. Finally, the author offers insights into the implications of the 1980 Pacific Northwest Electric Power Planning and Conservation Act and the role of the new Northwest Power Planning Council in regional electrical energy planning

  14. Nuclear fusion power supply device

    International Nuclear Information System (INIS)

    Nakagawa, Satoshi.

    1975-01-01

    Object: To use a hybrid power supply device, which comprises a thyristor power supply and a diode power supply, to decrease cost of a nuclear fusion power supply device. Structure: The device comprises a thyristor power supply connected through a closing unit and a diode power supply connected in parallel through a breaker, input of each power supply being applied with an output voltage of a flywheel AC generator. When a current transformer is excited, a disconnecting switch is turned on to close the diode power supply and a current of the current transformer is increased by an automatic voltage regulator to a set value within a predetermined period of time. Next, the current is cut off by a breaker, and when the breaker is in on position, the disconnecting switch is opened to turn on the closing unit. Thus, when a plasma electric current reaches a predetermined value, the breaker is turned on, and the current of the current transformer is controlled by the thyristor power supply. (Kamimura, M.)

  15. Quality assurance system in nuclear engineering

    International Nuclear Information System (INIS)

    Adams, H.W.; Hoensch, V.

    1985-01-01

    Due to the close connection between the German Atomic Energy Law and the nuclear control regulations, quality systems in nuclear engineering have taken on a special form. Quality assurance systems as a stipulated organisation of structure and procedure to assure quality have implications for the organisation of the electric supply company at the planning, erection and commissioning stage and for the organisation of the nuclear power station facility. To supervise the application and effectiveness of the stipulated organisation of structure and procedure internally and externally among contractors, special organisation units have been set up at the plant suppliers, manufactures, electric supply companies and nuclear power station facilities, which in the electric supply field go by the name of Quality Assurance Supervision. (orig.) [de

  16. Reliability analysis of self-supply system of V-1 nuclear power plant

    International Nuclear Information System (INIS)

    Kuklik, B.

    The results are summarized of the fault tree analysis of the V-1 power plant self-consumption system. The 6 kV busbars providing power for the main circulating pumps, the steam generator feed pumps and other important components including the 0.4 kV busbars are of the highest importance for nuclear safety. A fault tree analysis was also made of the emergency core cooling system of the reactor. Dangerous faults are defined and fault trees are developed. A brief description is given of the calculation algorithm for a digital computer. Some results are discussed. The calculated reliability of the emergency core cooling system is 10 5 years, of the 6 kV busbars it is 6.6x10 4 years. In case of a permanent or a long-term outage of the 220 kV stand-bye power supply, the system reliability is reduced to 7x10 2 years. (Z.M.)

  17. Supply of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    Any large-scale atomic energy programme is inherently dependent on the availability of materials that can be used as fuel in reactors, and the International Atomic Energy Agency, at its inception, was intended to act as a bank for the flow of materials between Member States. According to its Statute, one of its primary functions is to provide materials 'to meet the needs of research on, and development and practical application of, atomic energy for peaceful purposes, including the production of electric power, with due consideration for the needs of the under-developed areas of the world'. If the Agency is to fulfil its Statutory function, it would be essential for it to have not only some ready sources of supply, but also an established framework of general terms and conditions on which it could secure the supplies. The latter would eliminate the need for going through elaborate procedural formalities whenever the Agency receives a new request for materials. Such a framework has now been established with the signing of broad agreements with three countries which had offered to supply various quantities of special fissionable materials to the Agency. These agreements, signed in Vienna on 11 May 1959, with the USSR, the UK and the USA, lay down the basic terms and conditions on which these three countries will make nuclear materials available when needed by the Agency. The USSR has agreed to make available to the Agency 50 kg of uranium-235, the UK 20 kg and the USA 5 000 kg. The material will be supplied in the form of enriched uranium in any concentration up to 20 per cent; the amounts mentioned relate to the 235-isotope content of the materials. The UK and the USA have agreed that the parties to a particular supply agreement may decide on higher enrichment of uranium to be used for research reactors, material testing reactors or for other research purposes. The USA has also agreed to make available to the Agency such additional supplies as would match in amount

  18. Heat supply of the town of Trnava from EBO nuclear plant

    International Nuclear Information System (INIS)

    Kovarik, Z.

    4 variants of central heat supply from the V-2 Bohunice nuclear power plant were considered. Three included the supply of hot water while the fourth envisaged the supply of steam. The variants of hot water supply differed in the proportion of heat supply during load peak, the range being from 75% to 88% to 100%. The system suggested considers hot water with a maximum overpressure of 2.5 MPa and temperature of 150/70 degC, with possible temporary decrease to 130/70 degC. The estimated power of heat exchange stations is 240 MW at a temperature gradient of 150/70 degC and 180 MW at a temperature gradient 130/70 degC. The location, design and control of the heat supply system and the specifications of heat generation facilities are given. (J.P.)

  19. Device for controlling water supply to nuclear reactor

    International Nuclear Information System (INIS)

    Iwasaki, Toshio.

    1974-01-01

    Object: To smoothly control automatic water supply for realizing stable operation of a nuclear reactor by providing a flow rate limiting signal selection circuit and a preferential circuit in a water supply control device for a nuclear reactor wherein the speed of a recirculation pump may be changed in two-steps. Structure: Opening angle signals for a water supply regulating valve are controlled by a nuclear reactor water level signal, a vapor flow rate signal and a supplied water flow rate signal through an adder and an adjuster in response to a predetermined water level setting signal. When the water in the reactor is maintained at a predetermined level, a selection circuit receives a water pump condition signal for selecting one of the signals from a supplied water rate limiting signal generator generating signals for indicating whether one or two water supply pumps are operated. A low value preferential circuit passes the lower of the values generated from the selection circuit and the adder. The selection circuit receives a recirculation pump condition signal and selects either one of the signals from the supplied water flow rate limiting signal generator operated at high speed or low speed. A high value preferential circuit passes the higher value

  20. Nuclear fuel supply: challenges and opportunities

    International Nuclear Information System (INIS)

    Lowen, S.

    2006-01-01

    Prices of uranium, conversion services and enrichment services have all significantly increased in the last few years. These price increases have generally been driven by a tightening in the supply of these products and services, mostly due to long lead times required to bring these products and services to the market. This paper will describe the various steps in the nuclear fuel cycle for natural and enriched uranium fuel, will discuss the development of the front-end fuel cycle for low void reactivity fuel, and will address the challenges faced in the long-term supply of each component, particularly in the light of potential demand increases as a result of a nuclear renaissance. The opportunities for new capacity and uranium production will be outlined and the process required to achieve sufficient new supply will be discussed. (author)

  1. RELAP/MOD1.5 analysis of steam line break transients for a 3-loop and a 4-loop Westinghouse nuclear steam supply system

    International Nuclear Information System (INIS)

    Peeler, G.B.; McDonald, T.A.; Kennedy, M.F.

    1984-01-01

    RELAP/MOD1.5 (Cycle 31 and 34) calculations were made to assess the assumptions used by Westinghouse (W) to analyze mainsteam line break transients. Models of a W 3-loop and 4-loop nuclear steam supply system were used. Sensitivity studies were performed to determine the effect of the availability of offsite power, break size and initial core power. Comparison with W results indicated that if the assumptions used by W are replicated within the RELAP5 framework, then the W methodology for prediction of the Nuclear Steam Supply System (NSSS) response is conservative for steam line break transients

  2. Prospects of heat supply from Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Kuba, V.

    1987-01-01

    The possibilities are discussed of using the Temelin nuclear power plant for heat supply to a number of localities in the South Bohemian Region, to a distance of up to 34 km. Direct supply of steam and of 150/70 degC or 180/65 degC hot water is envisaged. An alternative solution has also been proposed allowing to supply steam and hot water simultaneously from 180 degC hot water with quantitative regulation. The hot water is made to expand at a pressure of 0.3 to 0.5 MPa and the low-pressure steam is compressed to a pressure of 0.9 to 1.3 MPa. This steam will be supplied to the existing heating system. The possibility was also studied of supplying Prague with heat and 180/65 degC hot water of a thermal output of up to 1,700 MW using a two-pipe heat supply line of 105 to 125 km in length. (B.S.). 2 figs

  3. Approach to securing of stable nuclear fuel supplies

    International Nuclear Information System (INIS)

    Koike, Kunihisa; Imamura, Isao; Noda, Tetsuya

    2010-01-01

    With the dual objectives of not only ensuring stable electric power supplies but also preventing global warming, the construction of new nuclear power plants is being planned in many countries throughout the world. Toshiba and Westinghouse Electric Company (WEC), a member of the Toshiba Group, are capable of supplying both boiling water reactor (BWR) and pressurized water reactor (PWR) plants to satisfy a broad range of customer requirements. Furthermore, to meet the growing demand for the securing of nuclear fuel supplies, Toshiba and WEC have been promoting the strengthening and further expansion of supply chains in the fields of uranium production, uranium hexafluoride (UF 6 ) conversion, uranium enrichment, and fuel fabrication. (author)

  4. Legal aspects of nuclear fuel supply

    International Nuclear Information System (INIS)

    Sartorelli, C.

    1981-10-01

    This paper discusses the problems of nuclear fuel supply in the context of the types of purchase of uranium, the different technical operations involved (enrichment, reprocessing) and finally, the control exercised over such materials in the framework of IAEA Safeguards and the ''London Club'' agreement between the supplying countries. A description follows of the functions of the Euratom Supply Agency in application of the Euratom's Treaty's provisions on the principle of equal access to ores, source and special fissile materials for Community countries. (NEA) [fr

  5. Croatian National System of Nuclear Materials Control

    International Nuclear Information System (INIS)

    Biscan, R.

    1998-01-01

    In the process of economic and technological development of Croatia by using or introducing nuclear power or in the case of international co-operation in the field of peaceful nuclear activities, including international exchange of nuclear material, Croatia should establish and implement National System of Nuclear Materials Control. Croatian National System of accounting for and control of all nuclear material will be subjected to safeguards under requirements of Agreement and Additional Protocol between the Republic of Croatia and the International Atomic Energy Agency (IAEA) for the Application of Safeguards in Connection with the Treaty on the Non-Proliferation of Nuclear Weapons (NPT). The decision by NPT parties at the 1995 NPT Review and Extension Conference to endorse the Fullscope IAEA Safeguards Standard (FSS) as a necessary precondition of nuclear supply means that states are obliged to ensure that the recipient country has a FSS agreement in place before any nuclear transfer can take place (Ref. 1). The FSS standard of nuclear supply is a central element of the Nuclear Suppliers Group (NSG) Guidelines which the NSG adopted in 1992 and should be applied to members and non-members of the NSG. The FSS standard of nuclear supply in general allows for NPT parties or countries which have undertaken the same obligations through other treaty arrangements, to receive favourable treatment in nuclear supply arrangements. However, the Iraqi experience demonstrate that trade in nuclear and dual-use items, if not properly monitored, can contribute to a nuclear weapons program in countries acting contrary to their non-proliferation obligation. Multilateral nuclear export control mechanisms, including the FSS supply standard, provide the basis for co-ordination and standardisation of export control measures. (author)

  6. Introduction to nuclear supply chain management. In the context of fuel cycle strategy from LWR cycle system to FR cycle system

    International Nuclear Information System (INIS)

    Shiotani, Hiroki; Ono, Kiyoshi; Namba, Takashi; Yasumatsu, Naoto; Heta, Masanori

    2011-01-01

    Supply chain management (SCM) is an important technique to maintain supply and demand balance and to achieve total optimization from upstream to downstream in manufacturers' management. One of the major reasons why SCM receives much attention recently is the trend in production and sales systems from 'Push type' to 'Pull type'. 'Push type' can be restated as 'Make to Stock' (MTS). MTS is a type of supply chain in which the production is not connected to actual demand. On the contrary, 'Pull type' can be restated as 'Make to Order' (MTO) in which the production is connected to actual demand. In this paper, the terminologies and ideas of SCM was introduced into the scenario study to give a fresh perspective for considering LWR cycle to FR cycle transition strategies in Japan. Then, an analytical tool (SCM tool) which has been developed by the authors is used to survey Japanese nuclear energy system in transition with the SCM terminologies and viewpoints. When some of the Japanese nuclear fuel cycle strategies and tools are thought back with the framework of SCM, they tend to treat nuclear fuel cycle system as 'Push type' supply chain in their simulations. For example, a reprocessing plant separates SFs (spent fuels) without considering the actual Pu demand. However, because future reprocessing plants and fuel fabrication plants will act as Pu suppliers (front-end facility) to FR as well as back-end facilities of LWRs, the reasonable plant operation principle can be 'Pull type'. The analysis was conducted by the SCM tool to simulate the behaviors of both MTS and MTO type facilities during the LWR to FR transition period. If there are large uncertainties in the Pu demand or the load factor, etc. of future reprocessing plants, SCM framework is beneficial. Furthermore, the realization of MTO type operation by SCM can reduce the recovered Pu stock in spite of the increase of the SF interim storage. As the result of the investigation on the boundary location of 'Push type

  7. Uranium supply of the Swiss nuclear power plants

    International Nuclear Information System (INIS)

    Clausen, A.

    1991-01-01

    Securing the supply to Swiss nuclear power stations takes into account the fact that finished fuel elements must be introduced. The situation is, however, relieved by the fact there are excess capacities both in the amount of natural uranium available as well as in all processing stages. As further security, each nuclear power station keeps a reload of fuel elements in stock, so that if supplies are disrupted, continued operation is guaranteed for 1-2 years. Political influences should be taken into account, as should any repercussions that fuel disposal may have on fuel supply. 3 figs

  8. Quality assurance in nuclear fuel element component supply

    International Nuclear Information System (INIS)

    Jenkins, B.P.

    1987-01-01

    The paper describes the application of Quality Assurance to nuclear fuel element component supply. The Quality Assurance programme includes integrated procurement, purchasing, surveillance and receipt inspection functions. Purchasing policy is based on a consistent preference for competitive tendering. Multiple sourcing is used to encourage competitive pricing and increase security of supply. A receipt inspection facility is maintained to ensure the high product quality levels demanded by the nuclear industry. (U.K.)

  9. Power source system for nuclear fusion

    International Nuclear Information System (INIS)

    Nakagawa, Satoshi.

    1975-01-01

    Object: When using an external system power source and an exclusive power source in a power source circuit for supplying power to the coils of a nuclear fusion apparatus, to minimize the capacity of the exclusive power source and provide an economical power source circuit construction. Structure: In the initial stage of the power supply, rectifying means provided in individual blocks are connected in parallel on the AC side, and power is supplied to the coils of the nuclear fusion apparatus from an external system power source with the exclusive power source held in the disconnected state. Further, at an instant when the limit of permissible input is reached, the afore-mentioned parallel circuit consisting of rectifying means is disconnected, while at the same time the exclusive power source is connected to the input side of the rectifying means provided in a block corresponding to the exclusive power source side, thereby supplying power to the coils of the nuclear fusion apparatus from both the external system power source and exclusive power source. (Kamimura, M.)

  10. How current are EURATOM provisions on nuclear supply and ownership in view of the European Union's enlargement?

    International Nuclear Information System (INIS)

    Bouquet, A.

    2001-01-01

    This contribution is mainly based on two papers presented at nuclear law conferences in 1998 and 2001, respectively setting out the special provisions governing supplies of nuclear fuels to the European Union (Chapter 6 of the Treaty establishing the European Atomic Energy Community, hereinafter referred to as the 'Euratom Treaty') and the right of ownership of the Euratom Community (Chapter 8 of the Euratom Treaty). These special Treaty provisions cannot be compared to anything observed in other legal systems. Hence, with their introduction into the legal systems of the new European Union member states, the question arises as to how current these provisions are and how they have been implemented in practice. Two of the fundamental objectives of the Euratom Treaty most relevant in this field are to ensure that all users in the Community receive a regular and equitable supply of ores and nuclear fuels (Article 2d Euratom) and to exercise the Community's right of ownership with respect to special fissile materials (Article 2f Euratom). Furthermore, the objectives of ensuring the establishment of the basic installations necessary for the development of nuclear energy in the Community (Article 2c Euratom), of safeguarding that material is not diverted from its intended use (Article 2e Euratom), of establishing a common market (Article 2g Euratom) and of maintaining external relations (Article 2h Euratom) can be relevant to nuclear trade and to the Supply Agency's action. The Treaty's philosophy with regard to supply and ownership is the result of a delicate compromise between public authority interventionism and a more free market approach. The interventionism resulted in a monopolistic system of supplies (exclusive right to conclude contracts, right of option, public authority ownership), whereas the free market approach brought about the commercial organisation of the entity responsible for the implementation of supply provisions (separate legal entity, market

  11. The current and perspective problems of nuclear power fuel supply

    International Nuclear Information System (INIS)

    Solonin, M.I.; Konovalov, I.I.

    2003-01-01

    Conception of fuel supply is comprised of supplying of natural uranium resources, nuclear fuel production including engineering stages of refining, enriching, production, use of secondary uranium and plutonium raw materials. The structure of nuclear fuel cycle is considered. Enterprises of the Russian nuclear fuel cycle, world recourses and fundamental producers of uranium are performed, demands in natural uranium of Russian and frontier NPP to 2010 are demonstrated. Dynamics of the development of separate methods - diffusion and centrifugal is presented as well as parameters of fuel supply at Russian and frontier NPP are compared [ru

  12. Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems

    Directory of Open Access Journals (Sweden)

    Zhe Dong

    2016-01-01

    Full Text Available The modular high temperature gas-cooled reactor (MHTGR is a typical small modular reactor (SMR that offers simpler, standardized and safer modular design by being factory built, requiring smaller initial capital investment, and having a shorter construction period. Thanks to its small size, the MHTGRs could be beneficial in providing electric power to remote areas that are deficient in transmission or distribution and in generating local power for large population centers. Based on the multi-modular operation scheme, the inherent safety feature of the MHTGRs can be applicable to large nuclear plants of any desired power rating. The MHTGR-based nuclear steam supplying system (NSSS is constituted by an MHTGR, a side-by-side arranged helical-coil once-through steam generator (OTSG and some connecting pipes. Due to the side-by-side arrangement, there is a tight coupling effect between the MHTGR and OTSG. Moreover, there always exists the parameter perturbation of the NSSSs. Thus, it is meaningful to study the model-free coordinated control of MHTGR-based NSSSs for safe, stable, robust and efficient operation. In this paper, a new model-free coordinated control strategy that regulates the nuclear power, MHTGR outlet helium temperature and OTSG outlet overheated steam temperature by properly adjusting the control rod position, helium flowrate and feed-water flowrate is established for the MHTGR-based NSSSs. Sufficient conditions for the globally asymptotic closed-loop stability is given. Finally, numerical simulation results in the cases of large range power decrease and increase illustrate the satisfactory performance of this newly-developed model-free coordinated NSSS control law.

  13. Nuclear safety and energy supply security: conflict or goal?

    International Nuclear Information System (INIS)

    Kutas, S.

    2006-01-01

    Energy generation and safety problems at the nuclear power plant have been analysed. Nuclear power plants are operated on the commercial basis in many countries today. Safety and security in energy generation and distribution is a complex problem. Energy supply reliability, security energy price and other issues should be co-ordinated and solved at the same time. Decentralisation and deregulation means new challenges for regulatory bodies and assurance of security. International co-operation in this field is very important. Western European Nuclear Regulators' Association (WENRA) consolidates efforts of regulatory bodies of European countries in order to harmonize approaches of nuclear safety. Nuclear Safety, and security of energy supply is the task and goal at the same time. (author)

  14. Nuclear fuel supplies

    International Nuclear Information System (INIS)

    1960-01-01

    When the International Atomic Energy Agency was set up nearly three years ago, it was widely believed that it would soon become a world bank or broker for the supply of nuclear fuel. Some observers now seem to feel that this promise has been rather slow to come to fruition. A little closer analysis would, however, show that the promise can be fulfilled only in a certain objective context, and to the extent that this context exists, the development of the Agency's role has been commensurate with the actual needs of the situation

  15. Technical report on dc power supplies in nuclear power plants

    International Nuclear Information System (INIS)

    1977-06-01

    Emergency electrical power supplies, both a.c. and d.c. for nuclear power plants are important to safety. For this reason, the electric power systems for operating nuclear plants and those plants under licensing review have been required to provide a high degree of reliability. It is this high reliability that provides confidence that sufficient safety margin exists against loss of all d.c. power for extended periods of time to allow an orderly examination of safety issues, such as this. However, because of the importance of the a.c. and d.c. power systems, the staff has been expending effort to review the reliability of these systems and shall continue to do so in the future

  16. Specific properties of the electrical equipment in the nuclear steam supply system; Specificnosti elektricne opreme u primarnom djelu nuklearne elektrane

    Energy Technology Data Exchange (ETDEWEB)

    Smiljanic, D [Rade Koncar Institut, Zagreb (Yugoslavia)

    1979-07-01

    The paper presents description of reactor coolant pump motor in the primary coolant loop. The motor is treated as a representative of all electrical equipment in the nuclear steam supply system that has to meet all the requirements concerning reliability, minimum maintenance, radiation, seismic etc. (author)

  17. Computer determination of event maps with application to auxiliary supply systems

    International Nuclear Information System (INIS)

    Wredenberg, L.; Billinton, R.

    1975-01-01

    A method of evaluating the reliability of sequential operations in systems containing standby and alternate supply facilities is presented. The method is based upon the use of a digital computer for automatic development of event maps. The technique is illustrated by application to a nuclear power plant auxiliary supply system. (author)

  18. Conflict nuclear power. Theses for current supply with and without nuclear power

    International Nuclear Information System (INIS)

    Schwarz, E.

    2007-01-01

    In the context of a lecture at the 2nd Internationally Renewable Energy Storage Conference at 19th to 21st November, 2007, in Bonn (Federal Republic of Germany), the author of the contribution under consideration reports on theses for current supply with and without nuclear power. (1) Theses for current supply with nuclear energy: Due to a relative amount of 17 % of nuclear energy in the world-wide energy production and due to the present reactor technology, the supplies of uranium amount nearly 50 to 70 years. The security of the nuclear power stations is controversially judged in the public and policy. In a catastrophic accident in a nuclear power station, an amount of nearly 2.5 billion Euro is available for adjustment of damages (cover note). The disposal of radioactive wastes is not solved anywhere in the world. The politically demanded separation between military and civilian use of the nuclear energy technology is not possible. The exit from the nuclear energy is fixed in the atomic law. By any means, the Federal Republic of Germany is not insulated in the European Union according to its politics of nuclear exit. After legal adjustment of the exit from the nuclear energy the Federal Republic of Germany should unfold appropriate activities for the re-orientation of Euratom, Nuclear Energy Agency and the International Atomic Energy Agency. The consideration of the use of nuclear energy in relation to the risks has to result that its current kind of use is not acceptable and to be terminated as fast as possible. (2) Theses for current supply without nuclear energy: The scenario technology enables a transparency of energy future being deliverable for political decisions. In accordance with this scenario, the initial extra costs of the development of the renewable energies and the combined heat and power generation amount approximately 4 billion Euro per year. The conversion of the power generation to renewable energies and combined heat and power generation

  19. Labor supply of engineers and scientists for nuclear electric utilities, 1987-1992

    International Nuclear Information System (INIS)

    Blair, L.M.

    1988-01-01

    An assessment of the adequacy of the supply of health physicists, nuclear engineers, and other engineers for the nuclear electric utility industry is based on job openings for scientists and engineers in broader nuclear-power-related fields, which include engineering and design, manufacturing, fabrication, supporting services, and government. In assessing the likely adequacy of labor supplies for commercial nuclear power job openings over the next 5 yr, consideration has been given to competing sources of labor demands, including nuclear energy research and development activities, nuclear defense, and the total US economy, and to the likely supply of new graduates. In particular, over the last 3 yr, the number of degrees awarded and enrollments in nuclear engineering programs have declined 12 and 14%, respectively, and in health physics programs, 5 and 14%, respectively. For health physics and nuclear engineers, tight labor market conditions (i.e. labor supplies and demand balanced at relatively high salaries) are expected over the next 5 yr because of declining enrollments and slowly growing employment levels plus job replacement needs. The commercial nuclear power field is expected to face tight labor markets for electrical and materials engineers because of strong competing demands in the economy. Other engineering occupations are likely to have adequate supplies for the nuclear power field but at salaries that continue to be relatively higher than salaries for other professional occupations

  20. A re-evaluation of nuclear plant offsite power supplies

    International Nuclear Information System (INIS)

    William E Berger; Robert E Henry

    2005-01-01

    Full text of publication follows: De-regulation of the electric power industry has resulted in separate ownership of the transmission and power generation facilities as well as a revised format for operating the transmission facilities. Currently we see the transfer of large blocks of bulk power between markets which can impact the voltage regulation at the offsite power supply. Where Nuclear Plant operations once knew with a large degree of certainty the operating range of the system supplying the offsite power supply, this may no longer be the case and more challenges to the safety systems could result. These challenges may manifest themselves as either a loss of offsite power or voltage levels approaching the degraded level setpoints. In this paper we will first explore what challenges are caused by deregulation and how they impact offsite power supply operations. Next we will incorporate the knowledge grained regarding accidents and consequences from the Individual Plant Evaluations (IPE's) to see how the offsite power supply could be operated to mitigate the challenges and extend the capacity of the auxiliary power system. Various scenarios will be examined using the Modular Accident Analysis Program (MAAP) as an integral plant model. MAAP simulations that include both the plant thermal hydraulic responses and corresponding electric power demand are presented to demonstrate the impact of alternate approaches to offsite power system operation. The original design phase of the offsite and onsite power distribution system was based on a criterion relating to the starting of all safety loads if a safety injection signal was present independent of the accident or its progression. The IPE and risk informed insights that are readily available today will be applied in the re-analyses of the offsite distribution system response. (authors)

  1. Nuclear energy and the security of energy supply

    International Nuclear Information System (INIS)

    Bertel, E.

    2005-01-01

    Security of energy supply was a major concern for OECD governments in the early 1970. Since then, successive oil crises, volatility of hydrocarbon prices, as well as terrorist risks and natural disasters, have brought the issue back to the centre stage of policy agendas. In this paper, the author discusses the problem of energy supply security. Can security of supply be measured? What is the role of government and of nuclear energy? And what are measures for ensuring security of supply? (A.L.B.)

  2. Ventilation-air conditioner system in nuclear power plant

    International Nuclear Information System (INIS)

    Kubota, Ryuji; Sugisaki, Toshihiko.

    1989-01-01

    This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

  3. The use of engineering features and schematic solutions of propulsion nuclear steam supply systems for floating nuclear power plant design

    International Nuclear Information System (INIS)

    Achkasov, A.N.; Grechko, G.I.; Pepa, V.N.; Shishkin, V.A.

    2000-01-01

    In recent years many countries and the international community represented by the IAEA have shown a notable interest in designing small and medium size nuclear power plants intended for electricity and heat generation for remote areas. These power plants can be also used for desalination purposes. As these nuclear plants are planned for use in areas without a well-developed power grid, the design shall account for their transportation to the site in complete preparedness for operation. Since the late 80s, the Research and Development Institute of Power Engineering (RDIPE) has carried out active efforts in designing reactor facilities for floating nuclear power plants. This work relies on the long-term experience of RDIPE engineers in designing the propulsion NSSS. Advantages can be gained from the specific engineering solutions that are already applied in the design of propulsion Nuclear Steam Supply System (NSSS) or from development of new designs based on the proven technologies. Successful implementation of the experience has been made easier owing to rather similar design requirements prescribed to ship-mounted NSSS and floating NPP. The common design targets are, in particular, minimization of mass and dimensions, resistance to such external impacts as rolling, heel and trim, operability in case of running aground or collision with other ships, etc. (author)

  4. Westinghouse Small Modular Reactor nuclear steam supply system design

    Energy Technology Data Exchange (ETDEWEB)

    Memmott, M. J.; Harkness, A. W.; Van Wyk, J. [Westinghouse Electric Company LLC, 600 Cranberry Woods Drive, Cranberry Twp. PA 16066 (United States)

    2012-07-01

    The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the first in a series of four papers which describe the design and functionality of the Westinghouse SMR. Also described in this series are the key drivers influencing the design of the Westinghouse SMR and the unique passive safety features of the Westinghouse SMR. Several critical motivators contributed to the development and integration of the Westinghouse SMR design. These design driving motivators dictated the final configuration of the Westinghouse SMR to varying degrees, depending on the specific features under consideration. These design drivers include safety, economics, AP1000{sup R} reactor expertise and experience, research and development requirements, functionality of systems and components, size of the systems and vessels, simplicity of design, and licensing requirements. The Westinghouse SMR NSSS consists of an integral reactor vessel within a compact containment vessel. The core is located in the bottom of the reactor vessel and is composed of 89 modified Westinghouse 17x17 Robust Fuel Assemblies (RFA). These modified fuel assemblies have an active core length of only 2.4 m (8 ft) long, and the entirety of the core is encompassed by a radial reflector. The Westinghouse SMR core operates on a 24 month fuel cycle. The reactor vessel is approximately 24.4 m (80 ft) long and 3.7 m (12 ft) in diameter in order to facilitate standard rail shipping to the site. The reactor vessel houses hot and cold leg channels to facilitate coolant flow, control rod drive mechanisms (CRDM), instrumentation and cabling, an intermediate flange to separate flow and instrumentation and facilitate simpler refueling, a pressurizer, a straight tube, recirculating steam

  5. Maintenance management of emergency power supply equipment (uninterruptible power supply) in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Nishida, Kyosuke; Hiyama, Hisao; Shibata, Satomi; Iwasaki, Shogo; Inami, Shinichi

    2009-01-01

    Uninterruptible power supply systems are installed in the Tokai reprocessing plant in preparation for the emergency case that the commercial power supply is stopped by an accidental or intentional interruption in the supply of electricity. The uninterruptible power supply system particularly provides a temporary power source to the important devices for the radiation control of nuclear critical monitoring in the plant. Thus, the system is potentially important and essential for nuclear plants. The paper reports the current activities such as regular inspections, replacement of parts and system update, to maintain the function of uninterruptible power supply systems. (author)

  6. Development of the on-site power supply in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Simon, M. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany)

    1986-02-15

    The design of the on-site power supply is different in German Nuclear Power Plants, depending on age and size of the plant. The cause for this is the evolution of the safety requirements. The general development of the design of safety Systems, which resulted in a strict separation of redundant trains is also reflected in the design of the emergency power system and even the complete on-site power supply System. This will be demonstrated by different examples. The advantages of this design with respect to the availability of on-site power will be explained and verified by means of operating experience. (author)

  7. Evaluation of a seafloor nuclear power supply and its potential applications. Final report

    International Nuclear Information System (INIS)

    1977-01-01

    The seafloor nuclear power supply (SNPS) concept has been proposed by Atomics International (AI) and Lockheed Petroleum Services, Ltd. (LPS) as a source of electrical energy for subsea pumping of petroleum products. It consists of a small nuclear reactor, moderated by zirconium hydride (ZrH) and cooled by liquid metal (NaK), which drives a 3-MW turbine/generator system using toluene as the working fluid. Arthur D. Little, Inc., was selected to assess the technical and economic feasibility of a SNPS, and to determine if potential applications for a SNPS might exist in offshore-oil-field development schemes where conventional power supplies could not be used. It was determined that the concept is technically feasible, with regard to the nuclear, marine, electrical, and petroleum engineering aspects. However, its initial cost of $14 million and operating expenses of $900,000 per year are considerably more in each case than the costs of conventional alternative power supplies. For the type of field development proposed as an example by LPS, a combination of gas turbines and dc cables would cost about $8 million. Fuel in the form of gas from the wells would be available at near-zero cost in almost all cases of field development, so that operating expenses would be minimal. Other power supply and cable systems were investigated, up to lengths of 200 miles. Alternating-current systems are preferred at distances less than 20 miles; direct current is more economical at greater distances. No set of circumstances was found in which oil field development is likely to occur and for which the SNPS offers uniquely attractive capabilities

  8. Nuclear power as a regional energy supply

    International Nuclear Information System (INIS)

    MacLoon, Frank.

    1983-02-01

    The author describes the Point Lepreau nuclear power plant and its impact on the electric power grid and the economy of the small province of New Brunswick. The 600 MW CANDU reactor is considered suitable for small operations and has an excellent world record. Although nuclear energy has high capital costs, its fuel costs are low, thus rendering it comparatively inflation free. Its fuel costs of 3 to 4 mills are contrasted with 40 mills for oil-fuelled units. The cost advantage of uranium over coal and oil permits New Brunswick to put aside funds for waste management and decommissioning. Regulatory streamlining is needed to reduce both expense and time of construction. The CANDU system is ideally suited to providing base load, with coal as an intermediate load supply and hydro for peaking. There is room for tidal power as a future part of the mix

  9. Nuclear reactor power supply

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

    The redundant signals from the sensor assemblies measuring the process parameters of a nuclear reactor power supply are transmitted each in its turn to a protection system which operates to actuate the protection apparatus for signals indicating off-process conditions. Each sensor assembly includes a number of like sensors measuring the same parameters. The sets of process signals derived from the sensor assemblies are each in its turn transmitted from the protection system to the control system which impresses control signals on the reactor or its components to counteract the tendency for conditions to drift off-normal status requiring operation of the protection system. A parameter signal selector is interposed between the protection system and the control system. This selector prevents a parameter signal of a set of signals, which differs from the other parameters signals of the set by more than twice the allowable variation of the sensors which produce the set, from passing to the control system. The selectors include a pair of signal selection units, one unit sending selected process signals to primary control channels and the other sending selected process signals to back-up control channels. Test signals are periodically impressed by a test unit on a selected pair of a selected unit and control channels. When test signals are so impressed the selected control channel is disabled from transmitting control signals to the reactor and/or its associated components. This arrangement eliminates the possibility that a single component failure which may be spurious will cause an inadvertent trip of the reactor during test

  10. Security of supply of uranium as nuclear fuel

    International Nuclear Information System (INIS)

    Guzman Gomez-Selles, L.

    2011-01-01

    When we talk about Sustainability related to nuclear fuel, the first concern that comes to our mind is about the possibility of having guarantees on the uranium supply for a sufficient period of time. In this paper we are going to analyze the last Reserves data published by the OCD's Red Book and also how the Reserve concept in fully linked to the uranium price. Additionally, it is demonstrated how the uranium Security of supply is guaranteed for, at least, the next 100 years. finally, some comments are made regarding other sources of nuclear fuel as it is the uranium coming from the phosphates or the thorium. (Author)

  11. New nuclear projects: structure, supply chain and financing

    International Nuclear Information System (INIS)

    Keppler, J.H.; Cometto, M.

    2015-01-01

    In 2015 there were 68 reactors being constructed throughout the world and 159 projects were planned. The projects for the construction of nuclear reactors face challenging issues like financing and management. The NEA (Nuclear Energy Agency) has analysed the feedback experience on a sample of reactor projects and of reactors recently commissioned in order to draw lessons on 3 issues: financing, long-term electricity price, and project management including the supply chain. It is already known that technologies requiring high initial capital like nuclear power or renewable energies, are very sensitive to the long-term price of electricity. The study shows that for a debt ratio below 60%, the risk for the investor is low even if the long-term electricity price drops by 30 %. Because of the complexity of the construction of a nuclear power plant there are mainly 3 types of project management: the turnkey project, the split package approach (a relatively low number of suppliers) and the multi-contract approach. The turnkey approach is favoured by the new entrants in the nuclear world. The harmonization of regulations and the convergence of the safety requirements are necessary to build an efficient and competitive supply chain. (A.C.)

  12. A model of Altio Lazio boiling water reactor using the LEGO code nuclear steam supply system simulation

    International Nuclear Information System (INIS)

    Garbossa, G.B.; Spelta, S.; Cori, R.; Mosca, R.; Cento, P.

    1989-01-01

    An extensive effort has been made at the Italian National Electricity Board (ENEL) to construct and validate a LEGO model capable of simulating the operational transients of the Alto Lazio Nuclear Station, a two-twin units site with BWR/6 class reactors, rated at 2894 MWt and with Mark III containment. The desired end-product of this effort is an overall plant model consisting of the Nuclear Steam Supply System model, described in this paper, and the Balance of Plant model, capable of simulating the transient response of Alto Lazio Station. The models utilize the in-house developed LEGO code, which is a modular package oriented to power plant modeling and suitable to perform transient analyses to assist during power plant design, control system design and operating procedure verification. The ability of the NSSS model to predict correctly the plant response is demonstrated through comparison with results calculated by the vendor, using REDY code, and by an in-house RETRAN-02 model

  13. Economic feasibility of heat supply from simple and safe nuclear plants

    International Nuclear Information System (INIS)

    Tian, J.

    2001-01-01

    Use of nuclear energy as a heating source is greatly challenged by the economic factor since the nuclear heating reactors have relative small size and often the lower plant load factor. However, use of very simple reactor could be a possible way to economically supply heat. A deep pool reactor (DPR) has been designed for this purpose. The DPR is a novel design of pool type reactor for heat only supply. The reactor core is put in a deep pool. By only putting light static water pressure on the core coolant, the DPR will be able to meet the temperature requirements of heat supply for district heating. The feature of simplicity and safety of DPR makes a decrease of investment cost compared to other reactors for heating only purposes. According to the economical assessments, the capital investment to build a DPR plant is much less than that of a pressurized reactor with pressure vessels. For the DPR with 120 or 200 MW output, it can bear the economical comparison with a usual coal-fired heating plant. Some special means taken in DPR design make an increase of the burn-up level of spent fuel and a decrease of fuel cost. The feasibility studies of DPR in some cities in China show that heating cost using nuclear energy is only one third of that by coal and only one tenth of that by nature gas. Therefore, the DPR nuclear heating system provides an economically attractive solution to satisfy the demands of district heating without contributing to increasing greenhouse gas emissions

  14. Bibliography: books and articles on nuclear waste, nuclear power and power supply during the years 1971-1987

    International Nuclear Information System (INIS)

    Djerf, M.; Hedberg, P.

    1988-06-01

    The bibliography provides a list of the supply published Swedish books and articles in periodicals on nuclear waste and nuclear power. Regarding book publication the bibliography comprises publications on questions of nuclear power and nuclear waste on the whole, whereas the bibliography on the periodical articles solely comprises nuclear waste questions. The book bibliography consists of a selective choice of publications, identified by a mapping of the total supply of information on energy- and nuclear power issues in articles and other publications in Sweden. The literature inventory as a whole is part of a grater research project aiming at a study of the role of mass media in forming public opinion about the nuclear power waste question. (O.S.)

  15. The global nuclear fuel market - supply and demand 1995-2015

    International Nuclear Information System (INIS)

    Keese, H.; Kidd, S.

    1996-01-01

    The findings and main conclusions of the 1996 supply and demand report of the Uranium Institute are summarised. The previous report was published in June 1994. In 1994 and 1995, world uranium production remained at a relatively depressed level, accounting for just over half reactor requirements only. Since mid 1995, however, some increase in production has occurred alongside rises in uranium spot market prices. This may indicate that supply is becoming tighter and indicate the end of the perception that supply availability is unlimited. Answers are attempted to the questions about the future which arise from this development. Nuclear power is first set in the context of the market for energy and for electricity in particular. The report then identifies key issues for the longer term future for nuclear power and considers various aspects of nuclear fuel supply and demand over the next 20 years. Three demand scenarios are explored. Even in the lower requirements case, the overall conclusion is that supply will only meet demand from 2002 onwards when all the projected new mine capacity is in place. Adequate supply is heavily dependent on other supply sources in the higher case scenarios. The market will need the entry of blended down high enriched uranium from dismantled weapons and an increased contribution from the reprocessing of spent fuel. Additional primary production is only likely if financial incentives are available and the regulatory framework permits. Finally, there is the possibility of re-enriching depleted uranium. (9 figures). (UK)

  16. Safety evaluation report related to the operation of WPPSS Nuclear Project No. 2, Docket No. 50-397, Washington Public Power Supply System

    International Nuclear Information System (INIS)

    1982-12-01

    Supplement 2 to the Safety Evaluation Report for Washington Public Power Supply System's application for a license to operate WNP-2 (Docket No. 50-397), located in Benton County, Washington, approximately 12 miles north of Richland, Washington, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report and Supplement 1

  17. Nuclear fuel cycle requirements and supply considerations, through the long-term

    International Nuclear Information System (INIS)

    1978-02-01

    The OECD Nuclear Energy Agency and the International Atomic Energy Agency have for many years published a joint report entitled ''Uranium Resources, Production and Demand'', and a revised edition of this work, dated December 1977, is now available. This report, on the other hand, is the result of a separate study of the supply and demand outlook for all fuel cycle services, as well as for uranium, through the long-term. The work was undertaken by the Nuclear Energy Agency's Working Party on Uranium Demand, whose members are listed in Appendix III. The intent here has been to contribute to the orderly development of nuclear power, by: 1. identifying potential problems in the supply of uranium and fuel cycle services, and possible areas for international co-operation in the resolution of such problems; 2. examining several long-range scenarios to determine the comparative needs of advanced reactors for uranium and for supporting services, thereby establishing the basis for the further development of uranium resources and specific reactor systems; and 3. assisting those having responsibilities in planning, forecasting, and programme management. This report is the work of a group of technical experts and does not necessarily reflect official policy or endorsement of the report's projections and conclusions by the Member Governments of the Nuclear Energy Agency

  18. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

    This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

  19. Proposal of modification of the Atucha I nuclear power plant's emergency power supply system

    International Nuclear Information System (INIS)

    Palacio, Pedro; Dabove, Mario

    1989-01-01

    The emergency power supply system of Atucha I N.P.P. consists of three 50% diesel generators. During the transient from normal power supply to emergency power supply (approximately 15 seconds) an hydraulic generator takes care of the emergency system. By this way, the emergency busbars constitute themselves an interruption free system. The two emergency busbars work normally coupled. This proposal consists of the following modifications: 1) Add a new diesel generator in order to allow the operation with two diesel generators per busbar. 2) To work with the two emergency busbars not coupled as normal operation mode. 3) To eliminate the hydraulic generator from the emergency power supply system, in order to simplify the operation and to reduce the failure possibility. Without the hydraulic turbine generator, the emergency busbars loose the interruption free condition. For this reason, for the loads that are not able for this mode of operation and are connected to the emergency power supply system, two additional low-voltage interruption free busbars are necessary. Finally, this proposal is compared with the Atucha II N.P.P. emergency power supply system. (Author)

  20. RI Mapping System for Identification of Radiological Contamination in Environmental Water Supply System

    Energy Technology Data Exchange (ETDEWEB)

    Na, Teresa W.; Ha, Jang Ho; Kim, Han Soo; Lee, Seung Hyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Na, Teresa W.; Lee, Rena [Ewha Womans Univ., Hospital, Seoul (Korea, Republic of)

    2012-03-15

    The interest of radiation protection has risen due to accidents of the Nuclear Power Plant, nuclear terrorism, and the radiological contamination in the city, In this respect, the development of environmental radiation monitoring for the radiological contaminants has been studied. In this study, the experiment for the radiological contamination in the water supply pipe line system has been simulated and preliminarily tested. The CsI(Tl)-PIN diode detectors were used and the preliminary test of radiation monitoring system was performed as multi detection system. The 2D image reconstruction algorithm was also developed for feasibility of the constructed multi-detection system.

  1. Supply of Prague with heat from a nuclear heat source

    International Nuclear Information System (INIS)

    Poul, F.

    1976-01-01

    The proposals are discussed of supplying Prague, the Czechoslovak Capital, with nuclear reactor-generated heat energy. The proposals meet the requirements of the general urban plan of development. The first nuclear heating plant is to be sited in the Kojetice locality, in the northern Prague suburb. It will be commissioned by 1984 and 1985. It is estimated that the maximum heat output in form of hot water will be 821 MW. By 1995 the construction of the second nuclear heating plant should be started southeast or east of Prague. The connection of these two nuclear plants to the hot water mains together with other conventional heating plants will secure the heat supply for Prague and its new housing estates and industrial works. (Oy)

  2. Supply Security in Future Nuclear Fuel Markets

    Energy Technology Data Exchange (ETDEWEB)

    Seward, Amy M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wood, Thomas W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gitau, Ernest T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ford, Benjamin E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-11-18

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs – that is, reactors likely to be licensed and market ready over the next several decades – that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  3. Supply Security in Future Nuclear Fuel Markets

    International Nuclear Information System (INIS)

    Seward, Amy M.; Wood, Thomas W.; Gitau, Ernest T.; Ford, Benjamin E.

    2013-01-01

    Previous PNNL work has shown the existing nuclear fuel markets to provide a high degree of supply security, including the ability to respond to supply disruptions that occur for technical and non-technical reasons. It is in the context of new reactor designs - that is, reactors likely to be licensed and market ready over the next several decades - that fuel supply security is most relevant. Whereas the fuel design and fabrication technology for existing reactors are well known, the construction of a new set of reactors could stress the ability of the existing market to provide adequate supply redundancy. This study shows this is unlikely to occur for at least thirty years, as most reactors likely to be built in the next three decades will be evolutions of current designs, with similar fuel designs to existing reactors.

  4. Nuclear fuel supply view in Argentina

    International Nuclear Information System (INIS)

    Cirimello, R.O.

    1997-01-01

    The Argentine Atomic Energy Commission promoted and participated in a unique achievement in the R and D system in Argentina: the integration of science technology and production based on a central core of knowledge for the control and management of the nuclear fuel cycle technology. CONUAR SA, as a fuel manufacturer, FAE SA, the manufacturer of Zircaloy tubes, CNEA and now DIOXITEC SA producer of Uranium Dioxide, have been supply, in the last ten years, the amount of products required for about 1300 Tn of equivalent U content in fuels. The most promising changes for the fuel cycle economy is the Slight Enriched Uranium project which begun in Atucha I reactor. In 1997 seventy five fuel assemblies, equivalent to 900 Candu fuel bundles, will complete its irradiation. (author)

  5. Nuclear fuel supply and demand in Western Europe 1991-2004

    International Nuclear Information System (INIS)

    Brusa, L.

    1992-01-01

    For the past ten years, Unipede and Open have jointly conducted an annual survey among their respective European members about nuclear programmes and nuclear fuel cycle requirements and supplies (uranium and enrichment). Its geographical scope is Western Europe, restricted to those countries having a current nuclear power programme. The respondents are the electric utilities in Belgium, Finland, France, Germany (western Laender only), Italy, the Netherlands, Spain, Sweden, Switzerland and the United Kingdom. Exclusively electric utilities are surveyed here, i.e. excluding national procurement organizations, traders, brokers, financial institutions, etc. For those countries where more than one utility is active, the responses covers the whole of the country electrical system and not only that of the respondents. The data, obtained from the individual utilities in the same format, are aggregated and form the basis of the report. This surveys cover uranium and enrichment requirements and supplies, recycling of uranium and plutonium, inventories; the quality of the data is guaranteed by the fact that the respondents are generally those people who are responsible for the day-to-day management of the nuclear fuel cycle in their country. The 1991 survey was launched in early June and replies were received between late June and September. This report aims at analysing the aggregated results of the survey and at providing some comments on the evolution of major parameters from the previous years. (author) 13 figs., refs

  6. The logistics and the supply chain in the Juzbado Nuclear Fuel Manufacturing Plant

    International Nuclear Information System (INIS)

    2005-01-01

    The paper describe the logistics and the supply chain in the Juzbado Nuclear Fuel Manufacturing Plant, located in Juzbado in the province of Salamanca. In the the article are described the principal elements in the supply chain and the difficulties of its management derived from the short period for the manufacturing of the nuclear fuel. It's also given a view in relation to the transportation by land sea of the nuclear components, uranium oxide powder and the manufactured fuel. The characteristics of the supply chain are determined by the plant production forecast, by the origin and high technology of the raw materials and by nuclear fuel delivery site locations. (Author)

  7. Issues Associated with IAEA Involvement in Assured Nuclear Fuel Supply Arrangements

    Energy Technology Data Exchange (ETDEWEB)

    Kessler, Carol E.; Mathews, Carrie E.

    2008-02-08

    Assured nuclear fuel supply has been discussed at various times as a mechanism to help limit expansion of enrichment and reprocessing (E&R) capability beyond current technology holders. Given the events in the last few years in North Korea and Iran, concern over weapons capabilities gained from acquisition of E&R capabilities has heightened and brought assured nuclear fuel supply (AFS) again to the international agenda. Successful AFS programs can be valuable contributions to strengthening the nonproliferation regime and helping to build public support for expanding nuclear energy.

  8. A valuation study of fuel supply stability of nuclear energy

    International Nuclear Information System (INIS)

    Nagano, Koji; Nagata, Yutaka; Hitomi, Kazumi; Hamagata, Sumio; Asaoka, Yoshiyuki

    2008-01-01

    In order to assess potential benefits of nuclear power with regard to its characteristics of fuel supply stability, the following three aspects are valuated under the Japanese energy and electricity mix: a) economic stability; i.e. nuclear power's contribution to the whole energy and electricity mix in terms of resistance to fluctuation and/or fuel price hikes, b) procurement stability; i.e. natural uranium, the raw fuel material for nuclear power generation, is being imported from more reliable sources through adequately diverse markets than in the cases of oil and natural gas, and, c) passive reserve effect; i.e. fuel materials as running stocks at power stations and fuel service facilities could maintain nuclear power generation running for a certain duration under unexpected disruption of fuel supply. (author)

  9. Nuclear supplier assessment how to control the nuclear supply chain quality?

    International Nuclear Information System (INIS)

    Henckes, A.

    2010-01-01

    With a road map of 84 (low scenario) to 198 (high scenario)* nuclear power plants to be build in the coming decade arise with intensity safety concerns. The challenge for governments and for nuclear companies as they increase construction is to manage a growing army of contractors and subcontractors worldwide and the quality of their production as well as their ability to deliver in time considering the speed-up and increasing pace of project development. Moreover by the last few years, the scope of needs for nuclear companies to set a QA/QC plan all along the supply chain has been increasingly enlarged with new stakes such as cost savings, social responsibilities and technical compliance. At last, with 'nuclear renaissance', the path to renew accreditation of existing suppliers facing international and domestic law/regulations combinations after a long period of low tide is now clear and wide. Nuclear operating companies and EPIC contractors now face a complex situation where on one side political pressure is hugely strong for a zero incident status to be considered as on the contrary the 'renaissance' will be suddenly stopped, on the other the status of 'industrial' maturity of the supply chain candidates is difficult to assess in a uniform and 'fair' way. Through this paper, the speaker will explain the full size supplier assessment strategy from paper to field which has been implemented in the Oil and Gas sector whose requirements of quality is high too. The speaker will present the key practices of this initiative from which the nuclear market can find more than a source of inspiration. (authors)

  10. Advanced marine reactor MRX and application to nuclear barge supplying electricity and heat

    International Nuclear Information System (INIS)

    Ishida, Toshihisa; Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Fukuhara, Yoshifumi; Ochiai, Masa-aki

    2000-01-01

    The basic design concept of an advanced marine reactor MRX has been established with adoption of several new technologies. The MRX is an integral-type PWR with 100 MWt aimed basically for use of ship propulsion. Adoption of a water-filled containment together with the integral type reactor makes the reactor light-weight and compact greatly. A engineered safety system is a simplified passive system, function of which is confirmed by the safety analysis. The MRX can be applied to an energy supply system of electricity and heat co-generation by installing it on a barge. Concept of a nuclear barge with the MRX of 334 MWt output is presented for use of supplying electricity, fresh water and hot water. Combined system of electric generation and desalination with the RO process can deliver variable output of electricity and fresh water according a demand. Latent heat of the exhausted steam from the turbine can be used effectively to raise the temperature of cold water as heat supply. (author)

  11. Nuclear energy in Canada: the CANDU system

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1979-10-01

    Nuclear electricity in Canada is generated by CANDU nuclear power stations. The CANDU reactor - a unique Canadian design - is fuelled by natural uranium and moderated by heavy water. The system has consistently outperformed other comparable nuclear power systems in the western world, and has an outstanding record of reliability, safety and economy. As a source of energy it provides the opportunity for decreasing our dependence on dwindling supplies of conventional fossil fuels. (auth)

  12. How can nuclear phaseout and climate protection be combined? Sustainable power supply in the residential sector

    International Nuclear Information System (INIS)

    Vallentin, Rainer

    2011-01-01

    The nuclear phaseout and the resulting energy turnaround will bring about changes in the power supply systems, especially if climate protection goals are to be reached. The author presents the example of a housing development in Germany which mirrors the private households sector. It is shown that the only way to achieve sustainable power supply is by consequently enhancing efficiency and by decarbonizing heat and power supply. The next two decades will be decisive.

  13. Redundancy of Supply in the International Nuclear Fuel Fabrication Market: Are Fabrication Services Assured?

    International Nuclear Information System (INIS)

    Seward, Amy M.; Toomey, Christopher; Ford, Benjamin E.; Wood, Thomas W.; Perkins, Casey J.

    2011-01-01

    For several years, Pacific Northwest National Laboratory (PNNL) has been assessing the reliability of nuclear fuel supply in support of the U.S. Department of Energy/National Nuclear Security Administration. Three international low enriched uranium reserves, which are intended back up the existing and well-functioning nuclear fuel market, are currently moving toward implementation. These backup reserves are intended to provide countries credible assurance that of the uninterrupted supply of nuclear fuel to operate their nuclear power reactors in the event that their primary fuel supply is disrupted, whether for political or other reasons. The efficacy of these backup reserves, however, may be constrained without redundant fabrication services. This report presents the findings of a recent PNNL study that simulated outages of varying durations at specific nuclear fuel fabrication plants. The modeling specifically enabled prediction and visualization of the reactors affected and the degree of fuel delivery delay. The results thus provide insight on the extent of vulnerability to nuclear fuel supply disruption at the level of individual fabrication plants, reactors, and countries. The simulation studies demonstrate that, when a reasonable set of qualification criteria are applied, existing fabrication plants are technically qualified to provide backup fabrication services to the majority of the world's power reactors. The report concludes with an assessment of the redundancy of fuel supply in the nuclear fuel market, and a description of potential extra-market mechanisms to enhance the security of fuel supply in cases where it may be warranted. This report is an assessment of the ability of the existing market to respond to supply disruptions that occur for technical reasons. A forthcoming report will address political disruption scenarios.

  14. Development of Supervisory Control and Data Acquisition (SCADA) Electrical Supply in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Zainudin Jaafar; Mohd Ashhar Khalid; Mohd Hanafiah Chik

    2015-01-01

    Nuclear Power supplies in Malaysia supplied from the power utility company Tenaga Nasional Berhad through several substations before reaching the building and equipment. The power supply is received and passed down through the 11000 V high voltage switch gears to 415 V 3-phase or 1-phase 240 V. The equipment used in this process is dangerous and monitoring hardware operating remotely (remote) is the best as only guard machinery may engage in business operations. Similarly, the supply of electrical parameters should be monitored to ensure safe and continuous supply of and according to the appropriate voltage for record and analysis when needed. This paper discusses the monitoring and data acquisition is performed using the system 'Supervisory Control And Data Acquisition (SCADA) was developed. (author)

  15. Nitrogen gas supply device in nuclear power plant

    International Nuclear Information System (INIS)

    Nishino, Masami

    1991-01-01

    The present invention concerns a nitrogen gas supply device in a nuclear power plant for supplying nitrogen gases to a reactor container and equipments working with the nitrogen gas as the load. A liquid nitrogen storage pool is disposed to a concrete nuclear buildings and has a two-vessel structure of inner and outer vessels, in which heat insulators are disposed between the inner and the outer vessels. Further, the nitrogen gas supply mechanism is disposed in an evaporation chamber disposed in adjacent with the liquid nitrogen storage pool in the reator building. Accordingly, since liquid nitrogen is stored in the liquid nitrogen storage pool having a structure surrounded by concrete walls, direct sunlight is completely interrupted, thereby enabling to prevent the heat caused by the direct sunlight from conducting to the liquid nitrogen. Further, since the outer vessel is not exposed to the surrounding atmosphere, heat conduction rate relative to the external air is small. This can reduce the amount of liquid nitrogen released to the atmospheric air due to natural evaporation. (I.N.)

  16. The Importance of Reliable Nuclear Power For Energy Supply

    International Nuclear Information System (INIS)

    Blix, Hans

    1989-01-01

    The severe accident at Chernobyl in 1986 caused a setback in public acceptance of nuclear power practically everywhere in the world. In some countries, the media even give the impression that nuclear power is on the way out worldwide, because of concerns about safety, radioactive waste disposal, and the risk of proliferation of nuclear weapons. Let me give you a more accurate picture of the situation. At the beginning of this year there were about 430 nuclear power reactors in operation in 26 countries around the world and they produced more than 16% of the world's electric energy. That amount of electricity is equal to the total amount of electric energy that was produced in the world in 1956. I mention this because, when we concentrate on the problems which nuclear power is facing, we tend to forget that among all the major energy sources? coal, oil, gas, hydro and nuclear- it is nuclear which has experienced the fastest rise in relative importance for the global energy supply. Its contribution to global energy supply has increased from just under 1% in 1974 to about 5% in 1987. On the positive side we can note the continuation of strong nuclear power programmes with construction starts in France and Japan, the start of construction at Sizewell B, which marks a new departure for nuclear power in the United Kingdom, and the orders for the Korean units 11 and 12

  17. Environmental inventories for future electricity supply systems for Switzerland

    Energy Technology Data Exchange (ETDEWEB)

    Dones, R; Gantner, U; Hirschberg, S [Paul Scherrer Inst. (PSI), Villigen (Switzerland); Doka, G; Knoepfel, I [Eidgenoessische Technische Hochschule, Zurich (Switzerland)

    1996-02-01

    This report provides the analysis of environmental inventories for selected electricity supply systems considered as possible options to meet the expected electricity demand in Switzerland in year 2030. Two possible electricity demand level cases were postulated by VSE, both under the basic assumption of economic growth: a high-growth demand case corresponding to a yearly increase of 2% from year 1995 to year 2010 and 1% from year 2010 to year 2030, and a low-growth demand case corresponding to a yearly increase of 1% from year 1995 to year 2010 and 0.5% from year 2010 to year 2030. The base (i.e. secured) supply in year 2030 will be, according to VSE, totally dominated by hydro with rather minor contributions from combined heat-and-power plants, small gas turbines, incinerators and solar photovoltaic plants. Due to decommissioning of the currently operating nuclear power plants and expiration of long-term electricity import contracts there will eventually occur a gap between the postulated electricity demand and the base supply. VSE provided seven options to cover this gap, defined in terms of mixes with different contributions from gas, coal, nuclear and solar chains; in this context a distinction is also made with respect to shares of domestic and imported electricity. The systems considered represent advanced technologies, regarded as either typical or most suitable for the Swiss conditions. System-specific input to the present analysis has been partially generated based on direct contacts with the industry. Life Cycle Analysis (LCA) was used to establish environmental inventories for the systems analysed. The analysis has been performed on three levels:(1) individually for each system considered, (2) comparison of systems, (3) comparison of supply options. Results are also provided for these three levels.

  18. Supply of science and engineering graduates for the United States nuclear industry

    International Nuclear Information System (INIS)

    Baker, J.G.; Blair, L.M.

    1993-01-01

    The concern in the USA about the adequacy of supply of new graduate scientists and engineers to meet technical employment needs, is particularly acute within the nuclear field because of declines in the number of education programs and number of students in nuclear engineering, health physics, and radiochemistry. The decline in the number of new graduates is assessed in comparison to current and projected future employment needs. Currently, supplies of new graduates are just meeting employment needs in nuclear engineering and are less than adequate in health physics and radiochemistry. If the number of graduates does not increase these inadequacies of supply are likely become more severe in the future. 5 figs

  19. Energy supply and nuclear energy

    International Nuclear Information System (INIS)

    Heitzer, H.

    1977-01-01

    The author emphasizes the necessity and importance of nuclear energy for the energy supply and stresses the point that it is extremely important to return to objective arguments instead of having emotional disputes. In this connection, it would be necessary for the ministries in question to have clear-cut political responsibility from which, under no circumstances, they may escape, and which they cannot pass on to the courts either. Within the framework of listing present problems, the author is concerned with the possibility of improved site planning, the introduction of a plan approval procedure and questions concerning immediately enforceable nuclear licences. He also deals with a proposal, repeatedly made, to improve nuclear licensing procedures on the one hand by introducing a project-free site-appointment procedure, and on the other hand by introducing a simplified licensing procedure for facilities of the same kind. Splitting the procedure into site and facility would make sense solely for the reason that in many cases the objections are, above all, directed against the site. (HP) [de

  20. Development of hot water supply system for a small district heating reactor

    International Nuclear Information System (INIS)

    Murase, Toshihiko; Narabayashi, Tadashi; Shimazu, Yoichiro

    2007-01-01

    On the earth, there are many environmental problems. For example, rapid increase of world population causes the enormous consumption of fossil fuel and emission of CO 2 into the global air. Now, mankaind faced to deal with these serious problems. One solution for these problems is utilization of nuclear reactors. Currently, about 65% of thermal output of a nuclear reactor is thrown away to the sea or the atmosphere through a turbine condenser. When a hot-water pipeline from a nuclear plant will be constructed, the exhaust heat from nuclear reactor will able to be utilized. Therefore, authors began to study nuclear power plant system for district heating. This reactor is based on a PWR plant. Its thermal output is 10 MWth and its electrical output is 3.4 MW. The nuclear plant supply electricity and heat for 2000 to 3000 houses. The plant aim to supply all the energy for the adjacent pepole's life, for example, heat, electricity and hydrogen for fuel battery car. This total-energy supply system assumed to be built in Northern area such as Hokkaido in Japan. In order to develop an optimum thermal design method for the system, heat transport experiments and thermal-hydraulic calculations were carried out. Using a metal pipe covered with foam-polyurethane thermal insulator, feed-water temperature and return-water temperature was measured to evaluate heat loss. As the result, the heat loss from the hot-water temperature was very little. The thermal-hydraulic calculation method was verified and applied to actual pipeline size calculation. The result of heat loss calculation will be 0.2degC/5 km. considering these results, the best pipe specification was obtained. (author)

  1. Supply, operation and radioactive waste disposal of nuclear power plants

    International Nuclear Information System (INIS)

    Mohrhauer, H.; Krey, M.; Haag, G.; Wolters, J.; Merz, E.; Sauermann, P.F.

    1981-07-01

    The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP) [de

  2. Supply chain of steel industries for the nuclear power plant construction in Indonesia

    International Nuclear Information System (INIS)

    Dharu Dewi; Sahala M Lumbanraja

    2017-01-01

    Nuclear Power Plant (NPP) Construction needs steel materials for the manufacturing of heavy components and civil work construction. National industries is expected to supply steel components especially for non nuclear component needs. Supply chain of steel industries is required to know the potency of steel industries from upstream to downstream industries which can support the NPP construction sustainability. The type of steel needed in the NPP construction consist of structure steel, rebar, steel plate, etc. The aim of the study is to identify supply chain of steel industries from upstream industries to downstream industries so that they can supply steel needs in the NPP construction. The methodology used are literature review and industries survey by purposive sampling test which sent questionnaires and carrying out technical visits to the potential industries to supply steel components for NPP construction. From the analysis of the questionnaires and survey, it has been obtained that the Indonesian steel industries capable of supplying steel for construction materials of non-nuclear parts are PT. Krakatau Steel, PT. Gunung Steel Group (PT Gunung Garuda and PT. Gunung Raja Paksi), PT. Cilegon Fabricators and PT. Ometraco Arya Samanta. While steel materials for primary components with nuclear grade, such as steel materials for reactor vessels and pressure vessels, the Indonesian steel industry has not been able to supply them. Therefore, the Indonesian steel industries must improve its capability, both in raw material processing and fabrication capability in order to meet the requirements of specifications, codes and standards of nuclear grade. (author)

  3. Maintaining a balanced electricity supply favours increased nuclear capacity in Finland

    International Nuclear Information System (INIS)

    Ahti, Toivola

    2001-01-01

    Finland's electricity supply is based on a balanced mix of energy sources to maximize the security of supply and to keep the volatility of electricity price at a minimum. One third of electricity is obtained from domestic sources hydro, wood and peat. Nuclear power provides one quarter and fossil fuels slightly over one fifth. Electricity imports from neighbour countries cover the rest of the consumption. It is important to maintain this balanced structure also when electricity supply is being increased. Domestic renewable sources are not enough to cover the predicted future needs, and increasing imports would risk the security of supply. Increasing the proportion of fossil fuels is not a generally desired option. Therefore, balanced increase of nuclear capacity has to be included among the choices of future electricity generation. (author)

  4. Holistic-integrated analysis and evaluation of nuclear energy for sustainable energy supply; Ganzheitlich-integrierte Betrachtung der Kernenergie im Hinblick auf eine nachhaltige Energieversorgung

    Energy Technology Data Exchange (ETDEWEB)

    Wissel, Steffen [Stuttgart Univ. (Germany). Inst. fuer Energiewirtschaft und Rationelle Energieanwendung (IER)

    2012-11-01

    Germany has decided in 2011 nuclear phase-out by the end of 2022. The European Commission is still convinced of the safe use of nuclear energy as option for carbon reduction in the energy supply. In the European energy market the decisions of neighboring countries have an impact on the national energy systems. The contribution covers a holistic-integrated analysis based on technical, economic and ecologic aspects of nuclear energy for sustainable energy supply in comparison with other fossil and renewable systems.

  5. Small nuclear power reactor emergency electric power supply system reliability comparative analysis; Analise da confiabilidade do sistema de suprimento de energia eletrica de emergencia de um reator nuclear de pequeno porte

    Energy Technology Data Exchange (ETDEWEB)

    Bonfietti, Gerson

    2003-07-01

    This work presents an analysis of the reliability of the emergency power supply system, of a small size nuclear power reactor. Three different configurations are investigated and their reliability analyzed. The fault tree method is used as the main tool of analysis. The work includes a bibliographic review of emergency diesel generator reliability and a discussion of the design requirements applicable to emergency electrical systems. The influence of common cause failure influences is considered using the beta factor model. The operator action is considered using human failure probabilities. A parametric analysis shows the strong dependence between the reactor safety and the loss of offsite electric power supply. It is also shown that common cause failures can be a major contributor to the system reliability. (author)

  6. Supplying the six. [Supplies of nuclear fuels and ores to the European Community

    Energy Technology Data Exchange (ETDEWEB)

    Oboussier, F

    1975-07-01

    Under the Euratom Treaty, the European Community must ensure that all users in the Community receive a regular and equitable supply of ores and nuclear fuels. Supply to users in the Community of ores, source materials, and special fissile materials is based on the principle of equal access of the users to the supply sources. To ensure such equal access, the Treaty prohibits all practices designed to secure a privileged position for certain users. In addition, an agency has been set up with two essential rights--that of an option on all ores, source materials, and special fissile materials produced in the territories of the Member States; and the exclusive right to conclude all contracts relating to the supply of ores, source materials, and special fissile materials coming from inside the Community or from outside. Dealings of the Agency with outside agencies, especially the former US AEC, are described. The uranium market and its economics and the availability of special fissile materials are summarized. (MCW)

  7. ORTAP: a nuclear steam supply system simulation for the dynamic analysis of high temperature gas cooled reactor transients

    International Nuclear Information System (INIS)

    Cleveland, J.C.; Hedrick, R.A.; Ball, S.J.; Delene, J.G.

    1977-01-01

    ORTAP was developed to predict the dynamic behavior of the high temperature gas cooled reactor (HTGR) Nuclear Steam Supply System for normal operational transients and postulated accident conditions. It was developed for the Nuclear Regulatory Commission (NRC) as an independent means of obtaining conservative predictions of the transient response of HTGRs over a wide range of conditions. The approach has been to build sufficient detail into the component models so that the coupling between the primary and secondary systems can be accurately represented and so that transients which cover a wide range of conditions can be simulated. System components which are modeled in ORTAP include the reactor core, a typical reheater and steam generator module, a typical helium circulator and circulator turbine and the turbine generator plant. The major plant control systems are also modeled. Normal operational transients which can be analyzed with ORTAP include reactor start-up and shutdown, normal and rapid load changes. Upset transients which can be analyzed with ORTAP include reactor trip, turbine trip and sudden reduction in feedwater flow. ORTAP has also been used to predict plant response to emergency or faulted conditions such as primary system depressurization, loss of primary coolant flow and uncontrolled removal of control poison from the reactor core

  8. A compact HV supply for field/PC based nuclear instrumentation

    International Nuclear Information System (INIS)

    Manna, A.; Nikhare, D.M.; Madhavi, V.; Bayala, A.K.; Mukhopadhyay, P.K.; Kataria, S.K.

    2001-01-01

    In the recent years, most of the nuclear instruments that were earlier based on NIM Bin standards, are becoming available as PC Add-on cards. This trend is due to the decreasing prices of desktop personal computers and the necessity for automation in radioactivity measurements. This paper describes the design and development of a HV supply module and its PC Add-on card version for field portable/ PC based nuclear instrumentation. The HV supply though being very compact in size meets all the stringent specifications required for detector biasing applications and it has been tested for use with NaI, BF 3 . (author)

  9. Addressing the supply security of the nuclear fuel cycle: a US merchant generator risk acceptance perspective

    International Nuclear Information System (INIS)

    Jordan, R. P.; Benavides, P.A.

    2006-01-01

    With the current rising markets across the nuclear fuel supply spectrum, understanding and managing nuclear fuel cycle supply security risk becomes an increasingly important consideration. In addressing this area, Constellation Energy is implementing an integrated multifaceted approach as consistent with a comprehensive risk profile covering the nuclear fuel supply industry. This approach is founded on use of a utility traditional procurement strategy, as dependent on the qualitative parameters of supply origination diversification, geopolitical stability, contracting duration and individual supplier financial bases. However, Constellation also adds an additional consideration into development of this nuclear fuel supply risk profile. To do such, qualitative assessments covering specific supplier risks, as based on the parameters of supplier management and organizational structure, design capacities (applicable to fabrication and enrichment only), operational history as applicable to forward-looking performance, regulatory or legal history and financial performance are also considered. Constellation overlays the risks of future availabilities, catastrophic occurrences and prices for each nuclear fuel material and service component onto a quantitative set of results. The overall focus of these assessments is the creation of a risk management perspective directed towards determining the potential loss or delay of nuclear fuel supply for our operating reactors. The conclusion of this effort is an integrated assessment of the nuclear fuel supply security as applicable to the Constellation-specific structured risk profile. Use of this assessment allows Constellation to target appropriate suppliers of interest in the marketplace and form the fundamental bases for the Constellation procurement strategy while managing risks associated with nuclear fuel cycle supply security. (authors)

  10. Nuclear fuel cycles : description, demand and supply estimates

    International Nuclear Information System (INIS)

    Gadallah, A.A.; Abou Zahra, A.A.; Hammad, F.H.

    1985-01-01

    This report deals with various nuclear fuel cycles description as well as the world demand and supply estimates of materials and services. Estimates of world nuclear fuel cycle requirements: nuclear fuel, heavy water and other fuel cycle services as well as the availability and production capabilities of these requirements, are discussed for several reactor fuel cycle strategies, different operating and under construction fuel cycle facilities in some industrialized and developed countries are surveyed. Various uncertainties and bottlenecks which are recently facing the development of some fuel cycle components are also discussed, as well as various proposals concerning fuel cycle back-end concepts. finally, the nuclear fuel cycles activities in some developing countries are reviewed with emphasis on the egyptian plans to introduce nuclear power in the country. 11 fig., 16 tab

  11. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

    International Nuclear Information System (INIS)

    1980-06-01

    This NASAP assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improvng the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness

  12. Prediction on Human Resource Supply/Demand in Nuclear Industry Using Markov Chains Model and Job Coefficient

    International Nuclear Information System (INIS)

    Kwon, Hyuk; Min, Byung Joo; Lee, Eui Jin; You, Byung Hoon

    2006-01-01

    According to the recent report by the OECD/NEA, there is a large imbalance between supply and demand of human resource in nuclear field. In the U.S., according to survey of Nuclear Engineering Department Heads Organization (NEDHO), 174 graduates in B.S or M.S degree were fed to nuclear industry in year 2004. Meanwhile, the total amount of demand in nuclear industry was about 642 engineers, which was approximately three times of the supply. In case of other developed western nations, the OECD/NEA report stated that the level of imbalance is similar to that of the U.S. However, nations having nuclear power development programs such as Korea, Japan and France seem to be in a different environment of supply and demand from that of the U.S. In this study, the difference of manpower status between the U.S and Korea has been investigated and the nuclear manpower required for the future in Korea is predicted. To investigate the factors making difference between the U.S. and NPP developing countries including Korea, a quantitative manpower planning model, Markov chains model, is applied. Since the Markov chains model has the strength of analyzing an inflow or push structure, the model fits the system governed by the inflow of manpower. A macroscopic status of manpower demand on nuclear industry is calculated up to 2015 using the Job coefficient (JC) and GDP, which are derived from the Survey for Roadmap of Electric Power Industry Manpower Planning. Furthermore, the total numbers of required manpower and supplied manpower up to 2030 were predicted by JC and Markov Chains model, respectively. Whereas the employee status of nuclear industries has been annually investigated by KAIF since 1995, the following data from the 10 th survey and nuclear energy yearbooks from 1998 to 2005 are applied; (a) the status of the manpower demand of industry, (b) number of students entering, graduating and getting job in nuclear engineering

  13. Prediction on Human Resource Supply/Demand in Nuclear Industry Using Markov Chains Model and Job Coefficient

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Hyuk; Min, Byung Joo; Lee, Eui Jin; You, Byung Hoon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2006-07-01

    According to the recent report by the OECD/NEA, there is a large imbalance between supply and demand of human resource in nuclear field. In the U.S., according to survey of Nuclear Engineering Department Heads Organization (NEDHO), 174 graduates in B.S or M.S degree were fed to nuclear industry in year 2004. Meanwhile, the total amount of demand in nuclear industry was about 642 engineers, which was approximately three times of the supply. In case of other developed western nations, the OECD/NEA report stated that the level of imbalance is similar to that of the U.S. However, nations having nuclear power development programs such as Korea, Japan and France seem to be in a different environment of supply and demand from that of the U.S. In this study, the difference of manpower status between the U.S and Korea has been investigated and the nuclear manpower required for the future in Korea is predicted. To investigate the factors making difference between the U.S. and NPP developing countries including Korea, a quantitative manpower planning model, Markov chains model, is applied. Since the Markov chains model has the strength of analyzing an inflow or push structure, the model fits the system governed by the inflow of manpower. A macroscopic status of manpower demand on nuclear industry is calculated up to 2015 using the Job coefficient (JC) and GDP, which are derived from the Survey for Roadmap of Electric Power Industry Manpower Planning. Furthermore, the total numbers of required manpower and supplied manpower up to 2030 were predicted by JC and Markov Chains model, respectively. Whereas the employee status of nuclear industries has been annually investigated by KAIF since 1995, the following data from the 10{sup th} survey and nuclear energy yearbooks from 1998 to 2005 are applied; (a) the status of the manpower demand of industry, (b) number of students entering, graduating and getting job in nuclear engineering.

  14. Auxiliary System Load Schemes in Large Thermal and Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kuzle, I.; Bosnjak, D.; Pandzic, H.

    2010-01-01

    Uninterrupted auxiliary system power supply in large power plants is a key factor for normal operation, transient states, start-ups and shutdowns and particularly during fault conditions. Therefore, there are many challenges in designing the main electrical system as well as the auxiliary systems power supply. Depending upon the type of fuel used and the environmental control system required, a thermal power plant may consume as much as 10% of its total generation for auxiliary power, while a nuclear power plant may require only 4 - 6% auxiliaries. In general, the larger the power generating plant, the higher the voltage selected for the AC auxiliary electric system. Most stations in the 75 to 500 MW range utilize 4,2 kV as the base auxiliary system voltage. Large generating stations 500 - 1000 MW and more use voltage levels of 6,9 kV and more. Some single dedicated loads such as electric driven boiler feed pumps are supplied ba a 13,8 kV bus. While designing the auxiliary electric system, the following areas must be considered: motor starting requirements, voltage regulation requirements, short-circuit duty requirements, economic considerations, reliability and alternate sources. Auxiliary power supply can't be completely generalized and each situation should be studied on its own merits to determine the optimal solution. Naturally, nuclear power plants have more reliability requirements and safety design criteria. Main coolant-pump power supply and continuity of service to other vital loads deserve special attention. This paper presents an overview of some up-to-date power plant auxiliary load system concepts. The main types of auxiliary loads are described and the electric diagrams of the modern auxiliary system supply concepts are given. Various alternative sources of auxiliary electrical supply are considered, the advantages and disadvantages of these are compared and proposals are made for high voltage distribution systems around the thermal and nuclear plant

  15. Modification of Japanese first nuclear ship reactor for a regional energy supply system using gadolinia as a burnable poison

    International Nuclear Information System (INIS)

    Sato, Kotaro; Shimazu, Yoichiro; Narabayashi, Tadashi; Tsuji, Masashi

    2009-01-01

    In our laboratory, a small regional energy supply system which uses a small nuclear reactor has been studied for a long time. This system could supply not only heat but also electricity. Heat could be used for hot-water supply, a heating system of a house, melting snow and so on. In this point, this system seems to be useful for the places like northern part of Japan where it snows in winter. This reactor is based on Nuclear Ship Mutsu which was developed as the first nuclear ship of Japan about 40 years ago. It has several advantages for a small reactor. For example, its moderator temperature coefficient is always to be deeply negative because boric acid solution is not used in moderator and coolant. This can lead to a self-controlled operation without control rod maneuvering for load change. But some modifications have been performed in order to satisfy requirements such as (1) longer core life without refueling and reshuffling, (2) reactivity adjustment for load change without control rods or soluble boron, (3) simpler operations for load changes and (4) ultimate safety with sufficient passive capability. In our previous study, we confirmed the core based on Mutsu core had longer core life (about 10 years) using high uranium enrichment fuel (more than 5wt%) and current 17x17 fuel assemblies. We also confirmed excess reactivity during the cycle could be suppressed using combination of erbium oxide (Er 2 O 3 ) and gadolinium oxide (Gd 2 O 3 ) as burnable poisons. Er 2 O 3 has advantages such that criticality safety can be kept even if uranium enrichment is more than 5wt% and burnup characteristics of the core can be gradual. But at this time there are 2 problems to apply for the core using Er 2 O 3 in Japan. First problem is that more than 5wt% enrichment fuel is not yet accepted in Japan. Second problem is that there are no experiences of using Er 2 O 3 in commercial reactors in Japan. Considering these problems, we have to modify the design of the core, using

  16. The importance of nuclear power to energy supply in Switzerland

    International Nuclear Information System (INIS)

    Kiener, E.

    2001-01-01

    The use of nuclear power is a matter of dispute also in Switzerland. The first opposition to plans for the Kaiseraugst nuclear power station near Basel sprang up in the seventies. In Switzerland, referenda are a popular expression of political disputes. On a federal level, a total of six referenda have been conducted about nuclear power since 1979. As a rule, antinuclear projects were rejected by a slim majority, except for the 1990 moratorium initiative. As a consequence, there was a ten-year ban on the construction of new nuclear power plants. Despite efforts by many parties it was not possible to develop a general consensus on an energy supply strategy. Because of the considerable importance to the power economy, and the economy at large, of nuclear power in Switzerland, where the five nuclear power plants in operation generate approx. 38% of the country's electricity, while 58% is produced in hydroelectric plants, a new Nuclear Power Act was adopted by Parliament in late February 2001. It constitutes the framework for the continued safe operation of nuclear power plants, keeps the nuclear option open for future planning, and handles spent fuel and waste management, final storage, and decommissioning. Also possible international solutions of final storage outside of Switzerland are taken into account. In this way, the Swiss government and parliament have advocated the continued use of nuclear power as one element of energy supply. (orig.) [de

  17. Transient evaluation using EMTP at one phase opening of the offsite power transformer of the emergency power supply systems for nuclear power plants. This report is a follow-up the last year's

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2014-01-01

    The emergency power supply systems of nuclear power plants, as the objects of this research, are critical to supplying stable electric power to such systems as the emergency core cooling system (ECCS), and to maintaining the safety of the nuclear power reactor; this was apparent from the accident at the Fukushima Daiichi Nuclear Power Station. The USNRC issued regulatory documents (BL 2012-01, IN 2012-03), and has commenced to review those problems which cannot be detected by degraded-voltage protection relays such as new design vulnerability of the power supply systems that are certain kinds of winding structures and iron core structures when the one-phase open fault occurs without a ground fault of the transformer connected to the offsite power supply system, including when the offsite power supply side is a wye connection and the load side is a delta connection etc. The report of the INSS JOURNAL 2013 used simulation by the electro-magnetic transients program (EMTP) and obtained findings that clearly specified the response at the time of the power supply side one-phase open without ground fault of various winding structures and various iron core structures of the three-phase transformer and identified the important issues for the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the one-phase open fault occurred without ground fault. In a continuation of the previous report, this paper summarizes the previous results, and then presents the principles by which normal voltages are maintained by both the primary and the secondary sides when the one-phase open failure without ground fault occurs on the primary side of the transformer, and the results of the analysis of operations of the protection relays of the emergency power systems and the safety related components of representative a domestic PWR plant by the simulation using EMTP. (author)

  18. Nuclear refinery - advanced energy complex for electricity generation, clean fuel production, and heat supply

    International Nuclear Information System (INIS)

    McDonald, C.F.

    1992-01-01

    In planning for increased U.S. energy users' demand after the year 2000 there are essentially four salient vectors: (1) reduced reliance on imported crude oil; (2) provide a secure supply with stable economics; (3) supply system must be in concert with improved environment goals; and (4) maximum use to be made of indigenous resources. For the last decade of this century the aforementioned will likely be met by increasing utilization of natural gas. Early in the next century, however, in the U.S. and the newly industrializing nations, the ever increasing energy demand will only be met by the combined use of uranium and coal. The proposed nuclear refinery concept is an advanced energy complex that has at its focal point an advanced modular helium reactor (MHR). This nuclear facility, together with a coal feedstock, could contribute towards meeting the needs of the four major energy sectors in the U.S., namely electricity, transportation, industrial heating and chemical feedstock, and space and water heating. Such a nuclear/coal synergistic system would be in concert with improved air quality goals. This paper discusses the major features and multifaceted operation of a nuclear refinery concept, and identifies the enabling technologies needed for such an energy complex to become a reality early in the 21st century. (Author)

  19. The structure of an expert system to diagnose and supply a corrective procedure for nuclear power plant malfunctions

    International Nuclear Information System (INIS)

    Hajek, B.K.; Stasenko, J.E.; Hashemi, S.; Bhatnagar, R.; Yamada, N.; Punch, W.F. III.

    1987-01-01

    Two prototype knowledge based systems have been developed at the Ohio State University. These systems were the result of collaboration between the Nuclear Engineering Program and the Laboratory for Artificial Intelligence Research (LAIR). The first system uses hierarchical classification to diagnose malfunctions of the coolant system in a General Electric Boiling Water Reactor (BWR). The second system provides a plan of action, through a process of dynamic procedure synthesis, to stabilize the plant once an abnormal transient has occurred. The objective of this paper is to discuss a structure that will integrate the two systems. The combined system will be capable of informing plant personnel about the nature of malfunctions, and of supplying to the operator the most direct corrective procedure available. Two important features of the integrated system are faulty sensor detection, based on malfunction context and unlike sensor data, and procedure synthesis based on the initial state of the plant

  20. INIS-International nuclear information system

    International Nuclear Information System (INIS)

    Marinkovic, N.

    1997-01-01

    INIS is the worlds leading decentralized information system on the peaceful uses of nuclear energy. It is operated by the International Atomic Energy Agency in co-operation with the member states and international organisations. Being one of the INIS member states, our country has began co-operation with INIS in 1975. INIS National Centre is acting within the Institute of Nuclear Sciences and according to the strictly defined organisation of the information system supplies the users with the available INIS products, meaning bibliographic data from the INIS data base. At the same time it is responsible for submitting information concerning domestic publications to the INIS Secretariat, including supplying foreign users with non-conventional literature if demanded. During the period 1990 - 1996 co-operation with INIS Secretariat was interrupted due to reasons which are not subject of this paper. Since then collaboration is established again, and updated INIS data base on CD-ROM is available at the National Centre. INIS on-line retrieval is not yet available

  1. Prospects of uranium supply-demand situation in world nuclear power development

    International Nuclear Information System (INIS)

    Chen Zuyi; Wang Xingwu

    2010-01-01

    Based on the newest materials and data published by authoritative organizations, this paper introduces the near-term and medium to long-term development situation of world nuclear power, summarizes the main characteristics of recent world uranium production, preliminarily analyses the relationship between uranium supply and demand to 2030. It is suggested that from the view-point of whole world, uranium resources are fully sufficient for the near-term and medium to long-term world uranium production and uranium demand of nuclear power. World uranium production can meet the near-term uranium demand for nuclear power. However, a big supply-demand gap may exist after 2015 as world nuclear power will be developed with high speed. In case if all const ruction plans of new uranium mines and production- expansion plans of existing uranium mines will be completed on time, it is quite possible for the world uranium production to meet the long-term uranium demand of nuclear power development. (authors)

  2. The international trade of nuclear power plants: the supply side - 5006

    International Nuclear Information System (INIS)

    Leveque, F.

    2015-01-01

    The international trade of nuclear power plants is usually studied from a demand perspective. Which new countries are willing to access to this technology? How the Fukushima Daiichi catastrophe has changed the market forecasts? What risks of proliferation new entrants entail? This paper takes an opposite direction. It looks at the structure and the organising of the supply side. Which countries are the major exporters? How their ranking has changed? Is the nuclear export industry becoming a global industry? Part 1 provides a short description of the worldwide market. Surprisingly, its size is modest and the US only plays a minor role. This part also provides a view on the relationship between domestic and export markets. Part 2 discusses the industrial organization of the nuclear industry. It compares the nuclear industry with the armament industry and the oil and gas supplies and services. Part 3 concludes in analysing the conditions nuclear industry could become a global industry. (author)

  3. Long-term outlook of energy demand and supply in Japan. Estimation of energy demand and supply for 'Nuclear Energy Vision 2100' of JAEA

    International Nuclear Information System (INIS)

    Tatematsu, Kenji; Kawasaki, Hirotsugu; Nemoto, Masahiro; Murakami, Masakazu

    2009-06-01

    In this study, we showed an energy demand and supply scenario toward the year 2100 in Japan, which underlies JAEA's 'Nuclear Energy Vision 2100' published in October 2008. This energy demand and supply scenario aimed at the coexistence of the reduction of the carbon dioxide emission and the energy security through reduction of the fossil fuel usage, positive electrification and the nuclear energy usage. We reduced the ratio of the fossil fuel in the primary energy supply to about 1/3 and extend the share of renewable and nuclear energy to 70% from current 15%. As a result, the carbon dioxide emission was reduced to current 10%, and it developed that the half was the contribution of the nuclear energy. (author)

  4. Environmental inventories for future electricity supply systems for Switzerland

    International Nuclear Information System (INIS)

    Dones, R.; Gantner, U.; Hirschberg, S.; Doka, G.; Knoepfel, I.

    1996-02-01

    This report provides the analysis of environmental inventories for selected electricity supply systems considered as possible options to meet the expected electricity demand in Switzerland in year 2030. The work was carried out by the Paul Scherrer Institute (PSI) and the Swiss Federal Institute of Technology Zurich (ETHZ), and was supported by the Swiss Association of Producers and Distributers of Electricity (VSE). Two possible electricity demand level cases were postulated by VSE, both under the basic assumption of economic growth: a high-growth demand case corresponding to a yearly increase of 2% from year 1995 to year 2010 and 1% from year 2010 to year 2030, and a low-growth demand case corresponding to a yearly increase of 1% from year 1995 to year 2010 and 0.5% from year 2010 to year 2030. The base (i.e. secured) supply in year 2030 will be, according to VSE, totally dominated by hydro with rather minor contributions from combined heat-and-power plants, small gas turbines, incinerators and solar photovoltaic plants. Due to decommissioning of the currently operating nuclear power plants and expiration of long-term electricity import contracts there will eventually occur a gap between the postulated electricity demand and the base supply. VSE provided seven options to cover this gap, defined in terms of mixes with different contributions from gas, coal, nuclear and solar chains; in this context a distinction is also made with respect to shares of domestic and imported electricity. The systems considered represent advanced technologies, regarded as either typical or most suitable for the Swiss conditions. System-specific input to the present analysis has been partially generated based on direct contacts with the industry. Life Cycle Analysis (LCA) was used to establish environmental inventories for the systems analysed. The analysis has been performed on three levels: 1) individually for each system considered, 2) comparison of systems, 3) comparison of supply

  5. Installation and operation of the Plantwide Fire Protection Systems and related Domestic Water Supply Systems

    International Nuclear Information System (INIS)

    1991-12-01

    A safe work environment is needed to support the Savannah River Site (SRS) mission of producing special nuclear material. This Environmental Assessment (EA) assesses the potential environmental impact(s) of adding to and upgrading the Plantwide Fire Protection System and selected related portions of the Domestic Water Supply System at SRS, Aiken, South Carolina. The following objectives are expected to be met by this action: Prevent undue threat to public health and welfare from fire at SRS; prevent undue hazard to employees at SRS from fire; prevent unacceptable delay to vital DOE programs as a result of fire at SRS; keep fire related property damage at SRS to a manageable level;, and provide an upgraded supply of domestic water for the Reactor Areas. The Reactor Areas' domestic water supplies do not meet current demand capacity due to the age and condition of the 30-year old iron piping. In addition, the water quality for these supplies is not consistent with current SCDHEC requirements. Therefore, DOE proposes to upgrade this Domestic Water Supply System to meet current demand and quality levels, as well as the needs of fire protection system improvement

  6. Economic principles of optimizing mixed nuclear and non-nuclear electricity systems

    International Nuclear Information System (INIS)

    Gouni, L.

    1984-01-01

    In this chapter, an attempt will be made to show how and why, viewed from the economic angle, nuclear energy and electricity systems supplement each other, since the former requires large size facilities, and the latter provide already existing networks for the supply of all users. Consequently, it is primarily through the electric vector that the rational development of the nuclear industry may be ensured. Section 2.1 sets forth the essential rules for economic calculation. In Section 2.2 we discuss the competitive factors among final-use forms of energy in regard to utilization, and we attempt to show how nuclear energy transmitted through electricity systems may meet such terms. Finally, Section 2.3 deals with, and specifies the characteristics of, electricity systems based on nuclear energy and, in particular, the rates to which they lead. (author)

  7. The best-mix of power demand and supply. Energy system integration

    International Nuclear Information System (INIS)

    Ogimoto, Kazuhiko

    2012-01-01

    In September 2012 after nationwide discussions, Energy and Environmental Council decided 'Innovative Strategy for Energy and the Environment': (1) Realization of a society not dependent on nuclear power, (2) Realization of green energy revolution, (3) For ensuring stable supply of energy, (4) Bold implementation of reform of electricity power systems and (5) Steady implementation of global warming countermeasures. Energy problem should be considered as supply and demand of whole energy. However, long-term energy problem such as in 2050 should assume global limits of fossil fuel supply and carbon dioxide emission and then in order to realize sustainable demand and supply of energy, maximum deployment of renewable energy power in primary energy and most practicable electrification of final demand for energy conservation should be implemented. Best mix of power and energy demand and supply would be significant to some extent. This article outlined analysis of power demand and supply in a long term, future power technologies and demand side management, and problems of power system operation and their solution, and then described energy system integration to realize power and energy/society best mix. (T. Tanaka)

  8. Nuclear energy: one of the possibilities for the diversification of energy supplies

    International Nuclear Information System (INIS)

    Pecqueur, Michel

    1982-01-01

    The example of the nuclear energy development in France and in Japan demonstrates that nuclear energy has a fundamental role to play in a balanced policy of diversification of energy supply. The French nuclear programme and the fuel cycle are more particularly detailed [fr

  9. C-E Nuclear Power Businesses Quality Management of Manufacturing and Design and its impact on Reliability of C-E Supplied Components

    Energy Technology Data Exchange (ETDEWEB)

    Mawhinney, D. [Combustion Engineering, Inc., Windsor (United States)

    1989-04-15

    To attain and sustain this objective, Nuclear Power Businesses has established a quality system for design and manufacturing of Nuclear Steam Supply System components, nuclear fuel and operating plant systems and services. Today's quality system has been designed, developed and refined over the past forty (40) years. This system is a dynamic one, based on solid quality principles, accepted industry standards and practices, complies with the ASME Code and 10 CFRP 50, Appendix B, but within the bounds of mandated requirements is adaptable to unique client needs. Nuclear Power Businesses is successfully implementing its quality philosophy through management and organizational commitment, strong leadership, teamwork and use of modern quality techniques. The quality system at C-E Nuclear Power Businesses has been developed in response to changing requirements over the past forty years. It is still changing today. The effectiveness of the system is evidenced by the superior performance of C-E Nuclear Power Businesses supplied Ness's. The system includes management involvement and awareness involvement and awareness and ensures that all employees are aware of Nuclear Power Businesses' quality goals. The system has a strong quality organization that establishes uniform policies and assures compliance. In addition, the system promotes open communication and prompt, permanent corrective action. Although we believe our system, as they exist today, meet or exceed client requirements, they are continuously reviewed and adjusted to improve their usefulness to make them more cost effective.

  10. C-E Nuclear Power Businesses Quality Management of Manufacturing and Design and its impact on Reliability of C-E Supplied Components

    International Nuclear Information System (INIS)

    Mawhinney, D.

    1989-01-01

    To attain and sustain this objective, Nuclear Power Businesses has established a quality system for design and manufacturing of Nuclear Steam Supply System components, nuclear fuel and operating plant systems and services. Today's quality system has been designed, developed and refined over the past forty (40) years. This system is a dynamic one, based on solid quality principles, accepted industry standards and practices, complies with the ASME Code and 10 CFRP 50, Appendix B, but within the bounds of mandated requirements is adaptable to unique client needs. Nuclear Power Businesses is successfully implementing its quality philosophy through management and organizational commitment, strong leadership, teamwork and use of modern quality techniques. The quality system at C-E Nuclear Power Businesses has been developed in response to changing requirements over the past forty years. It is still changing today. The effectiveness of the system is evidenced by the superior performance of C-E Nuclear Power Businesses supplied Ness's. The system includes management involvement and awareness involvement and awareness and ensures that all employees are aware of Nuclear Power Businesses' quality goals. The system has a strong quality organization that establishes uniform policies and assures compliance. In addition, the system promotes open communication and prompt, permanent corrective action. Although we believe our system, as they exist today, meet or exceed client requirements, they are continuously reviewed and adjusted to improve their usefulness to make them more cost effective

  11. Application of expert system to nuclear power plant operation and guidance system

    International Nuclear Information System (INIS)

    Goto, M.; Takada, Y.

    1990-01-01

    For a nuclear power plant, it is important that an expert system supplies useful information to the operator to meet the increasing demand for high-level plant operation. It is difficult to build a user-friendly expert system that supplies useful information in real time using existing general-purpose expert system shells. Therefore a domain-specific expert system shell with a useful knowledge representation for problem-solving in nuclear power plant operation was selected. The Plant Table (P/T) representation format was developed for description of a production system for nuclear power plant operation knowledge. The P/T consists of plant condition representation designed to process multiple inputs and single output. A large number of operation inputs for several plant conditions are divided into 'timing conditions', 'preconditions' and 'completion conditions' to facilitate knowledge-base build-up. An expert system for a Nuclear Power Plant Operation and Guidance System utilizing the P/T was developed to assist automatic plant operation and surveillance test operation. In these systems, automatic plant operation signals to the plant equipment and operation guidance messages to the operators are both output based on the processing and assessment of plant operation conditions by the P/T. A surveillance test procedure guide for major safety-related systems, such as those for emergency core cooling systems, is displayed on a CRT (Cathode Ray Tube) and test results are printed out. The expert system for a Nuclear Power Plant Operation and Guidance System has already been successfully applied to Japanese BWR plants

  12. Comparative study for endenergy supply with nuclear district heating and with nuclear long distance energy

    International Nuclear Information System (INIS)

    Dietrich, G.

    1975-07-01

    The future energy supply of the Federal Republic of Germany will be orientated to secure energy carriers. Moreover economical energy consumption and environmental protection will be a force for an increased application of district heating and nuclear long distance energy. The technics of generation, transport and distribution of the two energy carriers will be discussed, besides a short review of application areas and potentials. The cost comparisons by models show that there are special advantages for both systems. Nevertheless the conclusions from the study can be to favour nuclear long distance energy because of its wide application range in the whole heat market. But there is also the competition with combined heat and power generation on fossil basis, as practised in many industrial companies. As a result of a regional analysis of the area Aachen-Moenchengladbach-Koeln, the cost advantages of the nuclear long distance energy as a parameter of current prices are confirmed. Nuclear long distance energy, in combination with the high temperature reactor and a developed technic of catalysts up to temperatures of 900 K, is an energy source which will be independant of regional necessities, secure, non pollutant and economic. (orig.) [de

  13. Supplier quality assurance systems: a study in the nuclear industry

    International Nuclear Information System (INIS)

    Singer, A.J.; Churchill, G.F.; Dale, B.G.

    1988-01-01

    The results are reported of a study which investigated the impact of quality assurance on 13 suppliers to the nuclear industry. The purpose of the study was to determine the benefits and problems of applying quality assurance in the supply of high risk plant items and material for nuclear installations. The paper discusses the problems facing the industry including: multiple audits and inspections, the irritation with having to contend with two quality system standards (namely BS 5750 and BS 5882) and the cost effectiveness of the more stringent quality system and quality control surveillance requirements imposed by the nuclear industry. It is also pointed out that companies supplying non-nuclear industrial customers were dissatisfied with the qualifications, experience and professional competence of some auditors and many inspectors. (author)

  14. Systems integration processes for space nuclear electric propulsion systems

    International Nuclear Information System (INIS)

    Olsen, C.S.; Rice, J.W.; Stanley, M.L.

    1991-01-01

    The various components and subsystems that comprise a nuclear electric propulsion system should be developed and integrated so that each functions ideally and so that each is properly integrated with the other components and subsystems in the optimum way. This paper discusses how processes similar to those used in the development and intergration of the subsystems that comprise the Multimegawatt Space Nuclear Power System concepts can be and are being efficiently and effectively utilized for these purposes. The processes discussed include the development of functional and operational requirements at the system and subsystem level; the assessment of individual nuclear power supply and thruster concepts and their associated technologies; the conduct of systems integration efforts including the evaluation of the mission benefits for each system; the identification and resolution of concepts development, technology development, and systems integration feasibility issues; subsystem, system, and technology development and integration; and ground and flight subsystem and integrated system testing

  15. The renewable and nuclear energies in the basquet of energy supply

    International Nuclear Information System (INIS)

    Martinez Corcoles, F.

    2008-01-01

    The share of nuclear and renewable sources in the energy portfolio yields great benefits to all stake holders and that both sources are not exclusive each other but offer multiple complementary features and synergy's, therefore both technologies should be part of the present and future energy mix. This portfolio should be enough and reliable all the time, guarantee the security of supply, protect the environment and give competitive prices. All these features are to a great extent met by nuclear and renewable technologies and therefore they should play an important role on world and national energy supply. (Author)

  16. An approach to a self-consistent nuclear energy system

    International Nuclear Information System (INIS)

    Fujii-e, Yoichi; Arie, Kazuo; Endo, Hiroshi

    1992-01-01

    A nuclear energy system should provide a stable supply of energy without endangering the environment or humans. If there is fear about exhausting world energy resources, accumulating radionuclides, and nuclear reactor safety, tension is created in human society. Nuclear energy systems of the future should be able to eliminate fear from people's minds. In other words, the whole system, including the nuclear fuel cycle, should be self-consistent. This is the ultimate goal of nuclear energy. If it can be realized, public acceptance of nuclear energy will increase significantly. In a self-consistent nuclear energy system, misunderstandings between experts on nuclear energy and the public should be minimized. The way to achieve this goal is to explain using simple logic. This paper proposes specific targets for self-consistent nuclear energy systems and shows that the fast breeder reactor (FBR) lies on the route to attaining the final goal

  17. Investigation of occurrences of loss of external power supply in Spanish nuclear power plants

    International Nuclear Information System (INIS)

    Conde, J.M.; Reig, J.

    1989-01-01

    The paper reports on an investigation undertaken by the Nuclear Safety Council into occurrences of loss of external power supply in Spanish light water plants between 1981 and 1987. During this period all of the plants investigated (nine), with the exception of one, experienced an event of this type. The causes, effects and duration of each are studied in detail and the conclusion is drawn that the main cause of this type of occurrence is the intrinsic instability of the Spanish national grid. The response of plants to these various failures in external power supply was studied, special attention being paid to the correct operation of safety systems. In addition, the behaviour of other systems not related to safety is discussed, as are modifications and actions taken as a result of accumulated experience with a view to improving the plant response in the event of the failure of the external power supply, and reducing the frequency of such occurrences and their effective duration. The data obtained from this analysis were compared with those obtained in studies performed in other countries and the conclusion was drawn that failures in the external power supply occur slightly more frequently in Spain than in other countries. Similarly, a comparison was drawn between plant response during an actual failure and the response obtained during loss of external power nuclear tests which are carried out in all Spanish plants during the startup (commissioning) programme, in order to ascertain whether the test itself is adequate. (author). 1 fig., 3 tabs

  18. Nuclear power and sustainable energy supply for Europe

    International Nuclear Information System (INIS)

    Hilden, W.

    2006-01-01

    Developing and promoting a farsighted energy policy is a key aspect in achieving sustainable development in the European Union. Factors to be coped with in this context are the Union's increasing dependence on energy imports, and the threats facing the climate. Moreover, it is imperative that the Lisbon strategy be pursued, according to which Europe is to be made the world's most dynamic knowledge-based economic region by 2010. As early as in 2000, the EU Commission published its Green Paper, ''Towards a European Strategy of Continuity in Power Supply.'' Continuity of supply, in this context, not only stands for maximized self-sufficiency or minimized dependencies. What is at stake is a reduction of the risks stemming from dependence on imports and from changes in the environment. This goal can be achieved through a balanced and diverse structure both of energy resources and of the geographic origins of fuels. The right energy mix is decisive. The European Commission feels that nuclear power can make an important contribution towards sustainable energy supply in Europe. Nuclear power should keep its place in the European energy mix. One important aspect in this regard is improved public acceptance through communication, transparency, and confidence building. High safety standards and a credible approach to the safe long-term management of radioactive waste are major components of this sustainable energy source. (orig.)

  19. Location sites for nuclear power plants and the public drinking water supplies

    International Nuclear Information System (INIS)

    1987-05-01

    This report presents the results of a study by the Dutch RIWA- Working Group Nuclear Power Plants, of the possible effects of a nuclear-reactor melt-down accident upon the drinking-water supply in the Netherlands which is dependent on surface waters. The aim of this report is to contribute to the 're-consideration with regard to siting of nuclear power plants' of the Dutch government. In the case of a nuclear-reactor melt-down accident in the Netherlands or directly adjacent countries, surface waters destined for drinking-water production may be contaminated severely. The amount of contamination depends, among other things, upon the distance, wind direction, dry as well as wet deposition and the features of the place yielding drinking water. From calculations of contamination of surface waters in the case of open- supply build up it appears that the derived norm of the radionuclide cocktail may be exceeded for a period of weeks up to several months or even years. There are reasons to draw the same conclusion for supply build up in the dunes by means of surface infiltration in the dunes. A melt-down accident can cause very severe contamination. Also here it can be stated that, in the case of a calamity in the Netherlands or directly adjacent countries, a norm transgression may occur for weeks up to years. In view of the risks which nuclear power plants can hold for the drinking-water supply which depends upon surface-waters as basis element. Severe objections should be made with respect to the siting of nuclear power plants in the Netherlands unless the occurrence of melt-down accidents could be excluded. 11 refs.; 4 figs.; 7 tabs

  20. Reliability analysis with the simulator S.ESCAF of a very complex sequential system: the electrical power supply system of a nuclear reactor

    International Nuclear Information System (INIS)

    Blot, M.

    1987-06-01

    The reliability analysis of complex sequential systems, in which the order of arrival of the events must be taken into account, can be very difficult, because the use of the classical modelling technique of Markov diagrams leads to an important limitation on the number of components which can be handled. The desk-top apparatus S.ESCAF, which electronically simulates very closely the behaviour of the system being studied, and is very easy to use, even by a non specialist in electronics, allows one to avoid these inconveniences and to enlarge considerably the analysis possibilities. This paper shows the application of the S.ESCAF method to the electrical power supply system of a nuclear reactor. This system requires the simulation of more than forty components with about sixty events such as failure, repair and refusal to start. A comparison of times necessary to perform the analysis by these means and by other methods is described, and the advantages of S.ESCAF are presented

  1. Quick discharge circuit for pacer nuclear power supply

    International Nuclear Information System (INIS)

    Chen, C.Y.

    1975-01-01

    A quick discharge circuit for a pacer's nuclear power supply is described. A pacer capable of implantation within the body of a patient and capable of being powered by at least one nuclear battery is disclosed. Voltage from a single nuclear battery is increased by a factor of about 25 to 30 in order to provide a voltage level adequate to power pacer circuitry. A restartable DC--DC converter is used for this purpose. But if the converter malfunctions the load voltage must be reduced below a certain level for the converter to be automatically restarted. The present invention relates to means for reducing the time from converter malfunction to resumption of converter operation in order to reduce the corresponding inoperative pacer time period. (U.S.)

  2. Future development of nuclear energy systems

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    Nuclear energy development in Japan has passed about 30 years, and reaches to a step to supply about 35 % of total electric power demand. However, together with globalization of economic and technical development, its future progressing method is required for its new efforts. Among such conditions, when considering a state of future type nuclear energy application, its contribution to further environmental conservation and international cooperation is essential, and it is required for adoption to such requirement how it is made an energy source with excellent economics.The Research Committee on 'Engineering Design on Nuclear Energy Systems' established under recognition in 1998 has been carried out some discussions on present and future status of nuclear energy development. And so forth under participation of outer specialists. Here were summarized on two year's committee actions containing them and viewpoints of nuclear industries, popularization of nuclear system technology, and so forth. (G.K.)

  3. Startup of Pumping Units in Process Water Supplies with Cooling Towers at Thermal and Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Berlin, V. V., E-mail: vberlin@rinet.ru; Murav’ev, O. A., E-mail: muraviov1954@mail.ru; Golubev, A. V., E-mail: electronik@inbox.ru [National Research University “Moscow State University of Civil Engineering,” (Russian Federation)

    2017-03-15

    Aspects of the startup of pumping units in the cooling and process water supply systems for thermal and nuclear power plants with cooling towers, the startup stages, and the limits imposed on the extreme parameters during transients are discussed.

  4. Nuclear proliferation and civilian nuclear power: report of the nonproliferation alternative systems assessment program. Volume V. Economics and systems analysis

    International Nuclear Information System (INIS)

    1979-12-01

    This NASAP assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improving the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness. The objectives of this assessment are to identify when economic incentives to deploy advanced nuclear power systems might exist, to estimate the costs of using technologies that would reduce the risk of proliferation, to assess the impact of major economic uncertainties on the transition to new technologies, and to compare the investments required for alternative systems

  5. Nuclear applications for steam and hot water supply

    International Nuclear Information System (INIS)

    1991-07-01

    An increase in the heat energy needs underlined by the potential increase in fossil fuel prices, particularly in oil supplies, and by the necessity for an improvement of the environment worldwide, as signalized by the IAEA Member States, prompted the decision to start a programme leading to this report. This document is intended to help to identify the experience of Member States where nuclear power plants or specialized nuclear heat plants are employed or envisaged to be used for distribution of steam or hot water to industrial or residential consumers, covering low and medium temperature ranges. 25 refs, 33 figs, 15 tabs

  6. The role and position of nuclear energy in the long-term energy supply of China

    International Nuclear Information System (INIS)

    Bao Yunqiao

    1992-03-01

    The history for development of world nuclear energy and policies in various countries are retrospected, and the development of world nuclear energy is reviewed. On the basis of analysis for the economy of nuclear power in abroad, it is verified that the cost of nuclear power is cheaper than that of coal-fired power. In the future, the nuclear power is still competitive in economy. The prospect for long-term energy supply in China is predicted on the present situation of energy industry. It is estimated that the gap between energy demands and supply will become larger and larger. The solution is to develop nuclear energy in south-east area. The long-term demands of electricity and electrical resources are estimated in China, and if nuclear energy is utilized, it will optimize the constitution of electricity. The economy of nuclear power is also evaluated. It is expected that the nuclear power will be cheaper than that of coal-fired power in China after equipment are made domestically and serially. From the analysis of the conditions of communication, transportation and pollution, the development of nuclear energy will reduce the tension of transportation and improve the environmental quality. Finally, the prospect of developing nuclear heating and the supply level of uranium resources in China are analyzed

  7. ECONOMIC PRINCIPLES FOR SELECTION OF OPTIMUM POWER-SUPPLY SYSTEM DEVELOPMENT IN BELARUS

    Directory of Open Access Journals (Sweden)

    L. P. Padalko

    2008-01-01

    Full Text Available The paper considers main directions of the technological development of the Belarusian power-supply system. Comparative analysis of the economic efficiency of thermal power station modernization on the basis of steam- and gas technology, nuclear technology development and simple renovation of the worn-out generating capacities of thermal power stations has been carried out in the paper. Selection of the priority direction pertaining to optimization of industrial structure of the Belarusian power-supply system has been made on the basis of the presented minimum-specific cost criterion. The paper reveals that in the medium-term period the most optimum development of the Belarusian electrical power engineering is a technological  modernization  due to predicted  changes in natural gas and nuclear fuel costs. The modernization presupposes construction of topping plants in addition to the existing steam- and turbine equipment at thermal power stations. 

  8. Present state of the perception gap of nuclear energy between Japanese nuclear energy supplying region and an energy consuming region

    International Nuclear Information System (INIS)

    Ohnishi, Teruaki

    2002-01-01

    Public opinion surveys have been carried out since 1998 on what phase and on what extent of the perception of nuclear energy differs between Japanese dwelling in energy supplying region and an energy-consuming region. Southern Fukui rural district where 15 nuclear reactors are now installed and Osaka urban region of about 100 km apart from Fukui were selected as the respective targets for the energy supplying and consuming regions. Analyses of the data of about 3000 samples have revealed the followings. (1) The public in the nuclear energy supplying region are very friendly to nuclear energy so that only about 20 and 39 of the public are resistive to the general promotion of nuclear energy in Japan and to the construction of another nuclear reactor in their dwelling region, respectively. (2) On the other hand, in the energy-consuming region those respective fractions are 41 and 70 implying strong resistance to nuclear energy in the urban region. (3) Both the degree of interest in and the degree of knowledge on nuclear energy are very low, whereas the extent of fear to nuclear is high for the urban public. (4) Not only the fraction of the public who are satisfied with their present life, but the public fraction who is eagerly support the thought of return-to-nature are very high in the urban region. (5) On the other hand, in the energy supplying region, many peoples eagerly want their life to become more convenient than it is now, and 6) all those trends (I)-(5) are revealed more pronouncedly in the woman than the man. The perception gap of nuclear energy thus became clear between Japanese dwelling in rural and urban regions. On the basis of this knowledge, discussions on the nature of the so-called NIMBY will be made from the socio-psychological viewpoint and propositions will also be made on the methods to dissolve the perception gap of that soft. (author)

  9. Nuclear Option for a Secure and Sustainable Energy Supply

    International Nuclear Information System (INIS)

    Kolundzija, V.; Mesarovic, M.

    2002-01-01

    Present energy policy is required to ensure a balance between security of supply, competitiveness and environmental requirements. Recent changes involved by deregulation and liberalization of electricity and natural gas markets even strengthen such a policy. However, dependency on external energy sources carries risks that have to be managed since a large proportion of both oil and gas reserves are found in politically unstable regions. Electrical energy is a fundamental prerequisite for a civilized life and an essential commodity, but it cannot be stored and this restricts the extent to which there can be a real free market for electricity. Therefore, relying on imports of electricity to a large extent may prove unsecure because this requires a true, completely open market in which the opportunities for cross-border trade are effective and balanced and transport connections are adequate. This is equally applied to the countries in the South-Eastern Europe, despite very good prospects for development of the regional electricity market there. In this regard, the use of nuclear energy has not any risk associated with external dependency because there are abundant quantities of uranium available world-wide from many diverse sources. The inherent mitigation of supply risk associated with the use of uranium should act as an incentive to the further use of nuclear energy. In addition, already very large stocks of fuel assemblies and fuel-making materials available, especially when these are measured in terms of power generating capacity per year at current production rates. It is, therefore, very important for any country to recognize such strategic aspect of nuclear energy when addressing the issue of security of power supply. Nuclear option is in a unique position to restore its original role of the main source of energy with an increased attention paid to the security of electricity supply as well as regulatory changes affecting fossil fuels, particularly with due

  10. Total energy supply-system for manned spaceship using nuclear reactor

    International Nuclear Information System (INIS)

    Narabayashi, Tadashi; Honma, Yuji; Yoshida, Yutaka; Shimazu, Yoichiro

    2007-01-01

    In order to explore the deep space, such as Mars, Jupiter, Saturn, etc in the future, a spacecraft that will be driven by nuclear power should be developed. At present, satellites or space probes have been using mainly electric source of chemical battery, fuel battery, solar battery, and RI battery. However, considering highly developed and extensive space exploration in the future, it is obvious that larger electric power is required over the long term space travel more than several years. Additionally, the solar battery used in space will be fundamentally impossible to use in planetary exploration father away form Mars because sunlight is attenuated. Therefore, larger electric power source must be installed in the space craft. In this study, we consider about co-generation system for heat and electricity using nuclear power. We think that the nuclear power is appropriate for using in deep space because of a long time operation without refueling and possibility in downsizing due to higher power density. We selected the fast reactor system of about 18 MWth compared with other type of reactors, such as PWR and high temperature gas reactor (Honma, 2006). With regard to a power generation system, we examined about efficiency of Stirling engine compared with a gas-turbine engine. Theoretical efficiency of Stirling engine is much higher than that of gas-turbine engine. Therefore, we selected Stirling engine and we have started the model test of a Stirling engine. Total power generation at International Space Station (ISS) that has been built since 1998 is about 110kWe. We estimated that about 5 times as much electricity as that of ISS is enough to explore or developed the space. In that case, 2.5MWe will be generated by the system, number of crews will be about 10 and 2MW will be used to electric propulsion. (author)

  11. Nuclear Energy and Renewables interaction: System Effects in Low-carbon Electricity Systems

    International Nuclear Information System (INIS)

    Keppler, Jan Horst; Cometto, Marco

    2013-01-01

    This report presents a synthesis of the OECD/NEA study 'Nuclear Energy and Renewables: System Effects in Low-carbon Electricity Systems'. It addresses the increasingly important interactions of variable renewables and dispatchable energy technologies, such as nuclear power, in terms of their effects on electricity systems. These effects add costs to the production of electricity, which are not usually transparent. The report recommends that decision-makers should take into account such system costs and internalise them according to a 'generator pays' principle, which is currently not the case. Analysing data from six OECD/NEA countries, the study finds that including the system costs of variable renewables at the level of the electricity grid increases the total costs of electricity supply by up to one-third, depending on technology, country and penetration levels. In addition, it concludes that, unless the current market subsidies for renewables are altered, dispatchable technologies will increasingly not be replaced as they reach their end of life and consequently security of supply will suffer. This implies that significant changes in management and cost allocation will be needed to generate the flexibility required for an economically viable coexistence of nuclear energy and renewables in increasingly de-carbonised electricity systems

  12. Nuclear energy and ensuring the long-term energy supply in the German Federal Republic

    International Nuclear Information System (INIS)

    Koenig, H.H.

    1975-01-01

    The author reports on the papers read at the Reactor Conference in 1975. He pays special attention to the development of energy supply from nuclear stations, investigates the motives behind the growing resistance of the public, and shows that the acceptance procedure ensures the construction and operation of safe nuclear power installations. He also discusses the possibilities of improved energy utilisation, the climatic changes in coming generations, the characteristics of supply with nuclear district heating and process heat, as well as the state of building projects with high-temperature reactors and fast breeders. (orig.) [de

  13. Design considerations for micro nuclear reactors to supply power to off-grid mines

    Energy Technology Data Exchange (ETDEWEB)

    Gihm, B.; Cooper, G.; Morettin, D.; De Koning, P., E-mail: bgihm@hatch.ca [Hatch Ltd., Mississauga, Ontario (Canada); Carreau, M. [Hatch Ltd., Montreal, Quebec (Canada); Sarvinis, J. [Hatch Ltd., Mississauga, Ontario (Canada)

    2014-07-01

    Nuclear technology vendors have been proposing to develop small scale nuclear reactors to supply power and heat to remote industrial operations such as a mining site. Based on extensive experience in integrating different power generation technologies with captive mining power systems, Hatch examined the technical requirements of small scale nuclear reactor application in remote mine power generation. Mining power systems have unique characteristics and challenges that set them apart from utility grid connected power systems. Key examples of such unique characteristics are: A small number of large motor loads such as hoists, pumps, shovels, pumps and crushers represent a large fraction of the peak load. These equipment may cause significant load fluctuations and put the power systems under high stress; There is no organic demand growth (i.e., the load growth occurs as a step increase); and, The extreme environmental conditions and remoteness of the sites introduce a set of operational challenges and require specialized planning. This paper presents real remote mine operation data to demonstrate the load profile of remote mining sites. The operation characteristics and performance requirements of diesel reciprocating engines are discussed, which have to be matched or exceeded by a small scale nuclear power plant if it is to be a viable technical alternative to diesel power. The power quality control options from wind power integration in isolated grids are discussed as a parallel can be drawn between wind and nuclear power application in remote mine power systems. Finally the authors provided a list of technical constraints and design considerations for very small modular reactor development. (author)

  14. Design considerations for micro nuclear reactors to supply power to off-grid mines

    International Nuclear Information System (INIS)

    Gihm, B.; Cooper, G.; Morettin, D.; De Koning, P.; Carreau, M.; Sarvinis, J.

    2014-01-01

    Nuclear technology vendors have been proposing to develop small scale nuclear reactors to supply power and heat to remote industrial operations such as a mining site. Based on extensive experience in integrating different power generation technologies with captive mining power systems, Hatch examined the technical requirements of small scale nuclear reactor application in remote mine power generation. Mining power systems have unique characteristics and challenges that set them apart from utility grid connected power systems. Key examples of such unique characteristics are: A small number of large motor loads such as hoists, pumps, shovels, pumps and crushers represent a large fraction of the peak load. These equipment may cause significant load fluctuations and put the power systems under high stress; There is no organic demand growth (i.e., the load growth occurs as a step increase); and, The extreme environmental conditions and remoteness of the sites introduce a set of operational challenges and require specialized planning. This paper presents real remote mine operation data to demonstrate the load profile of remote mining sites. The operation characteristics and performance requirements of diesel reciprocating engines are discussed, which have to be matched or exceeded by a small scale nuclear power plant if it is to be a viable technical alternative to diesel power. The power quality control options from wind power integration in isolated grids are discussed as a parallel can be drawn between wind and nuclear power application in remote mine power systems. Finally the authors provided a list of technical constraints and design considerations for very small modular reactor development. (author)

  15. World's trend of national nuclear power policy and long-term perspective of nuclear power and supply and demand of uranium fuels

    International Nuclear Information System (INIS)

    Matsuo, Yuji; Nishida, Naoki; Yamaguchi, Yuji; Shimogoori, Kei; Murakami, Tomoko

    2013-01-01

    Based on perspective of nuclear power reflecting latest trend of national nuclear policy, supply and demand of uranium resources until 2035 was evaluated based on latest data. After the Fukushima nuclear accident, Germany and Italy dramatically changed nuclear power to phase out, while United States, Russia, France and Korea as well as China and India continued to promote nuclear power with no essential change of policy. Thus world's nuclear power capacity was foreseen to expand from 389 GW (2010) to 471 GW (2035, low growth case) and 760 GW (2035, high growth case). Following sharp increase of uranium cost after 2005, investment on natural uranium development became active and new operation start of uranium enrichment plants was anticipated in US and Europe, and then both supply and demand of natural uranium and uranium enrichment service would tend to relax until around 2020 and until 2035 extreme tightness of supply and demand might not occur even for high growth case. Uranium demand of Asian region including China and India would be largely expanded with natural uranium from Africa and Australia and uranium enrichment services from US, and Asian high overseas dependence would be continued. (T. Tanaka)

  16. World energy supply and demand and the future of nuclear power

    International Nuclear Information System (INIS)

    Lantzke, U.

    1977-01-01

    The OECD's world energy outlook analyses projected trends in energy damnd and supply for the OECD area and other major global regions to 1985. It provides a brief discussion of trends after 1985. OECD energy consumption is projected to grow more slowly than in the past. Conservation effects will increase efficiency of energy use per unit of economic growth. All domestic energy supplies in the OECD are projected to expand faster than in the past. The relative share of non-fossil energy sources in total production will be almost doubled. Assuming moderate economic growth, existing energy policies and a constnat real price for oil, the outlook's reference case projects OECD oil import at 35 million barrels a day by 1985. This level of import demand, when combined with the import needs of other oil importing areas, could approach the limit of availability of world oil supplies and as a result cause severe disequilibrium in world energy markets. The outlook indicates such severe disruption can be avoided by action to improve the world energy supply and demand balance without impeding economic growth objectives. Strong measures will be required both to conserve energy and to develop new energy supplies. The biggest increment to the OECD's energy supply by 1985 is expected to come from nuclear power. This substantial nuclear contribution will be inevitable and irreplaceable. As a result urgent solutions to problems concerning safety, availability of fuel cycle services, the environment, cost escalation and construction delays will be required

  17. Assessment of demand for and supply of qualified manpower for the nuclear industry

    International Nuclear Information System (INIS)

    Morelle, J.

    1993-01-01

    The OECD Nuclear Energy Agency recently published a study which presents the results of a pioneering survey of the demand for and the supply of qualified manpower in various sectors of the nuclear industry (including medicine), and in the related areas of regulation and education in 12 OECD countries. The current manpower situation is presented and the future demand is reviewed. Present and future activities of OECD countries to ensure a balance between supply and demand of qualified manpower are discussed

  18. DC systems design and research of Hainan Changjiang nuclear power plant

    International Nuclear Information System (INIS)

    Jiang Qingshui; Wang Yuhan

    2014-01-01

    Hainan Changjiang nuclear power plant is different from the referent power plant, the DC and 220 V AC uninterrupted systems of the nuclear island have been changed since the control system use DCS. It has different design on DC systems, power supply, selectivity of breakers, capacity of equipments and layout. We optimize the design of DC systems at the basement of Fuqing and Fangjiashan project. These are good experiments for the three generation nuclear power project about DC systems design of ACP1000. (authors)

  19. Nuclear plant-aging research on reactor protection systems

    International Nuclear Information System (INIS)

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed

  20. Availability of the electrical supply system of emergency sources of 900-MW pressurized water nuclear power plants

    International Nuclear Information System (INIS)

    Blin, A.

    A study made by CEA and EDF on the time-dependent probability of simultaneous loss of the electrical supply system from emergency sources is reported. Aspects covered include the availability of the electrical supply system in all possible conditions (2 available external sources, 1 available external source...) and the probability for repair after total loss of supply sources

  1. Optimisation of the coupling of nuclear reactors and desalination systems in Morocco

    International Nuclear Information System (INIS)

    Tabet, M.; Htet, A.; Alami, A.M.

    2006-01-01

    This study has been undertaken in the framework of IAEA CRP on 'Optimisation of the Coupling of Nuclear Reactors and Desalination Systems in Morocco'. Two sites have been selected to host nuclear desalination plants, and different combinations with nuclear reactors have been investigated. Other combinations with fossil fuel plants have been examined for comparison. The results obtained showed the competitiveness of nuclear energy, which could be a solution to supply the region that will suffer from water shortage. On the other hand, this study could help the decision makers in the management and planning of water, energy resources and supply. (author)

  2. Reactor units for power supply to the Russian Arctic regions: Priority assessment of nuclear energy sources

    Directory of Open Access Journals (Sweden)

    Mel'nikov N. N.

    2017-03-01

    Full Text Available Under conditions of competitiveness of small nuclear power plants (SNPP and feasibility of their use to supply power to remote and inaccessible regions the competition occurs between nuclear energy sources, which is caused by a wide range of proposals for solving the problem of power supply to different consumers in the decentralized area of the Russian Arctic power complex. The paper suggests a methodological approach for expert assessment of the priority of small power reactor units based on the application of the point system. The priority types of the reactor units have been determined based on evaluation of the unit's conformity to the following criteria: the level of referentiality and readiness degree of reactor units to implementation; duration of the fuel cycle, which largely determines an autonomy level of the nuclear energy source; the possibility of creating a modular block structure of SNPP; the maximum weight of a transported single equipment for the reactor unit; service life of the main equipment. Within the proposed methodological approach the authors have performed a preliminary ranking of the reactor units according to various criteria, which allows quantitatively determining relative difference and priority of the small nuclear power plants projects aimed at energy supply to the Russian Arctic. To assess the sensitivity of the ranking results to the parameters of the point system the authors have observed the five-point and ten-point scales under variations of importance (weights of different criteria. The paper presents the results of preliminary ranking, which have allowed distinguishing the following types of the reactor units in order of their priority: ABV-6E (ABV-6M, "Uniterm" and SVBR-10 in the energy range up to 20 MW; RITM-200 (RITM-200M, KLT-40S and SVBR-100 in the energy range above 20 MW.

  3. Ship-Based Nuclear Energy Systems for Accelerating Developing World Socioeconomic Advance

    Science.gov (United States)

    Petroski, Robert; Wood, Lowell

    2014-07-01

    Technological, economic, and policy aspects of supplying energy to newly industrializing and developing countries using ship-deployed nuclear energy systems are described. The approach analyzed comprises nuclear installations of up to gigawatt scale deployed within currently mass-produced large ship hulls which are capable of flexibly supplying energy for electricity, water desalination and district heating-&-cooling with low latencies and minimized shoreside capital expenditures. Nuclear energy is uniquely suited for mobile deployment due to its combination of extraordinary energy density and high power density, which enable enormous supplies of energy to be deployed at extremely low marginal costs. Nuclear installations on ships also confer technological advantages by essentially eliminating risk from earthquakes, tsunamis, and floods; taking advantage of assured access to an effectively unlimited amount of cooling water, and involving minimal onshore preparations and commitments. Instances of floating nuclear power stations that have been proposed in the past, some of which are currently being pursued, have generally been based on conventional LWR technology, moreover without flexibility or completeness of power output options. We consider nuclear technology options for their applicability to the unique opportunities and challenges of a marine environment, with special attention given to low-pressure, high thermal margin systems with continuous and assured afterheat dissipation into the ambient seawater. Such systems appear promising for offering an exceptionally high degree of safety while using a maximally simple set of components. We furthermore consider systems tailored to Developing World contexts, which satisfy societal requirements beyond electrification, e.g., flexible sourcing of potable water and HVAC services, servicing time-varying user requirements, and compatibility with the full spectrum of local renewable energy supplies, specifically including

  4. Impact of operational frequency overvoltage transients on nuclear power plant supply systems

    International Nuclear Information System (INIS)

    Aziz, Michael; Klipfel, Volkher; Behrens, Joerg; Trumm, Karl-Heinz; Bresler, Markus

    2008-01-01

    During the Forsmark-1 event from 25 th July 2006 a regular transient after load shedding caused serious impact to the power supply system due to an improper setting of the UPS protection devices. The applicability of the main security issue to German NPPs could be excluded. Nevertheless the event motivated the launch of a detailed analysis program on overvoltage transients. One main issue within this program was the study of overvoltage transients in the operational frequency range. The program was organized as a common project of the German operators with input from the authorities and the consultants, managed within the VGB (''Vereinigung der Grosskraftwerksbetreiber''). More general information to the ''VGB program'' can be found in [1, 2]. A generic model of the power supply and its protection system, the generator and the turbine turned out to be an efficient analysis approach. In a first step, the possible sources (initiating events) for overvoltage transients are identified. The scenarios resulting from the considered initiating events are evaluated with respect to their potential for causing damage in the station power supply system. In a second step those scenarios are excluded from further consideration, which can be categorized as fully covered by the design basis even under assumption with most conservative boundary conditions. In a third step the remaining scenarios for the covering transient are identified. The boundary conditions and failure postulates are assumed conservatively, but with respect to reasonable probabilistic limits. Finally the dynamics of the covering transient is simulated. (orig.)

  5. Reliability of dc power supplies in nuclear power plant application

    International Nuclear Information System (INIS)

    Eisenhut, D.G.

    1978-01-01

    In June 1977 the reliability of dc power supplies at nuclear power facilities was questioned. It was postulated that a sudden gross failure of the redundant dc power supplies might occur during normal plant operation, and that this could lead to insufficient shutdown cooling of the reactor core. It was further suggested that this potential for insufficient cooling is great enough to warrant consideration of prompt remedies. The work described herein was part of the NRC staff's efforts aimed towards putting the performance of dc power supplies in proper perspective and was mainly directed towards the particular concern raised at that time. While the staff did not attempt to perform a systematic study of overall dc power supply reliability including all possible failure modes for such supplies, the work summarized herein describes how a probabilistic approach was used to supplement our more usual deterministic approach to reactor safety. Our evaluation concluded that the likelihood of dc power supply failures leading to insufficient shutdown cooling of the reactor core is sufficiently small as to not require any immediate action

  6. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  7. Perspectives of electricity supply

    International Nuclear Information System (INIS)

    1988-01-01

    The 7 papers read at the symposium discussed the following subjects: Effects of the CO 2 problems of fossil energy systems on the world climate; status and perspectives of the German electricity industry in terms of competitiveness; The European electricity market and the integrated power supply system; Power supply without nuclear power; Costs and rates for households and other customers; Renewable energy sources and their contribution to energy supply in the Federal Republic of Germany; Electricity utilities as service partners. (UA) [de

  8. Nuclear power and sustainable energy supply for Europe. European Commission

    International Nuclear Information System (INIS)

    Hilden, W.

    2005-01-01

    The right energy mix is decisive. The European Commission feels that nuclear power can make an important contribution towards sustainable energy supply in Europe. Nuclear power should keep its place in the European energy mix. One important aspect in this regard is improved public acceptance through communication, transparency, and confidence building. High safety standards and a credible approach to the safe long-term management of radioactive waste are major components of this sustainable energy source. (orig./GL)

  9. Specific features of power supply based to a large part on nuclear energy

    International Nuclear Information System (INIS)

    Potemans, M.

    1986-01-01

    Belgium is forced to import primary energy so that for quite a long time now nuclear generation is the main source of electricity supply. This trend has been enhanced after the first oil crisis and currently more than 60 p.c. of the country's power supplies are produced from nuclear energy. This has brought about various advantages. The kWh rate has remained on a very competitive level, the balance of payments has been significantly improved, and dependence on imports in the energy sector has been considerably reduced. (orig.) [de

  10. Expert systems use in present and future CANDU nuclear power supply systems

    International Nuclear Information System (INIS)

    Lupton, L.R.; Basso, R.A.J.; Anderson, L.L.; Anderson, J.W.D.

    1989-11-01

    As CANDU nuclear power plants become more complex, and are operated under tighter constraints for longer periods between outages, plant operations staff will have to absorb more information to correctly and rapidly respond to upsets. A development program is underway at Atomic Energy of Canada Limited to use expert systems and interactive media tools to assist operations staff of existing and future CANDU plants. The complete system for plant information access and display, on-line advice and diagnosis, and interactive operating procedures is called the Operator Companion. A prototype, consisting of operator consoles, expert systems and simulation modules in a distributed architecture, is currently being developed to demonstrate the concepts of the Operator Companion. Specialized advisors are also being developed using expert system technology to meet specific operational and design needs

  11. The future energy supply in Germany in a common Europe with special emphasis on the role of nuclear power

    International Nuclear Information System (INIS)

    Kopp, G.

    2003-01-01

    The decision by the red-green federal government to opt out of the use of nuclear power has considerable consequences for the power industry and the national economy of Germany. In addition, there are additional burdens resulting from the Renewable Energies Act and the Cogeneration Act. Besides economic aspects, there are ecological benefits to be considered in favor of nuclear power. In addition to renewable energy sources, it is one of the important sources of energy which are free from CO 2 emissions. In opt-out decision also jeopardizes the role of Germany as a partner in international cooperation, with an acknowledged standard of nuclear know-how and a cutting-edge position in technical safety. The approaches towards a future energy supply system were put into specific terms together with the CDU/CSU within the activities of the parliamentary committee of inquiry on 'sustainable Energy Supply Under Conditions of Globalization and Deregulation'. The growing dependence on external energy sources, and the goals of climate protection, are other important tasks of future energy policy within the European framework. The Green Book by the EU Commission constitutes a remarkable basis for discussion in this respect. Current problems connected with nuclear power should be discussed seriously in order for nuclear power to continue successfully to contribute to energy supply in Europe. (orig.) [de

  12. Supply assurance by versatile energy systems

    International Nuclear Information System (INIS)

    Jaek, W.

    1982-01-01

    The scope of future possibilities of covering the energy requirements of the Federal Republic of Germany has been explained in four sessions handling the topics: structure and covering of the primary energy requirements, contributions of fossil and other energy sources, hydrocarbons and nuclear energy as well as perspectives and political reaction. All energy carriers are required in order to guarantee supply safety, but the industrial nations should make greater use of their know-how and capitals in order to meet short supply of raw material with flexibility. (orig.) [de

  13. Heat supply analysis of steam reforming hydrogen production process in conventional and nuclear

    International Nuclear Information System (INIS)

    Siti Alimah; Djati Hoesen Salimy

    2015-01-01

    Tile analysis of heat energy supply in the production of hydrogen by natural gas steam reforming process has been done. The aim of the study is to compare the energy supply system of conventional and nuclear heat. Methodology used in this study is an assessment of literature and analysis based on the comparisons. The study shows that the heat sources of fossil fuels (natural gas) is able to provide optimum operating conditions of temperature and pressure of 850-900 °C and 2-3 MPa, as well as the heat transfer is dominated by radiation heat transfer, so that the heat flux that can be achieved on the catalyst tube relatively high (50-80 kW/m"2) and provide high thermal efficiency of about 85 %. While in the system with nuclear energy, due to the demands of safety, process operating at less than optimum conditions of temperature and pressure of 800-850 °C and 4.5 MPa, as well as the heat transfer is dominated by convection heat transfer, so that the heat flux that can be achieved catalyst tube is relatively low (1020 kW/m"2) and it provides a low thermal efficiency of about 50 %. Modifications of reformer and heat utilization can increase the heat flux up to 40 kW/m"2 so that the thermal efficiency can reach 78 %. Nevertheless, the application of nuclear energy to hydrogen production with steam reforming process is able to reduce the burning of fossil fuels which has implications for the potential decrease in the rate of CO2 emissions into the environment. (author)

  14. The search of the best mode of the reserve power supply consumption during the nuclear reactor’s emergency shutdown procedures in case of force majeure circumstances

    Science.gov (United States)

    Zagrebaev, A. M.; Trifonenkov, A. V.

    2017-01-01

    This article deals with the problem of the control mode choice for a power supply system in case of force majeure circumstances. It is not known precisely, when a force majeure incident occurs, but the threatened period is given, when the incident is expected. It is supposed, that force majeure circumstances force nuclear reactor shutdown at the moment of threat coming. In this article the power supply system is considered, which consists of a nuclear reactor and a reserve power supply, for example, a hydroelectric pumped storage power station. The reserve power supply has limited capacity and it doesn’t undergo the threatened incident. The problem of the search of the best reserve supply time-distribution in case of force majeure circumstances is stated. The search is performed according to minimization of power loss and damage to the infrastructure. The software has been developed, which performs automatic numerical search of the approximate optimal control modes for the reserve power supply.

  15. A study on determination methods of fueling machine heavy water supply setpressure for Wolsong nuclear power plant unit 1

    International Nuclear Information System (INIS)

    Kim, J. M.; Jeong, B. Y.; Baek, S. J.; Noh, T. S.; Kim, Y. H.; Park, W. K.

    2001-01-01

    The present Wolsong 1 Fuel Handling (F/H)D 2 O Supply Pressure Control System, based on an analog cascaded Proportional-Integral-Differential (PID) control, is less accurate and requires more labor for test and maintenance in comparison with up-to-data digital controllers. Furthermore, F/H operator and technical staff have recently encountered difficulties in operation and maintenance because of frequent occurrences of system instability and failure, and obsolescence of hardware. However the analysis and design review of F/H D 2 O Supply Pressure Control System have not been performed appropriately. Therefore, the design review of F/H D 2 O Supply Pressure Control System has been thoroughly reviewed and analyzed. Based on the analysis results, the optimum pressure setpoints and its determination methods have been proposed for Wolsong Nuclear Power Plant Unit 1

  16. International symposium concluded that uranium supply for nuclear power is secure

    International Nuclear Information System (INIS)

    2000-01-01

    The document informs that stable uranium supply to fuel nuclear power plants will continue to be available according to the conclusion reached at the International Symposium on the Uranium Production Cycle and the Environment held from 2 to 6 October 2000 at the IAEA in Vienna. The meeting included specialists from about 40 countries, in addition to the Arab Atomic Energy Agency, European Commission, OECD/Nuclear Energy Agency (NEA), Office of Supervising Scientist (OSS)/Environment Australia, United Nations, Uranium Institute, World Bank, the World Energy Council and the Nuclear Energy Institute (NEI)

  17. Monitoring support system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashikawa, Yuichi; Kubota, Rhuji; Tanaka, Keiji; Takano, Yoshiyuki

    1996-01-01

    The nuclear power plants in Japan reach to 49 plants and supply 41.19 million kW in their installed capacities, which is equal to about 31% of total electric power generation and has occupied an important situation as a stable energy supplying source. As an aim to keeping safe operation and working rate of the power plants, various monitoring support systems using computer technology, optical information technology and robot technology each advanced rapidly in recent year have been developed to apply to the actual plants for a plant state monitoring system of operators in normal operation. Furthermore, introduction of the emergent support system supposed on accidental formation of abnormal state of the power plants is also investigated. In this paper, as a monitoring system in the recent nuclear power plants, design of control panel of recent central control room, introduction to its actual plant and monitoring support system in development were described in viewpoints of improvement of human interface, upgrade of sensor and signal processing techniques, and promotion of information service technique. And, trend of research and development of portable miniature detector and emergent monitoring support system are also introduced in a viewpoint of labor saving and upgrade of the operating field. (G.K.)

  18. Fuel supply investment cost: coal and nuclear. Commercial electric power cost studies (6)

    International Nuclear Information System (INIS)

    1979-04-01

    This study presents an accounting model for calculating the capital investment requirements for coal and nuclear fuel supply facilities. The study addresses mining, processing, fabrication, and transportation of coal and nuclear fuels. A generic example is provided, for coal from different sources, and for nuclear fuel. The relationship of capital investment requirements to delivered prices is included in each example

  19. Why nuclear geostorage systems for petroleum?

    Energy Technology Data Exchange (ETDEWEB)

    Harst, L van der; Knutson, C F [CER Geonuclear Corporation, Las Vegas, Nevada (United States)

    1970-05-15

    The objective of any kind of storage system in general is to act as a buffer between cyclical changes in supply and demand of the stored commodities. Since the advent of nuclear explosives engineering the possibility of constructing large-scale underground storage systems by means of contained nuclear explosions, for which the name nuclear geostorage has been coined, should be regarded as a valid alternative to the conventional storage systems currently in existence. Limiting this discussion to systems for storing crude oil, various options are available. The choice of any particular storage method depends, of course, on the circumstances surrounding each particular storage requirement; however, in many cases and for a variety of reasons, nuclear geostorage can be preferable to conventional solutions. Economic considerations are clearly among the most important ones. In this respect an increase in storage capacity will tend to favor the nuclear approach. Besides the economics, however, other considerations are important and may in some cases swing the balance in favor of nuclear geostorage plants, for instance: safety and strategic values, aesthetics, ease of access, lack of suitable tank farm space or lack of suitable geologic conditions for natural reservoirs. It should be borne in mind that the decision to use the nuclear approach to solve a storage problem can only be taken after satisfactory evaluation of the geological and geographical characteristics of the site, and when the technical, safety, political, and public relations factors can be handled adequately. (author)

  20. Why nuclear geostorage systems for petroleum?

    International Nuclear Information System (INIS)

    Harst, L. van der; Knutson, C.F.

    1970-01-01

    The objective of any kind of storage system in general is to act as a buffer between cyclical changes in supply and demand of the stored commodities. Since the advent of nuclear explosives engineering the possibility of constructing large-scale underground storage systems by means of contained nuclear explosions, for which the name nuclear geostorage has been coined, should be regarded as a valid alternative to the conventional storage systems currently in existence. Limiting this discussion to systems for storing crude oil, various options are available. The choice of any particular storage method depends, of course, on the circumstances surrounding each particular storage requirement; however, in many cases and for a variety of reasons, nuclear geostorage can be preferable to conventional solutions. Economic considerations are clearly among the most important ones. In this respect an increase in storage capacity will tend to favor the nuclear approach. Besides the economics, however, other considerations are important and may in some cases swing the balance in favor of nuclear geostorage plants, for instance: safety and strategic values, aesthetics, ease of access, lack of suitable tank farm space or lack of suitable geologic conditions for natural reservoirs. It should be borne in mind that the decision to use the nuclear approach to solve a storage problem can only be taken after satisfactory evaluation of the geological and geographical characteristics of the site, and when the technical, safety, political, and public relations factors can be handled adequately. (author)

  1. Nuclear energy and safety of supply

    International Nuclear Information System (INIS)

    Gutierrez, J. E.

    2006-01-01

    According to all kinds of studies, the demand for energy grows more rapidly than population. And it also happens that the consumption of electric energy grows more rapidly than consumption of other primary energies. In view of the spectacular growth of some developing countries, the question is: what type of energy source will we use to cover the growing demand for electric power? If energy should be cheep, reliable and clean, nuclear power should be one of the source used to cover the growing demand. In this respect, it is important to analyze the nuclear fuel cycle to ascertain the reliability of the nuclear power supply. From this perspective,there are three important stages of the front-end of the fuel cycle: uranium concentrate fabrication, enrichment and manufacturing. In recent years, mining production has barely covered half of the demand for uranium, while the rest has been covered by the so-called secondary sources: inventories, strategic reserves, dilution of highly enriched uranium from military weapons, or reprocessing. The known reserves today are enough to cover 65 years of operation of the current fleet. These reserves are much larger if we include those not currently available, or if natural uranium is used directly or reprocessing is included. In the enrichment stage, there is a needed to start operation before the end of the decade of the new plants that are planned. The entry into the market of highly enriched military uranium distroit this market. There is 30% excess capacity in manufacturing which is concentrated in one supplier that accounts for 50% of this excess. Nevertheless, it must be remembered that the fuel assembly is not a commodity, which means that the excess capacity cannot be used directly by the market. To conclude, it can be safety said that, although uranium is not exempt from the tensions to which other raw materials are subject and, as all the fossil fuels, it too could be depleted, the advance of technologies and the

  2. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

    International Nuclear Information System (INIS)

    1979-12-01

    This assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improving the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness. The objectives of this assessment are to identify when economic incentives to deploy advanced nuclear power systems might exist, to estimate the costs of using technologies that would reduce the risk of proliferation, to assess the impact of major economic uncertainties on the transition to new technologies, and to compare the investments required for alternative systems. This information can then be used to assess the potential economic benefits of alternative research, development, and demonstration programs and the timing of those programs

  3. Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-12-01

    This assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improving the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness. The objectives of this assessment are to identify when economic incentives to deploy advanced nuclear power systems might exist, to estimate the costs of using technologies that would reduce the risk of proliferation, to assess the impact of major economic uncertainties on the transition to new technologies, and to compare the investments required for alternative systems. This information can then be used to assess the potential economic benefits of alternative research, development, and demonstration programs and the timing of those programs.

  4. Analysis of supply chain management of N1-EAM project

    International Nuclear Information System (INIS)

    Wu Jize; Liu Xujia; Liu Huanhuan

    2014-01-01

    Supply chain management directly affect the safe and stable operation of nuclear power plants. China's nuclear power production management information system N1-EAM covers supply chain management business. This paper firstly N1-EAM supply chain management functions, advanced analysis of business processes, Qinshan area combined with supply chain management situation, the initial application of the proposed solutions. (authors)

  5. A thermoelectric-conversion power supply system using a strontium heat source of high-level radioactive nuclear waste

    International Nuclear Information System (INIS)

    Chikazawa, Yoshitaka

    2011-01-01

    A thermoelectric-conversion power supply system with radioactive strontium in high-level radioactive waste has been proposed. A combination of Alkali Metal Thermo-Electric Conversion (AMTEC) and a strontium fluoride heat source can provide a compact and long-lived power supply system. A heat source design with strontium fluoride pin bundles with Hastelloy cladding and intermediate copper has been proposed. This design has taken heat transportation into consideration, and, in this regard, the feasibility has been confirmed by a three-dimensional thermal analysis using Star-CD code. This power supply system with an electric output of 1 MW can be arranged in a space of 50 m 2 and approximately 1.1 m height and can be operated for 15 years without refueling. This compact and long-lived power supply is suitable for powering sources for remote places and middle-sized ships. From the viewpoint of geological disposal of high-level waste, the proposed power supply system provides a financial base for strontium-cesium partitioning. That is, a combination of minor-actinide recycling and strontium-cesium partitioning can eliminate a large part of decay heat in high-level waste and thus can save much space for geological disposal. (author)

  6. Availability of nuclear fuels: an aspect of supply assurance. [German Federal Republic

    Energy Technology Data Exchange (ETDEWEB)

    Dolinski, U; Ziesing, H J [Deutsches Inst. fuer Wirtschaftsforschung, Berlin (F.R. Germany)

    1976-08-01

    The future supply possibilities for the Federal Republic of Germany with nuclear fuel are investigated by the German Institute for Economy Research in an expertise on 'the safety, price and environmental aspects in the energy supply'. The requirements of natural uranium in the Federal Republic of Germany are dealt with, as well as the world-wide assured and probable deposits of natural uranium in relation to the extraction costs. After indicating the restrictive changes in the export policy of the supplying countries, the international and national state of development of recycling is shown.

  7. Nuclear technologies for local energy systems

    International Nuclear Information System (INIS)

    McDonnell, F.N.; Lynch, G.F.

    1990-03-01

    If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified and appropriate reactors developed. The Canadian program on reactor systems for local energy supply is at the forefront of these developments. This program emphasizes design simplicity, low power density and fuel rating, reliance on natural processes, passive systems, and reduced reliance on operator action. The first product, the SLOWPOKE Energy System, is a 10 MW heat source specifically designed to provide hot water to satisfy the needs of local heating systems for building complexes, institutions and municipal district heating systems. A demonstration heating reactor has been constructed at the Whiteshell Nuclear Research Establishment in Manitoba and has been undergoing an extensive test program since first operation in 1987 July. Based on the knowledge learned from the design, construction, licensing and operational testing of this facility, the design of the 10 MW commercial-size unit is well advanced, and Atomic Energy of Canada Limited is prepared to commit the construction of the first commercial unit. Although the technical demonstration of the concept is important, it is recognized that another crucial element is the public and regulatory acceptance of small nuclear systems in urban areas. The decision by a community to commit the construction of a SLOWPOKE Energy System brings to a sharp focus the current public apprehension about nuclear technologies

  8. Pickering NGS emergency water supply system emergency start flow simulation and experiment

    Energy Technology Data Exchange (ETDEWEB)

    Davidge, E.; Misra, A. [Ontario Power Generation Inc., Nuclear Safety Analysis & Technology Department, Toronto, Ontario (Canada)

    2012-07-01

    A proposed modification to the OPG Pickering Nuclear Generation Station Emergency Water Supply (EWS) system was analyzed using the Industry Standard Toolset code GOTHIC to determine the acceptability of the proposed system configuration during pump start-up. The new configuration of the system included a vertical dead-ended pipe, initially filled with air. The simulation demonstrated that no significant water hammer effects were predicted and tests performed with the new configuration confirmed the analysis results. (author)

  9. FRAMATOME nuclear services

    International Nuclear Information System (INIS)

    Delorme, H.; Buttin, J.

    1985-05-01

    FRAMATOME is a French company whose main activities since 1958 have been the design and manufacture of standardized PWR Nuclear Steam Supply Systems. FRAMATOME builds the Reactor Coolant System components and installs and starts-up the extended Nuclear Steam Supply Systems. In addition to the supply of spare parts of tooling, the services offered by Framatome are implementation of backfits aimed at performance and safety improvement and equipment reliability, technical assistance and, maintenance and repair services

  10. Cooperation of nuclear, thermal and hydroelectric power plants in the power system

    International Nuclear Information System (INIS)

    1984-01-01

    The conference heard 36 papers of which 23 were incorporated in INIS. The subjects discussed were: the development of power industry in Czechoslovakia, methods of statistical analysis of data regarding nuclear power plant operation, the incorporation of WWER nuclear power plants in the power supply system, the standardization of nuclear power plants, the service life of components, use of nuclear energy sources, performance of the reactor accident protection system, the use of nuclear power and heating plants in Hungary, risk analysis, optimization of nuclear power plants, accidents caused by leakage of the primary and secondary circuit. (J.P.)

  11. Supply of appropriate nuclear technology for the developing world: small power reactors for electricity generation

    International Nuclear Information System (INIS)

    Heising-Goodman, C.D.

    1981-01-01

    This paper reviews the supply of small nuclear power plants (200 to 500 MWe electrical generating capacity) available on today's market, including the pre-fabricated designs of the United Kingdom's Rolls Royce Ltd and the French Alsthom-Atlantique Company. Also, the Russian VVER-440 conventionally built light-water reactor design is reviewed, including information on the Soviet Union's plans for expansion of its reactor-building capacity. A section of the paper also explores the characteristics of LDC electricity grids, reviewing methods available for incorporating larger plants into smaller grids as the Israelis are planning. Future trends in reactor supply and effects on proliferation rates are also discussed, reviewing the potential of the Indian 220 MWe pressurised heavy-water reactor, South Korean and Jananese potential for reactor exports in the Far East, and the Argentine-Brazilian nuclear programme in Latin America. This study suggests that small reactor designs for electrical power production and other applications, such as seawater desalination, can be made economical relative to diesel technology if traditional scaling laws can be altered by adopting and standardising a pre-fabricated nuclear power plant design. Also, economy can be gained if sufficient attention is concentrated on the design, construction and operating experience of suitably sized conventionally built reactor systems. (author)

  12. Nuclear power supplies: their potential and the practical problems to their achievement for space missions

    International Nuclear Information System (INIS)

    Colston, B.W.; Brehm, R.L.

    1985-01-01

    The anticipated growth of the space station power requirement provides a good example of the problem the space nuclear power supply developers have to contend with: should a reactor power supply be developed that attempts to be all things to all missions, i.e., is highly flexible in its ability to meet a wide variety of missions, or should the development of a reactor system await a specific mission definition and be customized to this mission. This leads, of course, to a chicken-and-egg situation. For power requirements of several hundreds of kilowatts or more, no nuclear power source exists or is even far enough along in the definition stage (much less the development stage) for NASA to reasonably assume probable availability within the next 10 years. The real problem of space nuclear power is this ''chicken-and-egg'' syndrome: DOE will not develop a space reactor system for NASA without a firm mission, and NASA will not specify a firm mission requiring a space reactor because such a system doesn't exist and is perceived not to be developable within the time frame of the mission. The problem is how to break this cycle. The SP-100 program has taken an important first step to breaking this cycle, but this program is much more design-specific than what is required to achieve a broad technology base and latitude in achievable power level. In contrast to the SP-100 approach, a wider perspective is required: the development of the appropriate technologies for power levels can be broken into ranges, say, from 100 kWe to 1000 kWe, and from 1000 kWe to 10,000 kWe

  13. Nuclear Energy and Renewables. System Effects in Low-carbon Electricity Systems - Executive Summary

    International Nuclear Information System (INIS)

    2012-01-01

    This report addresses the increasingly important interactions of variable renewables and dispatchable energy technologies, such as nuclear power, in terms of their effects on electricity systems. These effects add costs to the production of electricity, which are not usually transparent. The report recommends that decision-makers should take into account such system costs and internalise them according to a 'generator pays' principle, which is currently not the case. Analysing data from six OECD/NEA countries, the study finds that including the system costs of variable renewables at the level of the electricity grid increases the total costs of electricity supply by up to one-third, depending on technology, country and penetration levels. In addition, it concludes that, unless the current market subsidies for renewables are altered, dispatchable technologies will increasingly not be replaced as they reach their end of life and consequently security of supply will suffer. This implies that significant changes in management and cost allocation will be needed to generate the flexibility required for an economically viable coexistence of nuclear energy and renewables in increasingly de-carbonised electricity systems. (authors)

  14. Supply of and demand for nuclear experts in the EU by 2020. EHRO-N report (2012)

    Energy Technology Data Exchange (ETDEWEB)

    Simonovska, Veronika; Estorff, Ulrik von [European Commission, Joint Research Centre, Petten (Netherlands). Inst. for Energy and Transport

    2014-06-15

    A report from EHRO-N (European Human Resource Observatory of the Nuclear Energy Sector) published in 2012: (1) Determines that the supply of employees with specific educational background and competences, called nuclear experts, does not correspond to the demand for the same employees in the EU by 2020, and that (2) It is useful to put the data on the supply of and demand for nuclear experts in the EU in perspective, using available statistical data on supply of STEM (science, technology, engineering, mathematics) graduates in EU and data on the employed HRST (human resources in science and technology) in the EU labour market. For more refined and accurate data that can determine policy directions, the most effective way would be to conduct regular nuclear human resource monitoring exercises in the EU in the future. This paper is a summary of the first findings as well as of the lessons learnt. (orig.)

  15. Supply Chain Systems Architecture and Engineering Design: Green-field Supply Chain Integration

    OpenAIRE

    Radanliev, P

    2015-01-01

    This paper developed a new theory for supply chain architecture, and engineering design that enables integration of the business and supply chain strategies. The architecture starts with individual supply chain participants and derives insights into the complex and abstract concept of green-field integration design. The paper presented a conceptual system for depicting the interactions between business and supply chain strategy engineering. The system examines the decisions made when engineer...

  16. Reconstruction of Low Pressure Gas Supply System

    Directory of Open Access Journals (Sweden)

    S. N. Osipov

    2013-01-01

    Full Text Available The current reconstruction of residential areas in large cities especially with the developed heat-supply systems from thermal power stations and reduction of heat consumption for heating due to higher thermal resistance of building enclosing structures requires new technical solutions in respect of gas-supply problems. While making reconstruction of a gas-supply system of the modernized or new buildings in the operating zone of one gas-distribution plant it is necessary to change hot water-supply systems from gas direct-flow water heaters to centralized heat-supply and free gas volumes are to be used for other needs or gas-supply of new buildings with the current external gas distribution network.Selection of additional gas-line sections and points of gas-supply systems pertaining to new and reconstructed buildings for their connection to the current distribution system of gas-supply is to be executed in accordance with the presented methodology.

  17. Cooling system for auxiliary systems of a nuclear power plant

    International Nuclear Information System (INIS)

    Maerker, W.; Mueller, K.; Roller, W.

    1981-01-01

    From the reactor auxiliary and ancillary systems of a nuclear facility heat has to be removed without the hazard arising that radioactive liquids or gases may escape from the safe area of the nuclear facility. A cooling system is described allowing at every moment to make available cooling fluid at a temperature sufficiently low for heat exchangers to be able to remove the heat from such auxiliary systems without needing fresh water supply or water reservoirs. For this purpose a dry cooling tower is connected in series with a heat exchanger that is cooled on the secondary side by means of a refrigerating machine. The cooling pipes are filled with a nonfreezable fluid. By means of a bypass a minimum temperature is guaranteed at cold weather. (orig.) [de

  18. Securing a safer, greener, expandable nuclear fuel cycle supply chain for future power production

    International Nuclear Information System (INIS)

    Capus, Georges

    2009-01-01

    After looking at what is necessary to sustainably ensure the global nuclear power plant fleet expansion, it becomes appearant that advanced reactor design should be accompanied with a greener and more flexible fuel cycle capability. The financial crisis has invaded all the front pages and our thoughts. However it has not rescheduled the growth of world population or reduced the desire of people in emerging economies to achieve a higher level of 'development'; nor has it alleviated climate change issues that demand CO2 constrained power sources. What is the outlook for nuclear power? On a worldwide basis, we have today a significant fleet of nuclear power plants, operating well, upgrading output, extending lifetime, and producing not only a safe reliable flow of electricity but a good flow of cash as well. For the countries hosting significant shares of this fleet, their nuclear power plants are increasingly precious assets, and despite the financial crisis, most of them are considering expansion of their nuclear fleets. For the others, the desire to access such a reliable and ultimately cheap source of energy will last longer than the temporary difficulties to get its financing. In short, the outlook for a massive phase of new nuclear builds remains very likely. Then comes the consequential issue of the nuclear fuel supply chain. From uranium exploration and production to back end solutions, most of the existing facilities were designed and startup decades ago. The question is therefore, does this supply chain offer the requested characteristics to sustain the nuclear power plants fleet for the long run? By requested characteristics, it is meant not only adequate capacity and improvement of quality, but also environmentally friendly new designs and processes. This paper is aimed at recalling the current situation of the supply chain, then at describing the status of major projects, and finally at identifying some gaps and issues

  19. EDF: The revision of the electrical supply tariff system

    International Nuclear Information System (INIS)

    Kaczmarek, A.M.

    1982-01-01

    The article deals with proposals by EDF for restructuring their tariffs for the supply of electricity. The objective is to take account of probable developments in demand, notably the steadily increasing gap between the summer and winter rates of consumption, and in generation, notably the large increase in the fraction of the total load that is met by nuclear stations. It is estimated that by 1990 generation will be 70% nuclear, 16% hydraulic, 9% by coal and 4% by oil, nuclear generation being by far the cheapest. The general philosophy of the new tariffs is: to retain the two-part (kW and kWh) structure; to simplify tariffs for small consumers; to apply to large consumers sophisticated tariffs that accurately reflect true costs of supply; to make maximum demand rather than supply voltage the determining factor; tariffs will be geographically uniform except for a few very large consumers favourably situated with respect to key points in the network; to adopt special means to spread peak loads. The new tariffs and some additional related measures for influencing the incidence of electricity consumption are described in some detail. (C.J.O.G.)

  20. A study on optimization of the nuclear safety system

    International Nuclear Information System (INIS)

    Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

    1986-12-01

    The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

  1. Supporting system in emergency response plan for nuclear material transport accidents

    International Nuclear Information System (INIS)

    Nakagome, Y.; Aoki, S.

    1993-01-01

    As aiming to provide the detailed information concerning nuclear material transport accidents and to supply it to the concerned organizations by an online computer, the Emergency Response Supporting System has been constructed in the Nuclear Safety Technology Center, Japan. The system consists of four subsystems and four data bases. By inputting initial information such as name of package and date of accident, one can obtain the appropriate initial response procedures and related information for the accident immediately. The system must be useful for protecting the public safety from nuclear material transport accidents. But, it is not expected that the system shall be used in future. (J.P.N.)

  2. Complex approach to power supply system in the Tomsk region

    International Nuclear Information System (INIS)

    Meshcheryakov, V.N.; Bojko, V.I.; Koshelev, F.P.; Kolpakov, G.N.; Shamanin, I.V.

    2001-01-01

    The problem of power supply of the Tomsk region is under consideration. Power sources are compared with regard to economical and ecological effectiveness. It is shown that nuclear power industry is promising for the Tomsk region due to a unique nuclear park in a town of Seversk with developed scientific, industrial, skilled personnel and construction bases. It is noted that the construction of the NPP based on two WWER-640, WWER-1000 reactors of new generation permits solving the problem of power supply of the Tomsk region [ru

  3. Study on the establishment of effective nuclear export system

    International Nuclear Information System (INIS)

    Kim, Byung Koo; So, Dong Sup; Baik, Dae Hyun; Kwack, Eun Ho; Shin, Jang Soo; Yoon, Wan Ki; Park, Wan Soo; Kim, Hyun Tae.

    1997-02-01

    To improve Korean nuclear export control system, the modification of the present export license procedure for the nuclear equipment and materials and the classification of control items and their related technologies are required. And it is also necessary to make a database of the original countries who have the right of prior consent. For the efficient export control of LWR items to DPRK, it is desirable to manage the export license scheme of nuclear reactor facility as a total package, and to prepare a control regime for the retransfer of nuclear reactor component such as reactor coolant pump and nuclear fuel whose technologies are not self-reliant. It is especially essential to prepare a systematic procedure for the supply of nuclear equipment and materials to DPRK in order to meet international guidelines of NSG and others through an accord on the nuclear cooperation between Republic of Korea (ROK) and DPRK. The principal elements to be included in the accord are the range of cooperation, the restriction within the peaceful uses, prior consent right in case of retransfer of important nuclear reactor components and of storage, transfer and changes of nuclear fuels, application of safeguards to the supplied Trigger list items, physical protection of nuclear material, requirement of the return of nuclear equipment and materials, and restriction right for the suspension or termination of the agreement. (author). 40 refs., 5 tabs., 8 figs

  4. The structure of an expert system to diagnose and supply a corrective procedure for nuclear power plant malfunctions

    International Nuclear Information System (INIS)

    Hajek, B.K.; Stasenko, J.E.; Hashemi, S.; Bhatnagar, R.; Punch, W.F. III; Yamada, N.

    1987-01-01

    During the past two years, two prototype knowledge based systems have been developed at the Ohio State University. These systems were the result of collaboration between the Nuclear Engineering Program and the Laboratory for Artificial Intelligence Research (LAIR). The first system uses hierarchical classification to diagnose malfunctions of the coolant system in a General Electric Boiling Water Reactor (BWR). The second system provides a plan of action, through a process of dynamic procedure management, to stabilize the plant once an abnormal transient has occurred. The objective of this paper is to discuss the structure that has been designed to integrate the two systems. The combined system will be capable of informing plant personnel about the nature of malfunctions, and of supplying to the operator the most direct corrective procedure available. Two important features of the integrated system are faulty sensor detection, based on malfunction context and unlike sensor data, and procedure management based on the initial state of the plant. Since the two knowledge based systems were developed separately, the integration has required a separate component currently under development, the Plant Status Monitoring System (PSMS). The task of PSMS is to monitor plant parameters in order to detect an abnormal condition developing within the plant. Based on the nature of the event, PSMS is capable of directing control to either the procedure management or diagnosis component. The integrated system plays only an advisory role, and any suggested action would be executed by the plant personnel

  5. Study on the FBR cycle introduction scenario. 2. A study on the role of nuclear energy under the diversity of energy supply-and-demand

    International Nuclear Information System (INIS)

    Ohtaki, Akira; Ono, Kiyoshi; Hirao, Kazunori

    2002-03-01

    This report concerns it self with the results of an investigation about the possibility of future nuclear utilization in the part of FBR Cycle Introduction Scenario Study in the JNC's 'Feasibility Study on Commercialized Fast Reactor Cycle System (the F/S)'. We have investigated about the problems that confront energy industries and electric power companies, the capacities of distributed generation, the coexistence method of a distributed generation and large-scale power supply generation, and the development status of a small-scale nuclear reactor from a wide viewpoint. Especially the spread of distributed generation causes the decrease of the electricity demand which the electric power companies supplies. Since introduction scale of a distributed power supply is also expected to increase in the future, it will give some influences to a future nuclear plan and a power supply plan. The hydrogen utilization with out greenhouse gas mission is expected to spread with distributed generation, such as a fuel cell and a micro-gas turbine. Therefore, we proposed the new business model that the hydrogen produced by using nuclear surplus electricity is consumed distributed generation, such as a fuel cell and a micro-gas turbine. We plan to evaluate quantitatively the best power supply composition based on this load stability business model, FBR introduction capacities, the load factor, and the amount of CO 2 reduction. (author)

  6. A method of short range system analysis for nuclear utilities

    International Nuclear Information System (INIS)

    Eng, R.; Mason, E.A.; Benedict, M.

    1976-01-01

    An optimization procedure has been formulated and tested that is capable of solving for the optimal generation schedule of several nuclear power reactors in an electric power utility system, under short-range, resource-limited, conditions. The optimization procedure utilizes a new concept called the Opportunity Cost of Nuclear Power (OCNP) to optimally assign the resource-limited nuclear energy to the different weeks and hours in the short-range planning horizon. OCNP is defined as the cost of displaced energy when optimally distributed nuclear energy is marginally increased. Under resource-limited conditions, the short-range 'value' of nuclear power to a utility system is not its actual generation cost, but the cost of the next best alternative supply of energy, the OCNP. OCNP is a function of a week's system reserve capacity, the system's economic loading order, the customer demand function, and the nature of the available utility system generating units. The optimized OCNP value of the short-range planning period represents the utility's short-range energy replacement cost incurred when selling nuclear energy to a neighbouring utility. (author)

  7. Study of the supply chain of the Brazilian Nuclear Program: partial report

    International Nuclear Information System (INIS)

    2009-01-01

    This document aims to contextualize the impact of the nuclear sector retaking national and internationally, on the productive phases, identifying the supply chain, analyzing the actual situation as well as the favorable perspectives and existing critical points

  8. Electricity supply in India

    International Nuclear Information System (INIS)

    Abbott, H.J.

    1993-09-01

    This briefing deals with the electricity supply industry in India in two parts. In the first, the structure and organization of the industry is described under sections dealing with national government involvement, energy policy, state electricity boards, regional electricity boards, state corporations, the private sector and private investment in the power sector including foreign investment. Secondly, the power supply system is described covering generation, plant load factor, non-utility generation, nuclear power, transmission and distribution, system losses and electricity consumption. (8 tables) (UK)

  9. Thermal coupling system analysis of a nuclear desalination plant

    International Nuclear Information System (INIS)

    Adak, A.K.; Srivastava, V.K.; Tewari, P.K.

    2010-01-01

    When a nuclear reactor is used to supply steam for desalination plant, the method of coupling has a significant technical and economic impact. The exact method of coupling depends upon the type of reactor and type of desalination plant. As a part of Nuclear Desalination Demonstration Project (NDDP), BARC has successfully commissioned a 4500 m 3 /day MSF desalination plant coupled to Madras Atomic Power Station (MAPS) at Kalpakkam. Desalination plant coupled to nuclear power plant of Pressurized Heavy Water Reactor (PHWR) type is a good example of dual-purpose nuclear desalination plant. This paper presents the thermal coupling system analysis of this plant along with technical and safety aspects. (author)

  10. TEXT poloidal coil systems power supplies

    International Nuclear Information System (INIS)

    Hutchins, S.H.; Brower, D.F.

    1977-01-01

    TEXT is a convertional iron core tokamak which will have a toroidal field of 3.0 Tesla produced by room temperature copper coils and a maximum plasma current pulse of 400 kA induced by a 40 turn Ohmic Heating coil. The major radius is 100 cm and the minor radius of the plasma is 28 cm. The machine is intended for basic research in tokamak plasma physics and atomic physics and is designed primarily to provide a stable hot plasma, extremely good diagnostic access, and reliable operation. The discharge pulse length will be 300 msec and the repetition period 120 seconds. Power for the toroidal field coils and for the ohmic heating supply is provided by a 100 MVA energy storage alternator. The vertical field, horizontal field, fast positioning, and discharge cleaning power supply systems are powered from the Tokamak Laboratory power mains. The ohmic heating power system consists of an SCR controlled premagnetizing supply and commutation circuit, the main ohmic heating capacitor bank to provide plasma breakdown and current rise, and an SCR controlled power supply which sustains plasma current during the 300 ms pulse. The vertical field power system uses a small capacitor bank and an SCR controlled supply. The horizontal field has a reversible SCR controlled supply, and the fast positioning coils are powered by bipolar output transistor controlled supplies. This paper describes the loads, required wave forms, and the specifications for these power supply systems

  11. Inspection methods for safeguards systems at nuclear facilities

    International Nuclear Information System (INIS)

    Minichino, C.; Richard, E.W.

    1981-01-01

    A project team at Lawrence Livermore National Laboratory has been developing inspection procedures and training materials for the NRC inspectors of safeguards systems at licensed nuclear facilities. This paper describes (1) procedures developed for inspecting for compliance with the Code of Federal Regulations, (2) training materials for safeguards inspectors on technical topics related to safeguards systems, such as computer surety, alarm systems, sampling techniques, and power supplies, and (3) an inspector-oriented methodology for evaluating the overall effectiveness of safeguards systems

  12. Problems in producing nuclear reactor for medical isotopes and the Global Crisis of molybdenum supply

    International Nuclear Information System (INIS)

    Zubiarrain, A.

    2011-01-01

    Nuclear medicine uses drugs that incorporate a radioactive isotope radiopharmaceuticals. Every year are performed, worldwide, 35 million nuclear medicine procedures, of which 80% are done with radiopharmaceuticals containing the isotope, molybdenum-99, produced in nuclear reactors. In recent years, there have been several supply crisis of molybdenum-99, which have hampered diagnostic procedure with technitium-99m. (Author)

  13. Power supply system for KSTAR neutral beam injector

    Energy Technology Data Exchange (ETDEWEB)

    Cho, W., E-mail: franciscocho@nfri.re.kr; Bae, Y.S.; Han, W.S.; Jeong, J.H.; Kim, J.S.; Park, H.T.; Yang, H.L.; Oh, Y.K.; Kwak, J.G.

    2015-10-15

    Highlights: • The power supply system in KSTAR NBI consists of DC power supplies for ion source. • For operation NBI, DC High Voltage based on the low voltage transformer with chopper. • The surge absorber near the ion source limit the energy deposited to accelerator grid. - Abstract: The power supply system in KSTAR neutral beam injector consists of low voltage and high current DC power supplies for plasma generator of ion source and high voltage and high current DC power supply for accelerator grid system. The arc discharge is initiated by an arc power supply supplying the arc voltage between the chamber wall and 12 filaments which are heated by individual filament power supply. The negative output of arc power supply is common to each positive output of 12 filament power supplies. To interrupt the arc discharging for the fault condition of the arc current unbalance, DCCT current monitor is placed at the positive output cable of the filament power supply. The plasma grid (G1) power supply has the maximum capability of 120 kV/70 A which consists of low voltage regulator with IGBT-switched chopper array system for the voltage control in unit of 600 V and the high voltage rectified transformers to supply DC voltage of 20 kV, 30 kV, and 50 kV. The output voltage of the G1 power supply is also connected to the input of the voltage divider system which supplies the gradient voltage to the gradient grid (G2) in the range of 80–90% of G1 voltage by changing tap of winding resistors in unit of 1%. The charged G1 voltage is turned on and off by the high voltage switch (HVS) system consisting of MOSFET fast semiconductor switches which can immediately be opened less than 1 μs when the ion source grid breakdown occurs. The decelerating grid (G3) power supply is inverter system using capacitor-charge power supply to supply maximum −5 kV/5 A. The important component in power supply system is the surge absorber near the ion source to limit the arc energy deposited to

  14. Power supply system for KSTAR neutral beam injector

    International Nuclear Information System (INIS)

    Cho, W.; Bae, Y.S.; Han, W.S.; Jeong, J.H.; Kim, J.S.; Park, H.T.; Yang, H.L.; Oh, Y.K.; Kwak, J.G.

    2015-01-01

    Highlights: • The power supply system in KSTAR NBI consists of DC power supplies for ion source. • For operation NBI, DC High Voltage based on the low voltage transformer with chopper. • The surge absorber near the ion source limit the energy deposited to accelerator grid. - Abstract: The power supply system in KSTAR neutral beam injector consists of low voltage and high current DC power supplies for plasma generator of ion source and high voltage and high current DC power supply for accelerator grid system. The arc discharge is initiated by an arc power supply supplying the arc voltage between the chamber wall and 12 filaments which are heated by individual filament power supply. The negative output of arc power supply is common to each positive output of 12 filament power supplies. To interrupt the arc discharging for the fault condition of the arc current unbalance, DCCT current monitor is placed at the positive output cable of the filament power supply. The plasma grid (G1) power supply has the maximum capability of 120 kV/70 A which consists of low voltage regulator with IGBT-switched chopper array system for the voltage control in unit of 600 V and the high voltage rectified transformers to supply DC voltage of 20 kV, 30 kV, and 50 kV. The output voltage of the G1 power supply is also connected to the input of the voltage divider system which supplies the gradient voltage to the gradient grid (G2) in the range of 80–90% of G1 voltage by changing tap of winding resistors in unit of 1%. The charged G1 voltage is turned on and off by the high voltage switch (HVS) system consisting of MOSFET fast semiconductor switches which can immediately be opened less than 1 μs when the ion source grid breakdown occurs. The decelerating grid (G3) power supply is inverter system using capacitor-charge power supply to supply maximum −5 kV/5 A. The important component in power supply system is the surge absorber near the ion source to limit the arc energy deposited to

  15. Development of a Nuclear Steam Supply System Thermal-Hydraulic Module for the Nuclear Power Plant Simulator Using a Best-Estimate Code, RETRAN

    International Nuclear Information System (INIS)

    Suh, Jae Seung

    2004-08-01

    The NSSS (Nuclear Steam Supply System) thermal-hydraulic programs adopted in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually used very simplified physical models for the real-time simulation of Ness thermal-hydraulic transients, which entails inaccurate results and, thus, the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, a realistic NSSS thermal-hydraulic program ARTS has been developed, it was based on the RETRAN code for the improvement of the Nuclear Power Plant full-scope simulator. Since ARTS is a generalized code to solve a simultaneous equation system, the smaller time-step size should be used if converged solution could not obtain even in a single volume. Therefore, dedicated models which do not force to reduce the time-step size are sometimes more suitable in terms of a real-time calculation and robustness. The PRT(Pressurizer Relief Tank) is a good example, which requires a dedicated model. The PRT consists of subcooled water in bottom and non-condensable gas in top. The sparger merged under subcooled water enhances condensation. The complicated thermal-hydraulic phenomena such as condensation, phase separation with existence of non-condensable gas makes difficult to simulate. Therefore, the PRT volume may limit the time-step size if it is modeled with a general control volume. To mitigate the time-step size reduction due to convergence failure at this component using RETRAN, the PRT model was developed as a dedicated model. The dedicated model was expected to provide reasonable results without convergence problem in the analysis of the system transients. The ARTS code guarantees the real-time calculations of almost all transients and ensures the robustness of simulations. However, there are some possibilities of calculation failure in the

  16. Uncertainty of Japanese electricity supply after nuclear disaster

    International Nuclear Information System (INIS)

    Uchiyama, Yohji

    2012-01-01

    The article describes the uncertainty of the Japanese energy policy influenced by disaster of the Fukushima Daiichi Nuclear Plants. With mounting criticism of nuclear power generation, the pro-nuclear tide which existed prior to the accident will probably end in the newly formulated energy policy. A review of Japan's energy policy is about to start. It is necessary to supply energy that makes us feel safe and secure in order to support people's lives and industrial activities in society. Every energy source entails risks, and we need to develop a concept of allowance that represents what level of energy usage is permissible. This is not a matter of 'making scientific determinations demarcated by the questions of harm versus harmless and risk versus safety', but rather the social concept of 'to what extend can we tolerate the risks while still looking at something as a positive' from the perspective of people's lives. Japanese people have a tendency to judge safety subjectively and demand absolute safety. Various risks have developed in today's globalized society, and it is important to regard permissible levels for each of these risks in an objective fashion. (author)

  17. THE COSTS OF ENERGY SUPPLY SECURITY

    Energy Technology Data Exchange (ETDEWEB)

    Rogner, H.H.; Langlois, L.M.; McDonald, A.; Weisser, D.; Howells, M.

    2007-07-01

    In general, increasing a country's energy supply security does not come for free. It costs money to build up a strategic reserve, to increase supply diversity or even to accelerate energy efficiency improvements. Nor are all investments in increasing energy supply security cost effective, even if the shocks they are designed to insure against can be predicted with 100% accuracy. The first half of the paper surveys different definitions and strategies associated with the concept of energy supply security, and compares current initiatives to establish an 'assured supply of nuclear fuel' to the International Energy Agency's (IEA's) system of strategic national oil reserves. The second half of the paper presents results from several case studies of the costs and effectiveness of selected energy supply security policies. One case study examines alternative strategies for Lithuania following the scheduled closure of the Ignalina-2 nuclear reactor in 2009. The second case study examines, for countries with different energy resources and demand structures, the effectiveness of a policy to increase supply diversity by expanding renewable energy supplies. (auth)

  18. Reliability estimation for multiunit nuclear and fossil-fired industrial energy systems

    International Nuclear Information System (INIS)

    Sullivan, W.G.; Wilson, J.V.; Klepper, O.H.

    1977-01-01

    As petroleum-based fuels grow increasingly scarce and costly, nuclear energy may become an important alternative source of industrial energy. Initial applications would most likely include a mix of fossil-fired and nuclear sources of process energy. A means for determining the overall reliability of these mixed systems is a fundamental aspect of demonstrating their feasibility to potential industrial users. Reliability data from nuclear and fossil-fired plants are presented, and several methods of applying these data for calculating the reliability of reasonably complex industrial energy supply systems are given. Reliability estimates made under a number of simplifying assumptions indicate that multiple nuclear units or a combination of nuclear and fossil-fired plants could provide adequate reliability to meet industrial requirements for continuity of service

  19. New reactor technology: safety improvements in nuclear power systems.

    Science.gov (United States)

    Corradini, M L

    2007-11-01

    Almost 450 nuclear power plants are currently operating throughout the world and supplying about 17% of the world's electricity. These plants perform safely, reliably, and have no free-release of byproducts to the environment. Given the current rate of growth in electricity demand and the ever growing concerns for the environment, nuclear power can only satisfy the need for electricity and other energy-intensive products if it can demonstrate (1) enhanced safety and system reliability, (2) minimal environmental impact via sustainable system designs, and (3) competitive economics. The U.S. Department of Energy with the international community has begun research on the next generation of nuclear energy systems that can be made available to the market by 2030 or earlier, and that can offer significant advances toward these challenging goals; in particular, six candidate reactor system designs have been identified. These future nuclear power systems will require advances in materials, reactor physics, as well as thermal-hydraulics to realize their full potential. However, all of these designs must demonstrate enhanced safety above and beyond current light water reactor systems if the next generation of nuclear power plants is to grow in number far beyond the current population. This paper reviews the advanced Generation-IV reactor systems and the key safety phenomena that must be considered to guarantee that enhanced safety can be assured in future nuclear reactor systems.

  20. Building and application of the performance diagnosis system for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, S.; Kanbara, K.; Sugawara, Y.

    2010-01-01

    To achieve a low-carbon society, we promote utilization of nuclear energy, which plays a zero-emission power generation. Therefore the nuclear power plants have been imposed a stable supply of electricity. The condition based maintenance (CBM) is effective in order to maintain a stable operation of the nuclear power plants. We built the performance diagnosis system based on the heat and mass balance calculation as one of supporting tools for the CBM. Moreover we note that the performance diagnosis system is built for steam turbine cycle operating with saturated steam conditions. (author)

  1. Construction of APR1000 nuclear power information management system based on international standards

    International Nuclear Information System (INIS)

    Choi, Seung Hwan; Song, Deok Yong; Han, Byung Sub; An, Kyung Ik; Hwang, Jin Sang

    2010-01-01

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model

  2. Construction of APR1000 nuclear power information management system based on international standards

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Seung Hwan [Korea Electric Power Research Institute, Daejeon (Korea, Republic of); Song, Deok Yong; Han, Byung Sub [Enesys Co., Daejeon (Korea, Republic of); An, Kyung Ik; Hwang, Jin Sang [PartDB Co., Daejeon (Korea, Republic of)

    2010-10-15

    In recent years, due to speedy rise of international oil prices, orders of nuclear power plant construction have been in progress by many countries to solve the stable supply of power. Our country has continued to perform nuclear power construction. As only a few developed countries like Japan and European countries have its own nuclear power construction technology, competition among them is keen. Our country has awarded the contract of UAE nuclear power plants based on the accumulated nuclear power plant construction technologies so far. In this regard, KEPCO has recognized the needs of information management system to manage nuclear power information and proceeded the implementation of nuclear power information management system for export-model

  3. Energy the security of supply in question. Combating global warming: what role for nuclear power. Warning issued by the International Energy Agency

    International Nuclear Information System (INIS)

    Montbrial, T. de; Moore, P.; Cambell, N.

    2007-01-01

    This issue of Alternatives newsletter put the question of energy supplies security. The unequal distribution of the world's energy resources raises the problem of energy independence and the security of supply. This question is particularly pertinent for Europe which, along with the Far East, possesses only a meager share of the planet's store of fossil fuels. Europe must learn how to live with its energy dependency, knowing that independence is an unrealistic objective in a world built on the interdependence of trade. The world's energy system is vulnerable to disruptions in supply and to geopolitical tensions. Given this context of instability, how can the security of supply and energy independence be increased? The challenge for western countries with few fossil fuel resources is to secure reliable supply while reducing energy dependency. One solution consists in diversifying power generation sources to lower dependency on oil and gas. The nuclear question is analyzed through the different point of views of Greenpeace and Greenspirit Strategies. Greenpeace refuses even the slightest involvement of nuclear power and considers that energy efficiency and renewable technologies are the only solution to both global warming and energy questions. On the other hand, Greenspirit Strategies sees nuclear power, combined with increased efforts to develop renewable energies, playing an essential role in the sustainable production of electricity. A last article devoted to the World Energy Outlook 2006 - the report published by the International Energy Agency - presents the hypotheses advanced by the Agency regarding future energy supply and its recommendations for counteracting a scenario for 2030 that is, to say the least, very alarming

  4. The renewable and nuclear energies in the basquet of energy supply; Las energias nuclear y renovables en La cesta del suministro energetico

    Energy Technology Data Exchange (ETDEWEB)

    Martinez Corcoles, F.

    2008-07-01

    The share of nuclear and renewable sources in the energy portfolio yields great benefits to all stake holders and that both sources are not exclusive each other but offer multiple complementary features and synergy's, therefore both technologies should be part of the present and future energy mix. This portfolio should be enough and reliable all the time, guarantee the security of supply, protect the environment and give competitive prices. All these features are to a great extent met by nuclear and renewable technologies and therefore they should play an important role on world and national energy supply. (Author)

  5. Domestic nuclear fuels supply: possibility of an independent technology

    International Nuclear Information System (INIS)

    Cirimello, R.O.

    1982-01-01

    After considering the different energy sources, their consumption and their respective periods of exploitation, technological considerations in the nuclear fuel field are made. The main subject is the Domestic Supply Project of Embalse Fuel (CANDU type). The different aspects which had to be developed during the realization of this project still under progress, and which are fundamental for the command of the technology, are described: 1) Qualification of the produced fuel elements: fuel elements' characteristics; the reactors' operating parameters, and the prototype fuel elements' characteristics; 2) Development of materials and/or suppliers: the obtainment of UO 2 and its physical properties are considered, as well as those of Zircaloy-4, the development of suppliers and the respective developments for the obtainment of materials such as beryllium, helium and colloidal graphite; 3) Processes development; the following processes are studied and defined: UO 2 pellets fabrication with UO 2 granulated powder; beryllium coating under vaccum; and induction brazing of bearing pads and spacers, end cap and end plate resistance welding and stamping of Zircaloy components, graphite-coating of cladding's internal face; 4) Development of special production equipments; automatic equipment for end cap-to-cladding resistance welding among others. The need for a specific program of quality assurance for nuclear fuels supply is emphasized and the basic criteria are established. The IAEA's quality asssurance requirements are also analyzed. (M.E.L.) [es

  6. A study on the nuclear computer codes installation and management system

    International Nuclear Information System (INIS)

    Kim, Yeon Seung; Huh, Young Hwan; Kim, Hee Kyung; Kang, Byung Heon; Kim, Ko Ryeo; Suh, Soong Hyok; Choi, Young Gil; Lee, Jong Bok

    1990-12-01

    From 1987 a number of technical transfer related to nuclear power plant had been performed from C-E for YGN 3 and 4 construction. Among them, installation and management of the computer codes for YGN 3 and 4 fuel and nuclear steam supply system was one of the most important project. Main objectives of this project are to establish the nuclear computer code management system, to develop QA procedure for nuclear codes, to secure the nuclear code reliability and to extend techanical applicabilities including the user-oriented utility programs for nuclear codes. Contents of performing the project in this year was to produce 215 transmittal packages of nuclear codes installation including making backup magnetic tape and microfiche for software quality assurance. Lastly, for easy reference about the nuclear codes information we presented list of code names and information on the codes which were introduced from C-E. (Author)

  7. Status of the new nuclear energy systems study in CIAE

    International Nuclear Information System (INIS)

    Ding, D.; Luo, Z.; Xu, M.

    2003-01-01

    The nuclear energy civil-application has been started in China. To meet the long-term sustainable primary energy supply it could be envisaged that the nuclear power systems will be developed in large scale. Following three key points must be satisfied by the future nuclear energy systems: - more safer nuclear energy systems than recent those should be developed to decrease the risk of core-melten and unforeseen release of radioactive materials; - long lived minor actinides and long lived fission products must be safely treated to assure a proper environment; - uranium resource should be sufficiently utilized. In order to meet above general requirements, the fast reactor technology development has been launched and the basic researches of Accelerator Driven Subcritical facility (ADS) system has been started in China. The activity of the construction of the China Experimental Fast Reactor and plan for next step, some calculation results on core physics study of ADS, some results on target physics and a proposed verification facility are briefed in the paper. (author)

  8. Sustainable minireactors: A framework for decentralized nuclear energy systems

    International Nuclear Information System (INIS)

    Harms, A.A.; Sassin, W.W.

    1983-01-01

    The concept of a nuclear energy system consisting of numerous small, specialized nuclear reactors providing heat or electricity for localized/regional purposes is considered. It is envisaged that a ''parent'' nuclear facility would sustain the fuel needs of many small nuclear energy ''satellites'' and possibly provide other fuel-management services. The choice of fuel cycle and the operational features of these satellites may be determined by the form of energy required, public and social preferences, and institutional factors. Three distinct classes of distributed systems, each based on extensions of existing nuclear technology, are identified and discussed. In addition to the points emphasized concerning the types of minireactors and the fuel cycles chosen, it is important to recognize the potential for mass-production of these smaller facilities. Also, if the fuel-consuming part of the system is widely distributed geographically and if the fuel can be stored, the simultaneous failure of substantial parts of the energy supply system seems unlikely. Finally, if there were a local need for medium-power facilities, provision for the stacking of minireactors to attain a specified power level could be introduced

  9. Can fuel services supply be secured? Building trust in a multi-lateral approach to nuclear fuel cycles

    Energy Technology Data Exchange (ETDEWEB)

    Antoine, B. [Engineering Systems Division, Massachusetts Institute of Technology, 77 Massachusetts Avenue, Room E40-261, Cambridge, MA 02139 (United States); Rodriguez-Vieitez, E. [Belfer Center for Science and International Affairs, Kennedy School of Government, Harvard University, One Brattle Sq., Room 503, Cambridge, MA 02138 (United States)

    2009-06-15

    Global climate change and concerns about energy supply security fuelling the nuclear desires of an increasing number of states, there is growing interest within the nonproliferation community to promote the establishment of an international system for the provision of nuclear fuel cycle services that would be 'equitable and accessible to all users of nuclear energy' (Rauf, 2008) while reducing proliferation risks. Although the idea was already voiced on the cradle of civilian use of nuclear energy (Baruch, 1946), the IAEA director's 2003 call for a group of international experts to examine the issue (ElBaradei, 2003) triggered renewed interest that resulted in up to twelve different proposals for multilateral nuclear fuel cycle arrangements (Rauf, 2008; Simpson, 2008). Nonproliferation experts have examined the conditions under which equitable and accessible access to enrichment, reprocessing and spent fuel disposal services can be granted to all users (Rauf, 2008; Braun 2006; Pellaud and al 2005). They suggested putting together multilateral nuclear approaches (MNA) that could consist in the establishment of mechanisms to assure fuel cycle services, or the shared ownership by recipient and host countries of fuel services facilities through either the creation of new multilateral centers or the conversion of existing national facilities into multinational enterprises. While countries that possess nuclear fuel facilities would benefit from the increased global security and strengthened non-proliferation situation that would result from the establishment of these MNAs, they would also be baited into participating by possible attraction of foreign investments as well as the opportunity to export high value services (Rushkin, 2006). Yet, what incentives would there be for a recipient non-nuclear state to participate in an arrangement that would intrinsically strip it of its sovereign right to ensure its fuel supply security? In addition to the economic

  10. Geothermal heat-pump systems of heat supply

    International Nuclear Information System (INIS)

    Vasil'ev, G.P.

    2004-01-01

    The data on the multilayer operation of the objects, located in the climatic conditions of the central area of Russia and equipped with the geothermal heat-pumping systems of the heat supply are presented. The results of the analytical studies on evaluating the geothermal heat-pumping systems of the heat supply integration efficiency into the structure of the energy supply system, prevailing in the country, are presented [ru

  11. Experience in Modelling Nuclear Energy Systems with MESSAGE: Country Case Studies

    International Nuclear Information System (INIS)

    2018-01-01

    Member States have recognized the increasing need to model future nuclear power scenarios in order to develop strategies for sustainable nuclear energy systems. The IAEA model for energy supply strategy alternatives and their general environmental impacts (MESSAGE) code is a tool that supports energy analysis and planning in Member States. This publication documents the experience gained on modelling and scenario analysis of nuclear energy systems (NES) using the MESSAGE code through various case studies performed by the participating Member States on evaluation and planning for nuclear energy sustainability at the regional or national level. The publication also elaborates on experience gained in modelling of global nuclear energy systems with a focus on specific aspects of collaboration among technology holder and technology user countries and the introduction of innovative nuclear technologies. It presents country case studies covering a variety of nuclear energy systems based on a once-through fuel cycle and a closed fuel cycle for thermal reactors, fast reactors and advanced systems. The feedback from case studies proves the analytical capabilities of the MESSAGE model and highlight the path forward for further advancements in the MESSAGE code and NES modelling.

  12. Investigation of thermochemical biorefinery sizing and environmental sustainability impacts for conventional supply system and distributed preprocessing supply system designs

    Energy Technology Data Exchange (ETDEWEB)

    Muth, jr., David J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Langholtz, Matthew H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Tan, Eric [National Renewable Energy Lab. (NREL), Golden, CO (United States); Jacobson, Jacob [Idaho National Lab. (INL), Idaho Falls, ID (United States); Schwab, Amy [National Renewable Energy Lab. (NREL), Golden, CO (United States); Wu, May [Argonne National Lab. (ANL), Argonne, IL (United States); Argo, Andrew [Sundrop Fuels, Golden, CO (United States); Brandt, Craig C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cafferty, Kara [Idaho National Lab. (INL), Idaho Falls, ID (United States); Chiu, Yi-Wen [Argonne National Lab. (ANL), Argonne, IL (United States); Dutta, Abhijit [National Renewable Energy Lab. (NREL), Golden, CO (United States); Eaton, Laurence M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Searcy, Erin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-03-31

    The 2011 US Billion-Ton Update estimates that by 2030 there will be enough agricultural and forest resources to sustainably provide at least one billion dry tons of biomass annually, enough to displace approximately 30% of the country's current petroleum consumption. A portion of these resources are inaccessible at current cost targets with conventional feedstock supply systems because of their remoteness or low yields. Reliable analyses and projections of US biofuels production depend on assumptions about the supply system and biorefinery capacity, which, in turn, depend upon economic value, feedstock logistics, and sustainability. A cross-functional team has examined combinations of advances in feedstock supply systems and biorefinery capacities with rigorous design information, improved crop yield and agronomic practices, and improved estimates of sustainable biomass availability. A previous report on biochemical refinery capacity noted that under advanced feedstock logistic supply systems that include depots and pre-processing operations there are cost advantages that support larger biorefineries up to 10 000 DMT/day facilities compared to the smaller 2000 DMT/day facilities. This report focuses on analyzing conventional versus advanced depot biomass supply systems for a thermochemical conversion and refinery sizing based on woody biomass. The results of this analysis demonstrate that the economies of scale enabled by advanced logistics offsets much of the added logistics costs from additional depot processing and transportation, resulting in a small overall increase to the minimum ethanol selling price compared to the conventional logistic supply system. While the overall costs do increase slightly for the advanced logistic supply systems, the ability to mitigate moisture and ash in the system will improve the storage and conversion processes. In addition, being able to draw on feedstocks from further distances will decrease the risk of biomass supply to

  13. Developing competence based qualification system in the nuclear energy sector

    International Nuclear Information System (INIS)

    Ceclan, Mihail

    2016-01-01

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  14. Developing competence based qualification system in the nuclear energy sector

    Energy Technology Data Exchange (ETDEWEB)

    Ceclan, Mihail [European Commission, Petten (Netherlands). Inst. for Energy and Transport

    2016-04-15

    The Institute for Energy and Transport of the Joint Research Centre, European Commission, developed a strategy and road map for ECVET implementation. The JRC road map for European Credit System for Vocational Education and Training (ECVET) implementation has reached the stage of Competence-Based Qualification System development. The Competence-Based Qualification System can help bridge the gap between Human Resources demand and supply in the nuclear market by structuring qualifications in small independent parts. This very specific ECVET feature of a qualification, facilitates the process of competences accumulation and the lifelong learning, mobility and flexible learning pathways. New developments are presented about the Competence-Based Qualification System development for the nuclear energy sector.

  15. The role of enterprise systems in supply chain networks: a taxonomy of supply chain strategies

    DEFF Research Database (Denmark)

    Møller, Charles

    2006-01-01

    in the supply chain and to choose the right supply chain strategy. The work is based on a comprehensive study of the Supply Chain Management (SCM) and Enterprise Resource Planning (ERP) literature and the study suggests that there is an emerging new research potential for Enterprise Systems (ES) in the supply......This paper proposes a taxonomy for supply chain integration strategies. The taxonomy is based on the contingencies of supply chain network coupling and the Extended Enterprise Systems (EES) architecture in the supply chain. The purpose of this model is to map the portfolio of relations...

  16. Energy the security of supply in question. Combating global warming: what role for nuclear power. Warning issued by the International Energy Agency

    Energy Technology Data Exchange (ETDEWEB)

    Montbrial, T. de [Areva, Paris (France); Moore, P. [Greenspirit Strategies Ltd, Vancouver (Canada); Cambell, N. [Greenpeace (Canada)

    2007-07-01

    This issue of Alternatives newsletter put the question of energy supplies security. The unequal distribution of the world's energy resources raises the problem of energy independence and the security of supply. This question is particularly pertinent for Europe which, along with the Far East, possesses only a meager share of the planet's store of fossil fuels. Europe must learn how to live with its energy dependency, knowing that independence is an unrealistic objective in a world built on the interdependence of trade. The world's energy system is vulnerable to disruptions in supply and to geopolitical tensions. Given this context of instability, how can the security of supply and energy independence be increased? The challenge for western countries with few fossil fuel resources is to secure reliable supply while reducing energy dependency. One solution consists in diversifying power generation sources to lower dependency on oil and gas. The nuclear question is analyzed through the different point of views of Greenpeace and Greenspirit Strategies. Greenpeace refuses even the slightest involvement of nuclear power and considers that energy efficiency and renewable technologies are the only solution to both global warming and energy questions. On the other hand, Greenspirit Strategies sees nuclear power, combined with increased efforts to develop renewable energies, playing an essential role in the sustainable production of electricity. A last article devoted to the World Energy Outlook 2006 - the report published by the International Energy Agency - presents the hypotheses advanced by the Agency regarding future energy supply and its recommendations for counteracting a scenario for 2030 that is, to say the least, very alarming.

  17. The condition monitoring system of turbine system components for nuclear power plants

    International Nuclear Information System (INIS)

    Ono, Shigetoshi

    2013-01-01

    The thermal and nuclear power plants have been imposed a stable supply of electricity. To certainly achieve this, we built the plant condition monitoring system based on the heat and mass balance calculation. If there are some performance changes on the turbine system components of their power plants, the heat and mass balance of the turbine system will change. This system has ability to detect the abnormal signs of their components by finding the changes of the heat and mass balance. Moreover we note that this system is built for steam turbine cycle operating with saturated steam conditions. (author)

  18. Centralized operation and monitoring system for nuclear power plants

    International Nuclear Information System (INIS)

    Kudo, Mitsuru; Sato, Hideyuki; Murata, Fumio

    1988-01-01

    According to the prospect of long term energy demand, in 2000, the nuclear power generation facilities in Japan are expected to take 15.9% of the total energy demand. From this fact, it is an important subject to supply nuclear power more stably, and in the field of instrumentation and control, many researches and developments and the incessant effort of improvement have been continued. In the central operation and monitoring system which is the center of the stable operation of nuclear power plants, the man-machine technology aiding operators by electronic and computer application technologies has been positively developed and applied. It is considered that hereafter, for the purpose of rationally heightening the operation reliability of the plants, the high quality man-machine system freely using the most advanced technologies such as high reliability digital technology, optical information transmission, knowledge engineering and so on is developed and applied. The technical trend of operation and monitoring system, the concept of heightening operation and monitoring capability, the upgrading of operation and monitoring system, and the latest operation, monitoring and control systems for nuclear power plants and waste treatment facilities are described. (K.I.)

  19. Scenario analysis on future electricity supply and demand in Japan

    International Nuclear Information System (INIS)

    Zhang, Qi; Ishihara, Keiichi N.; Mclellan, Benjamin C.; Tezuka, Tetsuo

    2012-01-01

    Under continuing policies of CO 2 emissions reduction, it is crucial to consider scenarios for Japan to realize a safe and clean future electricity system. The development plans for nuclear power and renewable energy - particularly solar and wind power - are being reconsidered in light of the Fukushima nuclear accident. To contribute to this, in the present study, three electricity supply scenarios for 2030 are proposed according to different future nuclear power development policies, and the maximum penetration of renewable energy generation is pursued. On the other side of the equation, three electricity demand scenarios are also proposed considering potential energy saving measures. The purpose of the study is to demonstrate quantitatively the technological, economic and environmental impacts of different supply policy selections and demand assumptions on future electricity systems. The scenario analysis is conducted using an input–output hour-by-hour simulation model subject to constraints from technological, economic and environmental perspectives. The obtained installed capacity mix, power generation mix, CO 2 emissions, and generation cost of the scenarios were inter-compared and analyzed. The penetration of renewable energy generation in a future electricity system in Japan, as well as its relationship with nuclear power share was uncovered. -- Highlights: ► Scenario analysis is conducted on future electricity systems under different supply policies and demand assumptions. ► Scenario analysis is conducted using a input–output hour-by-hour simulation model for real-time demand-supply balance. ► The technological, economic and environmental impacts of supply policies and demand assumptions on future electricity systems are studied. ► The maximum penetration of renewable energy generation is pursued in the scenario analysis using the hour-by-hour simulation. ► The relationship between the penetration levels of renewable energy and nuclear power

  20. Simulation and study on reactivity disturbs dynamic character of HTR-10 nuclear power system

    International Nuclear Information System (INIS)

    Huang Xiaojin; Feng Yuankun

    2002-01-01

    In order to not only know 10 MW High Temperature Gas Cooled Reactor (HTR-10) nuclear power system's dynamic character more deeply but also to satisfy requirements of control system's design and analysis, the dynamic model of HTR-10 nuclear power system is established on the basis of dynamic model of HTR-10 nuclear system, which supplies turbine and generate electricity system model. Using this model, system's main variables' dynamic processes are simulated when control rod takes step reactivity disturb. The concussive progresses which is caused by reactivity disturb are analyzed. The results indicate that fuel temperature changing more slowly than nuclear power makes reactivity negative feedback not to restrain power changing, and then power concussive progress comes to being

  1. Nuclear reactors. Use of the protection system for non-safety purposes (International Electrotechnical Commission Standard Publication 639:1979)

    International Nuclear Information System (INIS)

    Stefanik, J.

    1996-01-01

    This standard applies to the protection system of a nuclear reactor and, more especially, to all interconnections between a reactor protection system (as defined and explained in International Electrotechnical Commission Publication 231 A, first supplement to Publication 231, General Principles of Nuclear Reactor Instrumentation) and all other systems and equipment not part of the protection system, except: a) the physical connection between sensors of the protection system and the physical variables that they monitor, such as for example, thermo wells, moderating medium for neutron sensors, etc.; b) the electrical connection between the protection system and the reactor control rods or other safety mechanism; c) the electrical and pneumatic connections to the power distribution system (mains) and pneumatic supplies that supply power to the protection system. Although many clauses relate to all reactor protection systems, this standard applies mainly to protection systems in nuclear power reactors

  2. Nuclear power and heating plants in the electric power system. Part I

    International Nuclear Information System (INIS)

    Kalincik, L.

    1975-01-01

    Procedures used and results obtained in the following works are described: Incorporation of the nuclear power plants in the power system in the long term perspective; physical limitations on the WWER 440 reactor power changes during fuel campaigns; evaluation of the consumption and start-up characteristics of WWER type nuclear power plants (2x440 MWe); evaluation of refuelling campaigns distribution of nuclear power plant units with regard to comprehensive control properties of nuclear power plants; the possibilities are investigated of the utilization of the WWER type reactor for heat supply in Czechoslovakia. (author)

  3. Nuclear and intermittent renewables: Two compatible supply options? The case of the French power mix

    International Nuclear Information System (INIS)

    Cany, Camille; Mansilla, Christine; Costa, Pascal da; Mathonnière, Gilles; Duquesnoy, Thierry; Baschwitz, Anne

    2016-01-01

    The complementary features of low-carbon power sources are a central issue in designing energy transition policies. The French current electricity mix is characterised by a high share of nuclear power which equalled 76% of the total electric production in 2015. With the increase in intermittent renewable sources, nuclear flexibility is examined as part of the solution to balance electricity supply and demand. Our proposed methodology involves designing scenarios with nuclear and intermittent renewable penetration levels, and developing residual load duration curves in each case. The load modulation impact on the nuclear production cost is estimated. This article shows to which extent the nuclear annual energy production will decrease with high shares of intermittent renewables (down to load factors of 40% for proactive assumptions). However, the production cost increase could be compensated by progressively replacing the plants. Moreover, incentives are necessary if nuclear is to compete with combined-cycle gas turbines as its alternative back-up option. In order to reconcile the social planner with plant operator goals, the solution could be to find new outlets rather than reducing nuclear load factors. Nuclear flexibility could then be considered in terms of using its power to produce heat or hydrogen. - Highlights: •Nuclear flexibility is examined to balance the system with high renewables share. •Impacts of wind and solar shares on the nuclear load factor and LCOE are assessed. •Nuclear fleet replacement must be progressive to ensure competitive load-following. •Incentives are needed for nuclear to compete with CCGT gas back-up. •We recommend considering nuclear flexibility through the power use.

  4. Second strategic energy report of the European Union - more security of supply with nuclear power

    International Nuclear Information System (INIS)

    Heller, W.

    2008-01-01

    On November 13, 2008, the EU Commission presented the Second Strategic Energy Report. The Report was supplemented by one proposed directive each on the security of gas supply and on oil stockpiling, by a multitude of measures to improve energy efficiency, and by 2 communications by the Commission on offshore wind energy and the nuclear program of the EU. The Commission attaches strategic importance in securing energy supply to the domestic energy resources, renewables, coal, and nuclear power. Moreover, the Commission assigns to the use of nuclear power an important role in the transition to an economy causing only a minimum of CO 2 emissions. The updated nuclear program contains these proposals: - The most up-to-date technology is to be employed in the construction of new reactors, and - the highest standards of nuclear safety are to be applied. - The diverse licensing conditions and procedures currently existing in the member states are to be harmonized. A few days earlier, the Nuclear Energy Agency (NEA) of OECD had presented the 2008 Nuclear Energy Outlook in which the points raised by the EU Commission are outlined in the same sense for the OECD member countries. Germany clearly continues to be in an isolated position worldwide in opting out of the use of nuclear power. This raises the question when and in what way political majorities may again be found which would prevent the enforcement of laws in the interest of phasing out nuclear power, and get rid of the irrational blockages in spent fuel and nuclear waste management. (orig.)

  5. Studies of breakeven prices and electricity supply potentials of nuclear fusion by a long-term world energy and environment model

    International Nuclear Information System (INIS)

    Tokimatsu, K.; Asaoka, Y.; Okano, K.; Yoshida, T.; Hiwatari, R.; Konishi, S.; Nishio, S.; Fujino, J.; Ogawa, Y.; Yamaji, K.

    2002-01-01

    In response to social demand, this paper investigates the breakeven price (BP) and potential electricity supply of nuclear fusion energy in the 21st century by means of a world energy and environment model. We set the following objectives in this paper: (i) to reveal the economics of the introduction conditions of nuclear fusion; (ii) to know when tokamak-type nuclear fusion reactors are expected to be introduced cost-effectively into future energy systems; (iii) to estimate the share in 2100 of electricity produced by the presently designed reactors that could be economically selected in the year. The model can give in detail the energy and environment technologies and price-induced energy saving, and can illustrate optimal energy supply structures by minimizing the costs of total discounted energy systems at a discount rate of 5%. The following parameters of nuclear fusion were considered: cost of electricity (COE) in the nuclear fusion introduction year, annual COE reduction rates, regional introduction year, and regional nuclear fusion capacity projection. The investigations are carried out for three nuclear fusion projections one of which includes tritium breeding constraints, four future CO 2 concentration constraints, and technological assumptions on fossil fuels, nuclear fission, CO 2 sequestration, and anonymous innovative technologies. It is concluded that: (1) the BPs are from 65 to 125 mill kW -1 h -1 depending on the introduction year of nuclear fusion under the 550 ppmv CO 2 concentration constraints; those of a business-as-usual (BAU) case are from 51 to 68 mill kW -1 h -1 . Uncertainties resulting from the CO 2 concentration constraints and the technological options influenced the BPs by plus/minus some 10-30 mill kW -1 h -1 , (2) tokamak-type nuclear fusion reactors (as presently designed, with a COE range around 70-130 mill kW -1 h -1 ) would be favourably introduced into energy systems after 2060 based on the economic criteria under the 450 and

  6. Studies of breakeven prices and electricity supply potentials of nuclear fusion by a long-term world energy and environment model

    Science.gov (United States)

    Tokimatsu, K.; Asaoka, Y.; Konishi, S.; Fujino, J.; Ogawa, Y.; Okano, K.; Nishio, S.; Yoshida, T.; Hiwatari, R.; Yamaji, K.

    2002-11-01

    In response to social demand, this paper investigates the breakeven price (BP) and potential electricity supply of nuclear fusion energy in the 21st century by means of a world energy and environment model. We set the following objectives in this paper: (i) to reveal the economics of the introduction conditions of nuclear fusion; (ii) to know when tokamak-type nuclear fusion reactors are expected to be introduced cost-effectively into future energy systems; (iii) to estimate the share in 2100 of electricity produced by the presently designed reactors that could be economically selected in the year. The model can give in detail the energy and environment technologies and price-induced energy saving, and can illustrate optimal energy supply structures by minimizing the costs of total discounted energy systems at a discount rate of 5%. The following parameters of nuclear fusion were considered: cost of electricity (COE) in the nuclear fusion introduction year, annual COE reduction rates, regional introduction year, and regional nuclear fusion capacity projection. The investigations are carried out for three nuclear fusion projections one of which includes tritium breeding constraints, four future CO2 concentration constraints, and technological assumptions on fossil fuels, nuclear fission, CO2 sequestration, and anonymous innovative technologies. It is concluded that: (1) the BPs are from 65 to 125 mill kW-1 h-1 depending on the introduction year of nuclear fusion under the 550 ppmv CO2 concentration constraints; those of a business-as-usual (BAU) case are from 51 to 68 mill kW-1h-1. Uncertainties resulting from the CO2 concentration constraints and the technological options influenced the BPs by plus/minus some 10 30 mill kW-1h-1, (2) tokamak-type nuclear fusion reactors (as presently designed, with a COE range around 70 130 mill kW-1h-1) would be favourably introduced into energy systems after 2060 based on the economic criteria under the 450 and 550 ppmv CO2

  7. Electrical power supply and controls for a remotely operated glass melter for nuclear waste

    International Nuclear Information System (INIS)

    Haideri, A.Q.

    1985-01-01

    An electrical power supply, controls and instruments used for a joule heated glass melter for nuclear waste are discussed. Remotely replaceable interconnection wiring assemblies for power, controls and instruments are also described

  8. Supply system with microprocessor control for electron gun

    International Nuclear Information System (INIS)

    Duplin, N.I.; Sergeev, N.N.

    1988-01-01

    Precision supply system for electron gun used in Auger-spectrometer is described. The supply system consists of control and high-voltage parts, made as separate units. Supply high-voltage unit includes system supply module, filament module to supply electron gun cathode and 6 high-volt modules to supply accelerating, modulating and three focusing electrodes of the gun. High-voltage modules have the following characteristics: U-(100-1000)V output voltage, 5x10 -5 U stability, 10 -5 xU pulsation amplitude, J-(0-5)A filament current change range at 10 -4 xJ stability. Control unit including microprocessor, timer and storage devices forms control voltage for all modules and regulates voltage and current of filament at electrodes

  9. Reliability evaluation of power supply and distribution for special heat removal systems in nuclear power stations

    International Nuclear Information System (INIS)

    Jazbec, D.

    1982-01-01

    An example of the power supply and distribution of a Special Emergency Heat Removal System (SEHR) shows how an engineering organization may, with the aid of the analytical method of min-cut sets optimize the system reliability. Herein are given the necessary simple calculation methods. (Auth.)

  10. NuDat system for access to nuclear data

    International Nuclear Information System (INIS)

    Dunford, C.L.; Kinsey, R.R.

    1998-01-01

    The NuDat program provides a user with access to nuclear properties and to some nuclear reaction data. The program operates on DEC VMS operating systems and on PC's with Microsoft operating systems. The program has four user interfaces, all having the same content and functionality. These interfaces are Web, Video and Sequential for VMS. The PC interface is identical to the VMS Video interface. Forms are used to supply the type of data the user desires, the retrieval parameters, the output format, and the sort order of the data. The program and associated database is used in basic research, particularly for the systematic study of nuclear properties. It is also a useful tool for applied research to identify radiations from radionuclides contained in environmental samples, or from those produced by neutron or charged particle activation. The NuDat database is derived from several databases maintained by the National Nuclear Data Center. The databases are the Adopted Levels and Gammas data sets from ENSDF, the Nuclear Wallet Cards, Decay Radiations derived from ENSDF decay data sets processed by RADLIST, and Thermal Neutron Cross Sections

  11. Expected role of nuclear science and technology to support the sustainable supply of energy in Indonesia

    International Nuclear Information System (INIS)

    Soentono, Soedyartomo; Aziz, Ferhat

    2008-01-01

    Energy resources are available in Indonesia but small per capita. The increase of oil price and its reserve depletion rate dictates to decrease the oil consumption. Therefore, it is imperative to increase the shares of other fossils as well as the new and renewable sources of energy in various energy sectors substituting the oil. The introduction of nuclear power plant becomes more indispensable, although the share is to be small but significantly important for electric generation in Java-Madura-Bali grid. Nuclear technology can have also important role enabling the increase of the shares of renewable, e.g. geothermal, hydro and bio-fuels as well as fossil energies to meet more sustainable energy mix sufficing the energy demand to attain intended economic and population growths while maintaining the environment. The first introduced nuclear power plant is to be the proven ones, but the innovative nuclear energy systems being developed by various countries will eventually also be partially employed to further improve the sustainability. The nuclear science and technology are to be symbiotic and synergistic to other sources of energy to enhance the sustainable supply of energy. (author)

  12. International co-operation in the supply of nuclear fuel and fuel cycle services

    International Nuclear Information System (INIS)

    Sievering, N.F. Jr.

    1977-01-01

    Recent changes in the United States' nuclear policy, in recognition of the increased proliferation risk, have raised questions of US intentions in international nuclear fuel and fuel-cycle service co-operation. This paper details those intentions in relation to the key elements of the new policy. In the past, the USA has been a world leader in peaceful nuclear co-operation with other nations and, mindful of the relationships between civilian nuclear technology and nuclear weapon proliferation, remains strongly committed to the Non-Proliferation Treaty, IAEA safeguards and other elements concerned with international nuclear affairs. Now, in implementing President Carter's nuclear initiatives, the USA will continue its leading role in nuclear fuel and fuel-cycle co-operation in two ways, (1) by increasing its enrichment capacity for providing international LWR fuel supplies and (2) by taking the lead in solving the problems of near and long-term spent fuel storage and disposal. Beyond these specific steps, the USA feels that the international community's past efforts in controlling the proliferation risks of nuclear power are necessary but inadequate for the future. Accordingly, the USA urges other similarly concerned nations to pause with present developments and to join in a programme of international co-operation and participation in a re-assessment of future plans which would include: (1) Mutual assessments of fuel cycles alternative to the current uranium/plutonium cycle for LWRs and breeders, seeking to lessen proliferation risks; (2) co-operative mechanisms for ensuring the ''front-end'' fuel supply including uranium resource exploration, adequate enrichment capacity, and institutional arrangements; (3) means of dealing with short-, medium- and long-term spent fuel storage needs by means of technical co-operation and assistance and possibly establishment of international storage or repository facilities; and (4) for reprocessing plants, and related fuel

  13. Latest nuclear monitoring instrumentation and control system and its planned application

    International Nuclear Information System (INIS)

    Kawakami, Seishiro; Sato, Toshifumi; Ikeda, Jun

    2002-01-01

    With the recent rapid progress made in electronic devices used in digital monitoring and control systems, Toshiba has developed special-purpose digital monitoring equipment and human-machine interface equipment that meet the special requirement of high reliability and long-term supply and maintainability for nuclear power plants, and is scheduled to apply these new products to actual nuclear power plants. Moreover, for the in-core sensor, which is a special-purpose product for nuclear power plants, Toshiba has been developing a new local power range monitor (LPRM) detector as the comprehensive result of improvements made up to now, and has developed the first domestic gamma-thermo (GT) detector as a pivot of the next-generation neutron monitoring system. (author)

  14. Remote multiplexing system application to a nuclear generating station--An update

    International Nuclear Information System (INIS)

    Mazzoni, O.S.; Cava, A.L.; Bijoor, G.D.; Wiitala, M.F.

    1979-01-01

    Washington Public Power Supply System's Nuclear Power Plant WNP-2 is a 1200 MW, boiling water reactor (BWR) nuclear generating facility now under construction at Hanford, Washington. An early study indicated that substantial savings in cost could be obtained by the substitution of the Remote Multiplexing System (RMS) for the control and signal wiring between the Control Building and the outside facilities, which required long cable runs. It is a high speed, data system providing time-sharing digital communication. The purpose of this paper is to give the details of the RMS used in the WNP-2 project. It discusses the qualification requirements for Class IE systems and includes the description of the tests on the system

  15. Energy forum 2005: Nuclear power - in competition with sustainable energy supply in Europe. Lectures

    International Nuclear Information System (INIS)

    2005-01-01

    The forum of energy for future organized on 29st September 2005 the annual Energy Forum at Berlin. The Energy Forum 2005 dealt with nuclear power in competition with sustainable energy supply in Europe and didn't only give their members the possibility of a discussion on this actual theme. Furtheron demanding aims on CO2-reduction, increased raw material- and energy prices as the construction of a new Finnish nuclear power plant have countries moved to evaluate again the future-oriented role of nuclear power. (orig./GL)

  16. Methods of thermal power extraction from nuclear sources for meeting the consumer system demands

    International Nuclear Information System (INIS)

    Sellej, J.

    1985-01-01

    The technical design is discussed of heat extraction from nuclear power plants and heating plants. Variant technical designs are discussed of hot water and steam supply, including the basic aspects of nuclear safety. Hot water supplies are technically provided by heat exchanger units connected to turbines, or by heating turbines. The advantages and disadvantages of the two designs are discussed. The possibility of heat extraction by steam from the nuclear power plant is provided by steam exchangers, i.e., steam exchanger cascades, the so-called inserted steam circuit. Supplies of steam from nuclear sources, as against supplies of hot water have not yet been technically resolved with regard to safety, design and economic benefit. Nuclear heating plants have also been designed for hot water supply, but not yet for steam supply. (Pu)

  17. Investigation of thermochemical biorefinery sizing and environmental sustainability impacts for conventional supply system and distributed pre-processing supply system designs

    Energy Technology Data Exchange (ETDEWEB)

    David J. Muth, Jr.; Matthew H. Langholtz; Eric C. D. Tan; Jacob J. Jacobson; Amy Schwab; May M. Wu; Andrew Argo; Craig C. Brandt; Kara G. Cafferty; Yi-Wen Chiu; Abhijit Dutta; Laurence M. Eaton; Erin M. Searcy

    2014-08-01

    The 2011 US Billion-Ton Update estimates that by 2030 there will be enough agricultural and forest resources to sustainably provide at least one billion dry tons of biomass annually, enough to displace approximately 30% of the country's current petroleum consumption. A portion of these resources are inaccessible at current cost targets with conventional feedstock supply systems because of their remoteness or low yields. Reliable analyses and projections of US biofuels production depend on assumptions about the supply system and biorefinery capacity, which, in turn, depend upon economic value, feedstock logistics, and sustainability. A cross-functional team has examined combinations of advances in feedstock supply systems and biorefinery capacities with rigorous design information, improved crop yield and agronomic practices, and improved estimates of sustainable biomass availability. A previous report on biochemical refinery capacity noted that under advanced feedstock logistic supply systems that include depots and pre-processing operations there are cost advantages that support larger biorefineries up to 10 000 DMT/day facilities compared to the smaller 2000 DMT/day facilities. This report focuses on analyzing conventional versus advanced depot biomass supply systems for a thermochemical conversion and refinery sizing based on woody biomass. The results of this analysis demonstrate that the economies of scale enabled by advanced logistics offsets much of the added logistics costs from additional depot processing and transportation, resulting in a small overall increase to the minimum ethanol selling price compared to the conventional logistic supply system. While the overall costs do increase slightly for the advanced logistic supply systems, the ability to mitigate moisture and ash in the system will improve the storage and conversion processes. In addition, being able to draw on feedstocks from further distances will decrease the risk of biomass supply to

  18. Political and legal problems of international nuclear supply agreements: the Euratom experience

    International Nuclear Information System (INIS)

    Allen, D.W.

    1983-01-01

    This paper analyses the Chapters in the Euratom Treaty which are relevant to uranium supply agreements and the European Community's powers in international relations as conferred by the Treaty. It also examines the agreements concluded by Euratom with the US, Canada and Australia respectively with emphasis on their nuclear non-proliferation aspects. (NEA) [fr

  19. Nuclear Energy System Department annual report. (April 1, 2002 - March 31, 2003)

    International Nuclear Information System (INIS)

    Nakajima, Hajime; Shibata, Keiichi; Kugo, Teruhiko

    2003-09-01

    This report summarizes the research and development activities in the Department of Nuclear Energy System during the fiscal year of 2002 (April 1, 2002 - March 31, 2003). The Department has carried out researches and developments (R and Ds) of innovative nuclear energy system and their related fundamental technologies to ensure the long-term energy supply in Japan. The report deals with the R and Ds of an innovative water reactor, called Reduced-Moderation Water Reactor (RMWR), which has the capability of multiple recycling and breeding of plutonium using light water reactor technologies. In addition, as basic studies and fundamental researches of nuclear energy system in general, described are intensive researches in the fields of reactor physics, thermal-hydraulics, nuclear data, nuclear fuels, and materials. These activities are essential not only for the R and Ds of innovative nuclear energy systems but also for the improvement of safety and reliability of current nuclear energy systems. The maintenance and operation of reactor engineering facilities belonging to the Department support experimental activities. The activities of the research committees to which the Department takes a role of secretariat are also summarized. (author)

  20. Aspirations of Jordanians to use nuclear energy for electric power supply

    International Nuclear Information System (INIS)

    Al-Jaowny, W.; Al-mur, A.

    1993-01-01

    Despite the continuous efforts that exerted by the concerned authorities in Jordan for discovering and local source of energy yet it is still very limited, moreover, what is already known such as oil shale is still not economical to be utilized in the near future. And in light of the continuous increase in energy demand, Jordan looked for the study of different alternatives to cover its electrical energy, one of which is the electrical interconnection where the chance will be available for building big and highly economical stations such as nuclear to operate within the interconnected network and supply the requesting areas with minimum cost. And with the continuous expectations in the increase of oil prices all indications lead for the entry in nuclear energy. In this field Jordan had taken different actions to prepare itself for the use of nuclear energy where, a nuclear energy department was established and issued different laws related to the use of this energy, beside defining planned steps which include developing existing projects and activities, putting plans to establish national research center and develop experience and local industry to be ready for the future management of nuclear power station. (author)

  1. Accelerator-control-system interface for intelligent power supplies

    International Nuclear Information System (INIS)

    Cohen, S.

    1992-01-01

    A number of high-current high-precision magnet power supplies have been installed at the proton storage ring at the Los Alamos National Laboratory Accelerator Complex. The units replace existing supplies, powering large dipole magnets in the ring. These bending magnets require a high-current supply that is precise and stable. The control and interface design for these power supplies represents a departure from all others on-site. The supplies have sophisticated microprocessor control on-board and communicate with the accelerator control system via RS-422 (serial communications). The units, built by Alpha Scientific Electronics, Hayward, CA use a high-level ASCII control protocol. The low-level ''front-end'' software used by the accelerator control system has been written to accommodate these new devices. They communicate with the control system through a terminal server port connected to the site-wide ethernet backbone. Details of the software implementation for the analog and digital control of the supplies through the accelerator control system will be presented

  2. System Dynamics Modeling for Supply Chain Information Sharing

    Science.gov (United States)

    Feng, Yang

    In this paper, we try to use the method of system dynamics to model supply chain information sharing. Firstly, we determine the model boundaries, establish system dynamics model of supply chain before information sharing, analyze the model's simulation results under different changed parameters and suggest improvement proposal. Then, we establish system dynamics model of supply chain information sharing and make comparison and analysis on the two model's simulation results, to show the importance of information sharing in supply chain management. We wish that all these simulations would provide scientific supports for enterprise decision-making.

  3. Review of nuclear new build in relation to project structure, supply chain and financing - 15106

    International Nuclear Information System (INIS)

    Keppler, J.H.; Cometto, M.

    2015-01-01

    The construction of a new nuclear power plant is a major industrial project involving a number of complex economic, technical and regulatory challenges. This article focuses on 2 of the most important among them: first, sustainable financing which is primarily a function of interest rates and the stability of electricity prices and secondly, the management of a complex construction process and its supply chain. The analysis shows the much stronger dependence of nuclear energy on the stability of electricity prices when compared with a gas plant of the same size. Nevertheless the study underlines that at debt ratios below 60%, the risk for a debt-investor in a nuclear project is rather limited even for large electricity and permanent price fall. There exist a wide spectrum of different options for sharing the responsibilities between the ultimate operators of a nuclear power plant and the principal supplier. 3 main categories of contract are used for the construction of NPPs: the turnkey approach, the split-package approach and the multi-contract approach.In construction, where the emergence of a competitive, global supply chain is not yet ensured, the convergence of nuclear engineering codes and quality standards, as well as regulatory harmonisation remain a key step to promote both competition and public confidence

  4. Survey of sources of manpower supply for the nuclear power industry

    International Nuclear Information System (INIS)

    1981-01-01

    The following is a report of a survey designed to determine sources of manpower supply available to the Nuclear Power Industry. The survey is part of a larger research effort which is also designed to investigate occupational employment and training in the Nuclear Power Industry and competing sources of demand for technically qualified manpower. The results of those other studies have been published separately and are available upon request. This report includes a brief discussion of the background of the study, the research methods employed, the results obtained, and some implications of those findings. The appendices contain copies of the questionnaires used in the survey as well as some additional related data

  5. Argentina's operator support systems in nuclear power plants

    International Nuclear Information System (INIS)

    Goldstein, M.; Palamidessi, H.

    1996-01-01

    The development of operator support systems for nuclear power plants started in Argentina a few years ago. Four systems are at present deployed or under development. The participation of utility personnel in the co-ordinated research program has helped in revising the current experience and in selecting and specifying the systems to be developed and the resources needed for their implementation. Main efforts will be aimed to the selection of those systems that can be more easily implemented, to improve the data retrieval and handling, to develop diverse supplies of software products and to promote the understanding of support systems among the potential end users. (author). 12 refs

  6. Nuclear energy in the operation of the spanish electric system

    International Nuclear Information System (INIS)

    Atienza, L.

    2008-01-01

    Nuclear energy plays a basic role in electricity production in Spain. Its high availability rate, the predictability of its fuel recharges, its high operational reliability, its geographical location, the stability of its costs, with its fuel having low weight in the cost structure, the security of supply that the possibility of storing its fuel on-site in the power plant gives and the absence of CO 2 emissions are some of the advantages nuclear energy presents. Its stiffness for demand variations, its sudden disconnections, which are infrequent but with high impact on System Operation, the social perception and nuclear waste management must also be weighted up. (Author)

  7. Combined prediction model for supply risk in nuclear power equipment manufacturing industry based on support vector machine and decision tree

    International Nuclear Information System (INIS)

    Shi Chunsheng; Meng Dapeng

    2011-01-01

    The prediction index for supply risk is developed based on the factor identifying of nuclear equipment manufacturing industry. The supply risk prediction model is established with the method of support vector machine and decision tree, based on the investigation on 3 important nuclear power equipment manufacturing enterprises and 60 suppliers. Final case study demonstrates that the combination model is better than the single prediction model, and demonstrates the feasibility and reliability of this model, which provides a method to evaluate the suppliers and measure the supply risk. (authors)

  8. Modeling sustainability in renewable energy supply chain systems

    Science.gov (United States)

    Xie, Fei

    This dissertation aims at modeling sustainability of renewable fuel supply chain systems against emerging challenges. In particular, the dissertation focuses on the biofuel supply chain system design, and manages to develop advanced modeling framework and corresponding solution methods in tackling challenges in sustaining biofuel supply chain systems. These challenges include: (1) to integrate "environmental thinking" into the long-term biofuel supply chain planning; (2) to adopt multimodal transportation to mitigate seasonality in biofuel supply chain operations; (3) to provide strategies in hedging against uncertainty from conversion technology; and (4) to develop methodologies in long-term sequential planning of the biofuel supply chain under uncertainties. All models are mixed integer programs, which also involves multi-objective programming method and two-stage/multistage stochastic programming methods. In particular for the long-term sequential planning under uncertainties, to reduce the computational challenges due to the exponential expansion of the scenario tree, I also developed efficient ND-Max method which is more efficient than CPLEX and Nested Decomposition method. Through result analysis of four independent studies, it is found that the proposed modeling frameworks can effectively improve the economic performance, enhance environmental benefits and reduce risks due to systems uncertainties for the biofuel supply chain systems.

  9. Assessment of industrial energy options based on coal and nuclear systems

    International Nuclear Information System (INIS)

    Anderson, T.D.; Bowers, H.I.; Bryan, R.H.; Delene, J.G.; Hise, E.C.; Jones, J.E. Jr.; Klepper, O.H.; Reed, S.A.; Spiewak, I.

    1975-07-01

    Industry consumes about 40 percent of the total primary energy used in the United States. Natural gas and oil, the major industrial fuels, are becoming scarce and expensive; therefore, there is a critical national need to develop alternative sources of industrial energy based on the more plentiful domestic fuels--coal and nuclear. This report gives the results of a comparative assessment of nuclear- and coal-based industrial energy systems which includes technical, environmental, economic, and resource aspects of industrial energy supply. The nuclear options examined were large commercial nuclear power plants (light-water reactors or high-temperature gas-cooled reactors) and a small [approximately 300-MW(t)] special-purpose pressurized-water reactor for industrial applications. Coal-based systems selected for study were those that appear capable of meeting environmental standards, especially with respect to sulfur dioxide; these are (1) conventional firing using either low- or high-sulfur coal with stack-gas scrubbing equipment, (2) fluidized-bed combustion using high-sulfur coal, (3) low- and intermediate-Btu gas, (4) high-Btu pipeline-quality gas, (5) solvent-refined coal, (6) liquid boiler fuels, and (7) methanol from coal. Results of the study indicated that both nuclear and coal fuel can alleviate the industrial energy deficit resulting from the decline in availability of natural gas and oil. However, because of its broader range of application and relative ease of implementation, coal is expected to be the more important substitute industrial fuel over the next 15 years. In the longer term, nuclear fuels could assume a major role for supplying industrial steam. (U.S.)

  10. Introduction of Electrical System Simulation and Analysis Used in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Sang Hak; Jeong, Woo Sung

    2015-01-01

    The purpose of this paper is to introduce the simulation methods and tools to analyse and predict the performance of the electric power distribution system for nuclear power plants (NPPs) in Korea. Electrical System design engineers are to evaluate the load flow, bus voltage profiles, short circuit levels, motor starting, and fast bus transfer under various plant operating conditions and to verify the adequacy of power distribution System for a reliable power supply to plant loads under various disturbances which could jeopardize a safe and reliable operation of nuclear power plants. (authors)

  11. System effects of nuclear energy and renewables in low-carbon electricity Systems

    International Nuclear Information System (INIS)

    Keppler, J.H.; Gameron, R.; Cometto, M.

    2012-01-01

    Electricity produced by variable renewable energies significantly affects the economics of dispatchable power generators, in particular those of nuclear power, both in the short run and the long run; the outcome of these competing factors will depend on the amount of variable renewables being introduced, local conditions and the level of carbon prices. An assessment of grid-level system costs (including the costs for grid connection, extension and reinforcement, as well as the added costs for balancing and back-up, but excluding the financial costs of intermittency and the impacts on security of supply, the environment, siting and safety), reveals a considerable difference between those of dispatchable technologies and those of variable renewables. Using a common methodology and a broad array of country-specific data, the grid-level system costs for Finland, France, Germany, the Republic of Korea, the United Kingdom and the United States were calculated for nuclear, coal, gas, onshore wind, offshore wind and solar PV both at 10 pc and 30 pc penetration levels. Variable renewables are creating a market environment in which dispatchable technologies can no longer finance themselves through revenues in 'energy only' wholesale markets; this has serious implications for the security of electricity supplies. Four main policy recommendations are proposed

  12. Impact of Multilateral Approaches for Assurances of Nuclear Fuel Supply

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Han Myung; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Yang, M. H.; Oh, K. B.; Lee, K. S

    2007-12-15

    This study consists of 3 parts : analysis of the characteristics of the recent proposals for a nuclear fuel supply and the progress of them, responses from various sectors in the world, and measures for them. In response to recent proposals, majority of countries possessing sensitive nuclear fuel facilities are supportive in general. In contrast, many countries not possessing such facilities are reluctant about the proposals. To satisfy both parties, an ideal proposal could suggest measures to assure a non-proliferation as well as measures to acquire confidence from the so-called user nations. To get strong support from all countries concerned, the proposal should contain some critical elements such as clear attractiveness for a participation, equal opportunities for the participating countries, voluntarily in decision on a participation, and a gradual approach to remove any future obstacles encountered. The criteria to judge a legitimate need of a country for the introduction of nuclear fuel facilities should be prepared by a consensus. Compliance of a nonproliferation obligation, scale of an economy, and an energy security can be proposed as such criteria.

  13. Impact of Multilateral Approaches for Assurances of Nuclear Fuel Supply

    International Nuclear Information System (INIS)

    Lee, Han Myung; Lee, B. W.; Ko, H. S.; Ryu, J. S.; Yang, M. H.; Oh, K. B.; Lee, K. S.

    2007-12-01

    This study consists of 3 parts : analysis of the characteristics of the recent proposals for a nuclear fuel supply and the progress of them, responses from various sectors in the world, and measures for them. In response to recent proposals, majority of countries possessing sensitive nuclear fuel facilities are supportive in general. In contrast, many countries not possessing such facilities are reluctant about the proposals. To satisfy both parties, an ideal proposal could suggest measures to assure a non-proliferation as well as measures to acquire confidence from the so-called user nations. To get strong support from all countries concerned, the proposal should contain some critical elements such as clear attractiveness for a participation, equal opportunities for the participating countries, voluntarily in decision on a participation, and a gradual approach to remove any future obstacles encountered. The criteria to judge a legitimate need of a country for the introduction of nuclear fuel facilities should be prepared by a consensus. Compliance of a nonproliferation obligation, scale of an economy, and an energy security can be proposed as such criteria

  14. Nuclear science

    International Nuclear Information System (INIS)

    1989-01-01

    This fact sheet answers specific questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant number sign 1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  15. Nuclear science

    International Nuclear Information System (INIS)

    1989-04-01

    This report answers questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant No.1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  16. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Pilgrim Nuclear Power Station

    International Nuclear Information System (INIS)

    Selan, J.C.

    1982-01-01

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Pilgrim Nuclear Power Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  17. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

    This Safety Guide was prepared as part of the Nuclear Safety Standards programme for establishing Codes and Safety Guides relating to nuclear power plants (NPPs). The first edition of the present Safety Guide was developed in the early 1980s. The text has now been brought up-to-date, refined in several details and amended to include non-electrical diverse and independent power sources. This Guide applies to NPP for which the total power supply comprises a normal power supply and an emergency power supply (EPS), which may be electrical or a combination of electrical and non-electrical. The Guide provides general guidance for all types of EPS and specific guidance on the design safety requirements and the features of the electrical and non-electrical portions of the EPS. 9 figs, 2 tabs

  18. Burnout in a high heat flux boiling system with forced supply of liquid through a plane jet

    International Nuclear Information System (INIS)

    Katto, Yoshiro; Ishii, Kazunori.

    1978-01-01

    As for pool boiling, the non-dimensional formula for the burnout heat flux of a simple, basic boiling system has been obtained. On the other hand, in forced convection boiling, the studies on the burnout in forced flow boiling in a channel have been continued, but the derivation of a non-dimensional formula applicable generally is far away from the realization because the phenomena are too complex. Accordingly, in this study, the result of the experiment on the burnout of a boiling system to which liquid is supplied by the plane jet flowing out of a thin rectangular nozzle installed near the front edge of a rectangular heating surface is reported. The experimental apparatus is described, and the experiment was carried out in the ranges of two jet thicknesses at the nozzle outlet, two incident angles of jet and from 1.5 to 15 m/s of jet velocity. Burnout occurs under the situation of sufficiently developed nuclear boiling. A part of the liquid supplied from a plane jet is blown apart by the vapor blowing out of the nuclear boiling liquid layer covering the heating surface in the nuclear boiling with sufficiently developed high heat flux. However, the nuclear boiling liquid layer itself continues to exist on the heating surface till burnout occurs. Only the entering velocity of the plane jet affects burnout heat flux. (Kako, I.)

  19. Climate change benefits and energy supply benefits as determinants of acceptance of nuclear power stations: Investigating an explanatory model

    International Nuclear Information System (INIS)

    Visschers, Vivianne H.M.; Keller, Carmen; Siegrist, Michael

    2011-01-01

    Several countries are currently discussing whether they will rebuild their nuclear power stations in order to continue this type of energy production in the future. The public, with its own opinion about nuclear power stations, has an influential voice in this discussion. As a result, policy makers and nuclear scientists are interested in the public's perception of nuclear power and in what determines this perception. We therefore examined an explanatory model of the public's acceptance of nuclear power based on a telephone survey among a representative sample in Switzerland. The model included such factors as risk perception, benefit perception, affective feelings, and social trust. Moreover, we distinguished between two types of benefit perception: benefit for the climate and a secure energy supply. The model fitted very well to our data and explained acceptance very well. Acceptance was mainly influenced by perceived benefits for a secure energy supply and, to a lesser extent, both by perceived benefits for the climate and by risk perception. Affective feelings about nuclear power appeared to be a central factor in the model. Implications for communication about nuclear power stations and for further research are discussed. - Highlights: → Explanatory model of determinants of nuclear power acceptance was studied in the representative survey. → Perceived benefits for a secure energy supply had the largest influence on acceptance. → Perceived benefits for the climate seemed less influential on acceptance. → Affect had a central role in the explanatory model. → Implications for communication about nuclear power plants are discussed.

  20. Climate change benefits and energy supply benefits as determinants of acceptance of nuclear power stations: Investigating an explanatory model

    Energy Technology Data Exchange (ETDEWEB)

    Visschers, Vivianne H.M., E-mail: vvisschers@ethz.ch [ETH Zurich, Institute for Environmental Decisions (IED), Consumer Behavior, Universitaetsstrasse 22 CHN J 75.2, 8092 Zurich (Switzerland); Keller, Carmen; Siegrist, Michael [ETH Zurich, Institute for Environmental Decisions (IED), Consumer Behavior, Universitaetsstrasse 22 CHN J 75.2, 8092 Zurich (Switzerland)

    2011-06-15

    Several countries are currently discussing whether they will rebuild their nuclear power stations in order to continue this type of energy production in the future. The public, with its own opinion about nuclear power stations, has an influential voice in this discussion. As a result, policy makers and nuclear scientists are interested in the public's perception of nuclear power and in what determines this perception. We therefore examined an explanatory model of the public's acceptance of nuclear power based on a telephone survey among a representative sample in Switzerland. The model included such factors as risk perception, benefit perception, affective feelings, and social trust. Moreover, we distinguished between two types of benefit perception: benefit for the climate and a secure energy supply. The model fitted very well to our data and explained acceptance very well. Acceptance was mainly influenced by perceived benefits for a secure energy supply and, to a lesser extent, both by perceived benefits for the climate and by risk perception. Affective feelings about nuclear power appeared to be a central factor in the model. Implications for communication about nuclear power stations and for further research are discussed. - Highlights: > Explanatory model of determinants of nuclear power acceptance was studied in the representative survey. > Perceived benefits for a secure energy supply had the largest influence on acceptance. > Perceived benefits for the climate seemed less influential on acceptance. > Affect had a central role in the explanatory model. > Implications for communication about nuclear power plants are discussed.

  1. Energy costs and Portland water supply system

    Energy Technology Data Exchange (ETDEWEB)

    Elliott, W.M.; Hawley, R.P.

    1981-10-01

    The changing role of electrical energy on the Portland, Oregon, municipal-water-supply system is presented. Portland's actions in energy conservation include improved operating procedures, pump modifications, and modifications to the water system to eliminate pumping. Portland is implementing a small hydroelectric project at existing water-supply dams to produce an additional source of power for the area. Special precautions in construction and operation are necessary to protect the high quality of the water supply. 2 references, 7 figures.

  2. Systems thinking benefits in supply change management:an illustration of the viable systems model in a supply chain

    OpenAIRE

    Chronéer, Diana; Mirijamdotter, Anita

    2009-01-01

    Existing product development models are solely an organisational matter. They do not take into consideration the whole supply chain and its different actors. We investigate in this paper how Supply Chain Management (SCM) and Viable System Model (VSM) can support and create an effective use of information in product development and hence identify critical linkages in the supply chain. The aim is to introduce VSM as a framework that enable an analysis of company's supply chains and visualize vi...

  3. Production of concentrates for supplying a national nuclear electric program

    International Nuclear Information System (INIS)

    Delgado, C.M.

    An analysis was made of the yearly requirements of natural U to satisfy a nuclear power program in Mexico. On the basis of these requirements an evaluation was made of the concentrate production necessary to supply those needs. The lack of known commercial reserves to satisfy the concentrate needs is shown. An estimation is made of the costs for the discovery and exploitation of sufficient reserves. In evaluating the U needs and associated costs, three cases were considered: all BWR or PWR or HWR

  4. Maximising water supply system yield subject to multiple reliability ...

    African Journals Online (AJOL)

    Maximising water supply system yield subject to multiple reliability constraints via simulation-optimisation. ... Water supply systems have to satisfy different demands that each require various levels of reliability ... and monthly operating rules that maximise the yield of a water supply system subject to ... HOW TO USE AJOL.

  5. Thermal-CFD Analysis of Combined Solar-Nuclear Cycle Systems.

    Energy Technology Data Exchange (ETDEWEB)

    Fathi, Nima [Univ. of New Mexico, Albuquerque, NM (United States); McDaniel, Patrick [Univ. of New Mexico, Albuquerque, NM (United States); Vorobieff, Peter [Univ. of New Mexico, Albuquerque, NM (United States); de Oliveira, Cassiano [Univ. of New Mexico, Albuquerque, NM (United States); Rodriguez, Salvador B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Aleyasin, Seyed Sobhan [Univ. of Manitoba (Canada)

    2015-09-01

    The aim of this paper is evaluating the efficiency of a novel combined solar-nuclear cycle. CFD-Thermal analysis is performed to apply the available surplus heat from the nuclear cycle and measure the available kinetic energy of air for the turbine of a solar chimney power plant system (SCPPS). The presented idea helps to decrease the thermal pollution and handle the water shortage supply for water plant by replacing the cooling tower by solar chimney power plant to get the surplus heat from the available warm air in the secondary loop of the reactor. By applying this idea to a typical 1000 MW nuclear power plant with a 0.33 thermal efficiency, we can increase it to 0.39.

  6. A study on expert system applications for nuclear power plant

    International Nuclear Information System (INIS)

    Huh, Young Hwan; Kim, Kil Yoo; Kang, Soon Ju; Park, Nam Seok; Ryu, Chan Ho; Choi, In Seon; Chung, Young Moo; Chung, Tae Eon; Yim, Chang Jae; Lee, Yoon Sang.

    1990-01-01

    The objectives of this research are 1) to develop an expert system which can automatically evaluate eddy current (EC) signal during an eddy current test (ECT) of SG U tube inspection, 2) to build an effective data base management system for ECT data. By this expert system the reliability in EC signal evaluation can be improved, and the required man-power can be reduced. And this expert system can supply a stable ECT and contribute to a safe operation of the nuclear power plant. (author)

  7. The Management System for Nuclear Installations (Russian Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

  8. The Management System for Nuclear Installations Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a)To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b)As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c)To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a)Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b)Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c)Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d)Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e)Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear installation. (f

  9. Improved Management of Part Safety Classification System for Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Young; Park, Youn Won; Park, Heung Gyu; Park, Hyo Chan [BEES Inc., Daejeon (Korea, Republic of)

    2016-10-15

    As, in recent years, many quality assurance (QA) related incidents, such as falsely-certified parts and forged documentation, etc., were reported in association with the supply of structures, systems, components and parts to nuclear power plants, a need for a better management of safety classification system was addressed so that it would be based more on the level of parts . Presently, the Korean nuclear power plants do not develop and apply relevant procedures for safety classifications, but rather the safety classes of parts are determined solely based on the experience of equipment designers. So proposed in this paper is a better management plan for safety equipment classification system with an aim to strengthen the quality management for parts. The plan was developed through the analysis of newly introduced technical criteria to be applied to parts of nuclear power plant.

  10. Composite type nuclear power system

    International Nuclear Information System (INIS)

    Nakamoto, Koichiro.

    1993-01-01

    The present invention realizes a high thermal efficiency by heating steams at the exit of a steam generator of a nuclear power plant to high temperature by a thermal super-heating boiler. That is, a thermal superheating boiler is disposed between the steam generator and a turbogenerator to heat steams from the steam generator and supply them to the turbogenerator. In this case, it may be possible that feedwater superheating boiler pipelines to the steam generator are caused to pass through the thermal superheating boiler so that they also have a performance of heating feedwater. If the system of the present invention is used, it is possible to conduct base load operation by nuclear power and a load following operation by controlling the thermal superheating boiler. Further, a hydrogen producing performance is applied to the thermal superheating boiler to produce hydrogen when electric power load is lowered. An internally sustaining type operation method can be conducted of burning hydrogen by the superheating boiler upon increased electric power load. As a result, a power generation system which has an excellent economical property and can easily cope with the load following operation can be attained. (I.S.)

  11. Application of self-assessment in the nuclear fuel supply activities of Siemens AG

    International Nuclear Information System (INIS)

    Nilson, F.; Schaule, B.

    2000-01-01

    The quality of fuel assemblies supplied to our customers is defined by more than just their expected functionality (performance) during reactor operation and beyond but also by their cost (price) and the timeliness of their supply (including related services). This perspective implies a comprehensive view of the quality of business, - the same focus that the IAEA Code, Basic Requirement 9, addresses regarding management self-assessment. Siemens has adopted a comprehensive management philosophy in the Nuclear Fuels Business in the early Nineties under the header of 'TQM' that is similar to the one mentioned above. For this approach we found valuable guidance in the Business Excellence model of the European Foundation for Quality Management (EFQM) which is comparable to the self-assessment criteria listed by IAEA. In this contribution we are presenting examples and experiences of how such system of self-assessment and continuous improvement was implemented by senior management. Our experience of more than 6 years of TQM and 4 years of self-assessment yielded an increasing alignment and focus of our organization and all its members on the continuous improvement of our processes (business, management and support) - on the way to a learning organization. (author)

  12. The logistics and the supply chain in the Juzbado Nuclear Fuel Manufacturing Plant; Cadena logistica en la fabrica de elementos combustibles de Juzbado

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The paper describe the logistics and the supply chain in the Juzbado Nuclear Fuel Manufacturing Plant, located in Juzbado in the province of Salamanca. In the the article are described the principal elements in the supply chain and the difficulties of its management derived from the short period for the manufacturing of the nuclear fuel. It's also given a view in relation to the transportation by land sea of the nuclear components, uranium oxide powder and the manufactured fuel. The characteristics of the supply chain are determined by the plant production forecast, by the origin and high technology of the raw materials and by nuclear fuel delivery site locations. (Author)

  13. Systems approach to design of power supply to mines

    Energy Technology Data Exchange (ETDEWEB)

    Shul' ga, Yu I; Voloshko, A V

    1986-09-01

    Optimization of power supplies to underground coal mines in the USSR is evaluated. Systems analysis of power systems is discussed. Power system of a coal mine is treated as an element of the branch power system which forms a subsystem of the local and national power system. Design of a system for computerized control of power supplies to underground coal mines is evaluated. Elements of the system, control equipment, types of information stored and processed by the system as well as economic efficiency of using computerized control for power supply in underground mining are discussed. Recommendations for computer-aided design of power systems and use of computerized control systems for power supply in underground coal mining in the USSR are made.

  14. New water intake systems for thermal and nuclear power plants

    International Nuclear Information System (INIS)

    Ishchuk, T.B.; Samodel'nikov, B.T.

    1989-01-01

    Problems arising during design of water intake and spillway structures for the auxiliary water supply system of thermal and nuclear power plants connected with the provision of their reliable operation and with the effect on the temperature condition of reservoirs and their ecology are investigated. Design providing for the connection of intake channel and catch drain for a through (transition) channel and supplying a water transition flow by ejecting water outputs is suggested. The variant considered is effective for seas, lakes and reservoirs with adverse conditions for natural cooling and it is suitable for regions with seismicity up to 5-6 balls

  15. Modeling and simulation of the power demand and supply of a hydrothermal power generating system

    International Nuclear Information System (INIS)

    Pronini, R.A.

    1996-01-01

    Security of supply of electric energy is measured by the capacity to cover the energy demand and power of a supply grid. This coverage is important because the winter peak load period in Switzerland will become problematical in the near future. The objective of this research project is to analyze the ability of a power generating system to satisfy the power requirements of the corresponding supply network. The behaviour of the energy system in critical cases (loss of the largest generator, lack of available power from an external supplier or reduced capacity for energy storage) is tested for the present situation and for the rise in the annual load. The simulation of the load of the supply network is carried out by using a model developed for this project. This model is based on the analysis of half-hourly changes of load and on the statistical maximum values. The power generating system consists of nuclear generating units, hydro units with large reservoirs, run of the river installations and imported energy. Standby units such as gas turbines, spot market and coal-fired power stations are also available. Stochastic and deterministic energy and power models have been developed for the various power stations of the hydrothermal power system. In the case of nuclear power stations, a model has been developed on the basis of the output level, production losses and time and length of outages. The possible feeder streams of the run of the river installations and of the hydro units with a large reservoir are simulated using stochastic methods based on the historical values of the last 35 years. The commitment of the hydro units depends on the peak load requirements. The load and capacity over a period of several days and weeks have been simulated with stochastic models based on the Monte Carlo method and constantly (by half hour intervals) compared. In this manner each month can be simulated. (author) figs., tabs., 46 refs

  16. Safety and security analysis for distributed control system in nuclear power plants

    International Nuclear Information System (INIS)

    Lu Zhigang; Liu Baoxu

    2011-01-01

    The Digital Distributed Control System (DCS) is the core that manages all monitoring and operation tasks in a Nuclear Power Plant (NPP). So, Digital Distributed Control System in Nuclear Power Plant has strict requirements for control and automation device safety and security due to many factors. In this article, factors of safety are analyzed firstly, while placing top priority on reliability, quality of supply and stability have also been carefully considered. In particular, advanced digital and electronic technologies are adopted to maintain sufficient reliability and supervisory capabilities in nuclear power plants. Then, security of networking and information technology have been remarked, several design methodologies considering the security characteristics are suggested. Methods and technologies of this article are being used in testing and evaluation for a real implement of a nuclear power plant in China. (author)

  17. The supply chain of civil construction industries for support the nuclear power plant construction in Indonesia

    International Nuclear Information System (INIS)

    Dharu Dewi; Sriyana; Moch-Djoko Birmano; Sahala Lumbanraja; Nurlaila

    2013-01-01

    The use of domestic products for electricity infrastructure has been set out in the Ministerial Decree number: 54/M-IND/PER/3/2012, but the infrastructure of nuclear power plants (NPP) construction has not been included. Therefore, the potential of the local industries needs to be mapped it especially supply chain of civil construction industries to estimate the capability of the local component level (DCL) at the nuclear power plant project in Indonesia. NPP is a high-technology so that if NPP will be constructed, it is necessary to involve the national capability as media technology transfer, especially for EPC (Engineering, Procurement and Construction) services. Civil construction (civil part) play role is very large, about 21%. Therefore it is necessary in particular the role of the national civil construction industry to increase the capability of local content. Preparation of Civil construction infrastructure are depend on the supply chain of raw materials. The aim of the research was to map the supply chain of the civil construction industries. Methodology this study is a survey of national industries, literature review, and searching web site. The result study is a map of civil construction industries with raw material supply chain. (author)

  18. Nuclear Fusion Fuel Cycle Research Perspectives

    International Nuclear Information System (INIS)

    Chung, Hongsuk; Koo, Daeseo; Park, Jongcheol; Kim, Yeanjin; Yun, Sei-Hun

    2015-01-01

    As a part of the International Thermonuclear Experimental Reactor (ITER) Project, we at the Korea Atomic Energy Research Institute (KAERI) and our National Fusion Research Institute (NFRI) colleagues are investigating nuclear fusion fuel cycle hardware including a nuclear fusion fuel Storage and Delivery System (SDS). To have a better knowledge of the nuclear fusion fuel cycle, we present our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). To have better knowledge of the nuclear fusion fuel cycle, we presented our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). Our efforts to enhance the tritium confinement will be continued for the development of cleaner nuclear fusion power plants

  19. Secure energy supply without coal and nuclear power?

    International Nuclear Information System (INIS)

    Clement, W.

    2008-01-01

    The future of energy policy and energy supply is determined by the rising global demand for every kind of energy. Europe is being confronted with an ever growing dependence on imported oil and gas. We thus fall victim to the volatile ups and downs of oil and gas prices on the world markets. These risks to industry, and thus to jobs, are simply underrated, even ignored, in this country. Challenges of this kind require strategic solutions instead of case-by-case decisions which, in addition, more often than not are based on emotion rather than facts. Finding strategic solutions means that we must use all our scientific, technological and industrial potentials to achieve our ambitious goals in climate policy. We must use energy as intelligently as possible, i.e., we must develop and, above all, use CO 2 -free coal-fired power plants, safe nuclear power, renewable energy sources, and take measures to ensure a highly efficient management of energy. Only those four-pronged approach will enable us to ensure optimally competition, continuity of supply, and protection of the environment and the climate. Those who negate or ignore this interrelation are bound to fail in economic and ecological reality. (orig.)

  20. An advanced NSSS integrity monitoring system for Shin-Kori nuclear units 3 and 4

    International Nuclear Information System (INIS)

    Oh, Y. G.; Kim, H. B.; Galin, S. R.; Kim, S. H.; Lee, S. J.

    2009-01-01

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling. (authors)

  1. An Advanced NSSS Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4

    Science.gov (United States)

    Oh, Yang Gyun; Galin, Scott R.; Lee, Sang Jeong

    2010-12-01

    The advanced design features of NSSS (Nuclear Steam Supply System) Integrity Monitoring System for Shin-Kori Nuclear Units 3 and 4 are summarized herein. During the overall system design and detailed component design processes, many design improvements have been made for the system. The major design changes are: 1) the application of a common software platform for all subsystems, 2) the implementation of remote access, control and monitoring capabilities, and 3) the equipment redesign and rearrangement that has simplified the system architecture. Changes give an effect on cabinet size, number of cables, cyber-security, graphic user interfaces, and interfaces with other monitoring systems. The system installation and operation for Shin-Kori Nuclear Units 3 and 4 will be more convenient than those for previous Korean nuclear units in view of its remote control capability, automated test functions, improved user interface functions, and much less cabling.

  2. Probabilistic safety analysis of DC power supply requirements for nuclear power plants. Technical report

    International Nuclear Information System (INIS)

    Baranowsky, P.W.; Kolaczkowski, A.M.; Fedele, M.A.

    1981-04-01

    A probabilistic safety assessment was performed as part of the Nuclear Regulatory Commission generic safety task A-30, Adequacy of Safety Related DC Power Supplies. Event and fault tree analysis techniques were used to determine the relative contribution of DC power related accident sequences to the total core damage probability due to shutdown cooling failures. It was found that a potentially large DC power contribution could be substantially reduced by augmenting the minimum design and operational requirements. Recommendations included (1) requiring DC power divisional independence, (2) improved test, maintenance, and surveillance, and (3) requiring core cooling capability be maintained following the loss of one DC power bus and a single failure in another system

  3. Development of an integrated medical supply information system

    Science.gov (United States)

    Xu, Eric; Wermus, Marek; Blythe Bauman, Deborah

    2011-08-01

    The integrated medical supply inventory control system introduced in this study is a hybrid system that is shaped by the nature of medical supply, usage and storage capacity limitations of health care facilities. The system links demand, service provided at the clinic, health care service provider's information, inventory storage data and decision support tools into an integrated information system. ABC analysis method, economic order quantity model, two-bin method and safety stock concept are applied as decision support models to tackle inventory management issues at health care facilities. In the decision support module, each medical item and storage location has been scrutinised to determine the best-fit inventory control policy. The pilot case study demonstrates that the integrated medical supply information system holds several advantages for inventory managers, since it entails benefits of deploying enterprise information systems to manage medical supply and better patient services.

  4. 30 CFR 36.27 - Fuel-supply system.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fuel-supply system. 36.27 Section 36.27 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR TESTING, EVALUATION, AND APPROVAL OF... Construction and Design Requirements § 36.27 Fuel-supply system. (a) Fuel tank. (1) The fuel tank shall not...

  5. Systemic-Functional Approach to Utilities Supplys

    Directory of Open Access Journals (Sweden)

    Nikolay I. Komkov

    2017-01-01

    Full Text Available Purpose: the purpose of the article consists in statement of management approach to development of utilities supply processes based on conflict situations decision – making search. It had appeared in the period of the transition from the planned and directive management to market development. Methods: the research methodology is based on the system analysis of full life cycle processes functioning, forecasting of complex systems development, mathematical modeling of processes of services supply and innovative and investment projects modeling as well as development of supplying services processes. Results: the results of the work are concentrated in the presentation of systemic-functional approach to managing the development of processes of municipal services, able to resolve conflict situations in this sphere. Conclusions and Relevance: the traditional management approach on the basis of elimination of "bottlenecks" and emergencies prevailing within planned and directive system at its transformation in the market conditions has led to accumulation of conflict situations and unsolvable problems. The offered systemic-functional approach based on forecasting of full life cycle of the modernized processes and the services providing systems allows to consider costs of modernization, prime cost and quality of the rendered services. 

  6. National supply of reactivity control rods for Embalse nuclear power plant (CNE)

    International Nuclear Information System (INIS)

    Biondo, C.D.; Carloni, J.G.; Aba, J.A.

    1987-01-01

    The manufacture and supply on industrial scale of reactivity control rods for CNE (Embalse nuclear power plant) were developed by the National Atomic Energy Commission (CNEA) together with the private industry, as part of a program aimed to the substitution of imported supplies used in the operation of power plants by materials manufactured in Argentina. So far, the control rods were imported from Canada. In this work, the different development stages performed by CNEA and CONUAR S.A. are described, leading to the supply of a set of 21 cobalt rods to be included in a reactor of CNE in order to qualify this component. Among the main activities performed, the following stand out: specifications development, particularly those concerning to cobalt cores, evaluation of design documentation and elaboration of bidding conditions and a plan of manufacture and control. According to the results obtained during the service and the post-irradiation measurements, the design will be reviewed in order to undertake new manufacturing plans. (Author)

  7. Equipment system for advanced nuclear fuel development

    International Nuclear Information System (INIS)

    Kwon, Hyuk Il; Ji, C. G.; Bae, S. O.

    2002-11-01

    The purpose of the settlement of equipment system for nuclear Fuel Technology Development Facility(FTDF) is to build a seismic designed facility that can accommodate handling of nuclear materials including <20% enriched Uranium and produce HANARO fuel commercially, and also to establish the advanced common research equipment essential for the research on advanced fuel development. For this purpose, this research works were performed for the settlement of radiation protection system and facility special equipment for the FTDF, and the advanced common research equipment for the fuel fabrication and research. As a result, 11 kinds of radiation protection systems such as criticality detection and alarm system, 5 kinds of facility special equipment such as environmental pollution protection system and 5 kinds of common research equipment such as electron-beam welding machine were established. By the settlement of exclusive domestic facility for the research of advanced fuel, the fabrication and supply of HANARO fuel is possible and also can export KAERI-invented centrifugal dispersion fuel materials and its technology to the nations having research reactors in operation. For the future, the utilization of the facility will be expanded to universities, industries and other research institutes

  8. Advanced energy system with nuclear reactors as an energy source

    International Nuclear Information System (INIS)

    Kato, Y.; Ishizuka, T.; Nikitin, K.

    2007-01-01

    recovery system is also applicable to a fast reactor (FR) with a supercritical CO 2 gas turbine that achieves higher cycle efficiency than conventional sodium cooled FRs with steam turbines. The FR will eliminate problems of conventional FRs related to safety, plant maintenance, and construction costs. The FR consumes efficiently trans-uranium elements (TRU) produced in light water reactors as fuel and reduce long-lived radioactive wastes or environmental loads of long term geological disposal. An Advanced Energy System (AES) with nuclear reactors as an energy source has been proposed which supply electricity and heat to cities. The AES has three objectives: 1. Save energy resources and reduce green house gas emissions, attaining total energy utilization efficiency higher than 85% through waste heat recovery and utilization. 2. Foster a recycling society that produces methane and methanol for fuel cells from waste products of cities and farms. 3. Consume TRU produced in LWRs as fuel for FRs, and reduce long-lived radioactive wastes or environmental loads of long term geological disposal. References 1. Y. Kato, T. Nitawaki and K. Fujima, 'Zero Waste Heat Release Nuclear Cogeneration System, 'Proc. 2003 Intl. Congress on Advanced Nuclear Power Plants (ICAPP'03), Cordoba, Spain, May 4-7, 2003, Paper 3313. 2. Y. Kato, T. Nitawaki and Y. Muto, 'Medium Temperature Carbon Dioxide Gas Turbine Reactor, 'Nucl. Eng. Design, 230, pp. 195-207 (2004). 3. H. N. Tran and Y. Kato, 'New 2 37Np Burning Strategy in a Supercritical CO 2 Cooled Fast Reactor Core Attaining Zero Burnup Reactivity Loss,' Proc. American Nuclear Society's Topical Meeting on Reactor Physics (PHYSOR 2006), Vancouver, British Columbia, Canada, September 10-14, 2006

  9. Component nuclear containment structure

    International Nuclear Information System (INIS)

    Harstead, G.A.

    1979-01-01

    The invention described is intended for use primarily as a nuclear containment structure. Such structures are required to surround the nuclear steam supply system and to contain the effects of breaks in the nuclear steam supply system, or i.e. loss of coolant accidents. Nuclear containment structures are required to withstand internal pressure and temperatures which result from loss of coolant accidents, and to provide for radiation shielding during operation and during the loss of coolant accident, as well as to resist all other applied loads, such as earthquakes. The nuclear containment structure described herein is a composite nuclear containment structure, and is one which structurally combines two previous systems; namely, a steel vessel, and a lined concrete structure. The steel vessel provides strength to resist internal pressure and accommodate temperature increases, the lined concrete structure provides resistance to internal pressure by having a liner which will prevent leakage, and which is in contact with the concrete structure which provides the strength to resist the pressure

  10. Supply guarantee initiatives for nuclear fuel materials and services and their compatibility with the market

    International Nuclear Information System (INIS)

    Nagano, Koji

    2009-01-01

    This paper first discusses where and why those ideas for nuclear fuel supply assurance and guarantee mechanisms came out, and attempts to draw a comparison among the proposed schemes and thereby examine possible steps forward. (author)

  11. Power supply and stabilization of the supply system on board using decentralized voltage rectifiers

    Energy Technology Data Exchange (ETDEWEB)

    Grueb, W; Wegerer, K

    1987-04-01

    The functionally redundant power supply system of the Transrapid 06 II maglev train is described; it comprises four independent, battery-buffered networks and 30 linear generators per train section. Voltage rectifiers adapt the velocity- and load-dependent linear generator voltage to the 440 V d.c. networks and assure dynamic stabilisation as well as buffer battery loading. The result is a high-reliability power supply system on board with optimum utilisation of the power supplied by the linear generators while the train is running.

  12. Availability of nuclear fuels: one aspect of the reliability of supply. [German Federal Republic

    Energy Technology Data Exchange (ETDEWEB)

    Dolinski, U; Ziesing, H J [Deutsches Inst. fuer Wirtschaftsforschung, Berlin (F.R. Germany)

    1976-09-01

    In connection with the future supply of nuclear fuels to the Federal Republic of Germany the authors discuss the problems which arise. They describe the future development of the demand for natural uranium and the work involved in separation and deal with the possibilities of meeting the demand. They pay particular attention to the changed market situation and to the policies of the countries which produce uranium. The article is a detailed examination of the report by the German Institute for Economic Research (DIW) on aspects of the reliability of supply to the electricity supply industry in the Federal Republic of Germany, which was prepared under the aegis of the Bavarian Ministry for Economic and Transport. This investigation will be published, omitting the regional aspects, towards the middle of 1976, by the German Institute for Economic Research under the title 'Reliability, price and environmental protection aspects of energy supply'.

  13. Report of North-Rhine Westphalia's Land Government about the decision of the diet of July 10, 1986, concerning the transition to an energy supply system without nuclear electricity generation

    International Nuclear Information System (INIS)

    1987-09-01

    In response to the Chernobyl reactor accident, the diet of the Land North-Rhine Westphalia has taken the governmental declaration of the Land's prime minister as a basis for its discussions on June 4th and July 10th, 1986, about the hazards of nuclear power and the feasibility of energy supply without nuclear power. The decision taken by the diet on July 10th, 1986 calls upon the Land Government to 'inform the diet by mid-1987 about the means and methods and the time schedule envisaged for backing out of nuclear energy utilisation'. The report in hand deals with the technical feasibility and the effects of a nuclear power plant shut-off on the energy supply situation in the Land, with the legal framework, supervisory competences in the Land, the energy policy to be pursued by the Land government, and with the necessity to reach a new national consensus on energy policy. (orig./UA) [de

  14. Electrical system design and reliability at Ontario Hydro nuclear generating stations

    Energy Technology Data Exchange (ETDEWEB)

    Royce, C. J. [Ontario Hydro, 700 University Avenue, Toronto, Ontario M5G 1X6 (Canada)

    1986-02-15

    This paper provides an overview of design practice and the predicted and actual reliability of electrical station service Systems at Ontario Nuclear Generating Stations. Operational experience and licensing changes have indicated the desirability of improving reliability in certain instances. For example, the requirement to start large emergency coolant injection pumps resulted in the turbine generator units in a multi-unit station being used as a back-up power supply. Results of reliability analyses are discussed. To mitigate the effects of common mode events Ontario Hydro adopted a 'two group' approach to the design of safety related Systems. This 'two group' approach is reviewed and a single fully environmentally qualified standby power supply is proposed for future use. (author)

  15. Study on the possible consequences of a severe accident in a Swiss nuclear power plant on the drinking water supply

    International Nuclear Information System (INIS)

    Ustohalova, Veronika; Kueppers, Christian; Claus, Manuel

    2014-01-01

    The study on the possible consequences of a severe accident in a Swiss nuclear power plant on the drinking water supply covers the following issues: estimation of possible source terms and radioactive materials release rates, airborne water contamination, water contamination by direct pollution, consequences for the drinking water supply, emergency measures in case of a drinking water contamination, routine surveillance of surface and ground water and improvement possibilities in nuclear power plants.

  16. Hydropower recovery in water supply systems: Models and case study

    International Nuclear Information System (INIS)

    Vilanova, Mateus Ricardo Nogueira; Balestieri, José Antônio Perrella

    2014-01-01

    Highlights: • We present hydropower recovery models for water supply systems. • Hydropower recovery potential in water supply systems is highly variable. • The case studied could make the supply systems self-sufficient in terms of energy. • Hydropower recovery can reduce GHGs emissions and generate carbon credits. - Abstract: The energy efficiency of water supply systems can be increased through the recovery of hydraulic energy implicit to the volumes of water transported in various stages of the supply process, which can be converted into electricity through hydroelectric recovery systems. Such a process allows the use of a clean energy source that is usually neglected in water supplies, reducing its dependence on energy from the local network and the system’s operation costs. This article evaluates the possibilities and benefits of the use of water supply facilities, structures and equipment for hydraulic energy recovery, addressing several applicable hydroelectric models. A real case study was developed in Brazil to illustrate the technical, economic and environmental aspects of hydropower recovery in water supply systems

  17. Nuclear energy an introduction to the concepts, systems, and applications of nuclear processes

    CERN Document Server

    Murray, Raymond

    2001-01-01

    Nuclear Energy, Fifth Edition provides nuclear engineers, plant designers and radiation physicists with a comprehensive overview of nuclear energy and its uses, discusses potential problems and provides an outlook for the futureNew and important trends are discussed including probabilistic safety analysis (PSA), deregulation of the electric power industry to permit competition in the supply of electricity; improvements in performance characteristics of nuclear power plants, such as capacity factor, production costs, and safety factors; storage and disposal of all types of radioactive w

  18. Do we soon run out of uranium? Long-term concepts of nuclear fuel supply

    International Nuclear Information System (INIS)

    Prasser, Horst-Michael

    2008-01-01

    The extension of the worldwide light water reactor fleet will cause the demand for uranium to grow. The static reach of identified resources might soon fall below the life time of new nuclear power plants which are usually designed for 60 years of operation, if the exploration of new uranium deposits will stop resulting in exploitable resources. The article discusses, if, as frequently claimed, the energy consumption in the uranium mines renders impossible to secure the nuclear fuel supply in the long term. (orig.)

  19. Nuclear power plant Angra integrated enterprise management system

    International Nuclear Information System (INIS)

    Andrade, Ronaldo Barata de

    2009-01-01

    The characteristics and peculiarities of the Nuclear Power Plant ANGRA 3 enterprise, amongst which its technical complexity, the size of the project and of the supplies of goods and services contracted for for the Brazilian and foreign scopes, the variety of contractors and participants involved in the implementation, associated with the need of integrated management of all the activities of the enterprise, requires the setting of standardized criteria and procedures to be adopted by the enterprise Project Management Team and by all involved ELETRONUCLEAR (ETN) Units, Suppliers and Contractors for Brazilian and foreign goods and services for the execution of the activities related to overall enterprise planning. These criteria and procedures aim at covering the five Project Management Process Groups: Initiating Process Group, Planning Process Group, Execution Process Group, Monitoring and Controlling Process Group and Closing Process Group. For the ANGRA 3 enterprise, ETN developed the Integrated Enterprise Management System - INTEGRA, being the software 'Primavera Enterprise Project Management' a fundamental part of this system. The aim of this paper is to describe the main concepts involving the ANGRA 3 enterprise management, and the integration between the processes, including all disciplines in all phases of the enterprise life cycle, such as: Nuclear and Environmental Licensing, Infrastructure, National and Foreign Engineering, National and Import Supplies, Civil Works, Electromechanical Erection, Commissioning. (author)

  20. Safety requirements for a nuclear power plant electric power system

    Energy Technology Data Exchange (ETDEWEB)

    Fouad, L F; Shinaishin, M A

    1988-06-15

    This work aims at identifying the safety requirements for the electric power system in a typical nuclear power plant, in view of the UNSRC and the IAEA. Description of a typical system is provided, followed by a presentation of the scope of the information required for safety evaluation of the system design and performance. The acceptance and design criteria that must be met as being specified by both regulatory systems, are compared. Means of implementation of such criteria as being described in the USNRC regulatory guides and branch technical positions on one hand and in the IAEA safety guides on the other hand are investigated. It is concluded that the IAEA regulations address the problems that may be faced with in countries having varying grid sizes ranging from large stable to small potentially unstable ones; and that they put emphasis on the onsite standby power supply. Also, in this respect the Americans identify the grid as the preferred power supply to the plant auxiliaries, while the IAEA leaves the possibility that the preferred power supply could be either the grid or the unit main generator depending on the reliability of each. Therefore, it is found that it is particularly necessary in this area of electric power supplies to deal with the IAEA and the American sets of regulations as if each complements and not supplements the other. (author)

  1. Strategy of nuclear power in Korea, non-nuclear-weapon state and peaceful use of nuclear power

    International Nuclear Information System (INIS)

    Nagasaki, Takao

    2005-01-01

    The nuclear power plant started at Kori in Korea in April, 1978. Korea has carried out development of nuclear power as a national policy. The present capacity of nuclear power plants takes the sixes place in the world. It supplies 42% total power generation. The present state of nuclear power plant, nuclear fuel cycle facility, strategy of domestic production of nuclear power generation, development of next generation reactor and SMART, strategy of export in corporation with industry, government and research organization, export of nuclear power generation in Japan, nuclear power improvement project with Japan, Korea and Asia, development of nuclear power system with nuclear diffusion resistance, Hybrid Power Extraction Reactor System, radioactive waste management and construction of joint management and treatment system of spent fuel in Asia are stated. (S.Y.)

  2. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume III. Resources and fuel cycle facilities

    International Nuclear Information System (INIS)

    1980-06-01

    The ability of uranium supply and the rest of the nuclear fuel cycle to meet the demand for nuclear power is an important consideration in future domestic and international planning. Accordingly, the purpose of this assessment is to evaluate the adequacy of potential supply for various nuclear resources and fuel cycle facilities in the United States and in the world outside centrally planned economy areas (WOCA). Although major emphasis was placed on uranium supply and demand, material resources (thorium and heavy water) and facility resources (separative work, spent fuel storage, and reprocessing) were also considered

  3. Sea water pumping-up power plant system combined with nuclear power plant

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Tanaka, Masayuki.

    1991-01-01

    It is difficult to find a site suitable to construction for a sea water pumping-up power plant at a place relatively near the electric power consumption area. Then, a nuclear power plant is set at the sea bottom or the land portion of a sea shore near the power consumption area. A cavity is excavated underground or at the bottom of the sea in the vicinity of the power plant to form a lower pond, and the bottom of the sea, as an upper pond and the lower pond are connected by a water pressure pipe and a water discharge pipe. A pump water turbine is disposed therebetween, to which electric power generator is connected. In addition, an ordinary or emergency cooling facility in the nuclear power plant is constituted such that sea water in the cavity is supplied by a sea water pump. Accordingly, the sea water pumping-up plant system in combination with the nuclear power plant is constituted with no injuring from salts to animals and plants on land in the suburbs of a large city. The cost for facilities for supplying power from a remote power plant to large city areas and power loss are decreased and stable electric power can be supplied. (N.H.)

  4. Development of nuclear power plant automated remote patrol system

    International Nuclear Information System (INIS)

    Nakayama, R.; Kubo, K.; Sato, K.; Taguchi, J.

    1984-01-01

    An Automated Remote Patrol System was developed for a remote inspection, observation and monitoring of nuclear power plant's components. This automated remote patrol system consists of; a vehicle moving along a monorail; three rails mounted in a monorail for data transmission and for power supply; an image fiber connected to a TV camera; an arm type mechanism (manipulator) for moving image fiber; a computer for control and data processing and operator's console. Special features of this Automated Remote Patrol System are as follows: The inspection vehicle runs along horizontal and vertical (up/down) monorails. The arm type mechanism (manipulator) on the vehicle is used to move image fiber. Slide type electric collectors are used for data transmission and power supply. Time-division multiplexing is adapted for data transmission. Voice communication is used for controlling mechanisms. Pattern recognition is used for data processing. The experience that has been obtained from a series of various tests is summarized. (author)

  5. Applied reliability assessment for the passive safety systems of nuclear power plants (NPPs) using system dynamics (SD)

    International Nuclear Information System (INIS)

    Kim, Yun Il; Woo, Tae Ho

    2018-01-01

    The passive system by the free-fall is investigated in the accident of nuclear power plants (NPPs). The complex algorithm of the system dynamics (SD) modeling is done in the passive cooling system. The nuclear passive system by free-fall is successfully modeled for the loss of coolant accident (LOCA). Conventional passive system of gravity or natural circulation is working only when the piping systems is in the good condition. The external coolant supply system is introduced in the case of the piping system failure. The water is poured into the reactor through the guiding piping or tube. If the explosion happens, the coolants could be showering into the reactor core and its building. New kind of passive system is expected successfully in the on-site black out where the drone could be operated by battery or engine.

  6. Supplying the nuclear arsenal: Production reactor technology, management, and policy, 1942--1992

    Energy Technology Data Exchange (ETDEWEB)

    Carlisle, R.P.; Zenzen, J.M.

    1994-01-01

    This book focuses on the lineage of America`s production reactors, those three at Hanford and their descendants, the reactors behind America`s nuclear weapons. The work will take only occasional sideways glances at the collateral lines of descent, the reactor cousins designed for experimental purposes, ship propulsion, and electric power generation. Over the decades from 1942 through 1992, fourteen American production reactors made enough plutonium to fuel a formidable arsenal of more than twenty thousand weapons. In the last years of that period, planners, nuclear engineers, and managers struggled over designs for the next generation of production reactors. The story of fourteen individual machines and of the planning effort to replace them might appear relatively narrow. Yet these machines lay at the heart of the nation`s nuclear weapons complex. The story of these machines is the story of arming the winning weapon, supplying the nuclear arms race. This book is intended to capture the history of the first fourteen production reactors, and associated design work, in the face of the end of the Cold War.

  7. Nuclear materials management handbook. Safeguards, physical protection of nuclear material. 1995 ed.

    International Nuclear Information System (INIS)

    1995-01-01

    Now, very safe and stable supply of electric power has become to be obtained by nuclear energy, and Japan has steadily promoted nuclear power as the basic energy that contributes to overcome the unstable structure of energy supply in Japan highly depending on foreign countries, as shown in the long term plan of the research, development and utilization of nuclear power. Great progress was observed in nuclear fuel recycling in Japan such as the attainment of initial criticality of the prototype FBR 'Monju' and the start of construction of the commercial fuel reprocessing plant in Rokkasho. Recently the recognition of the importance of nuclear substance management has heightened, and the measures for maintaining and strengthening the reliability of nuclear nonproliferation system are investigated. It is important that Japan strictly observes the nuclear nonproliferation system based on the NPT which was extended infinitely. In this handbook, the outline of the measures for nuclear nonproliferation and safeguard and the protection of nuclear substances, the treaties and agreements and the national laws related to these are described. (K.I.)

  8. Conceptual study on HTGR-IS hydrogen supply system using organic hydrides

    International Nuclear Information System (INIS)

    Terada, Atsuhiko; Noguchi, Hiroki; Takegami, Hiroaki; Kamiji, Yu; Inagaki, Yoshiyuki

    2012-02-01

    We have proposed a hydrogen supply-chain system, which is a storage/supply system of large amount of hydrogen produced by HTGR-IS hydrogen production system. The organic chemical hydride method is one of the candidate techniques in the system for hydrogen storage and transportation. In this study, properties of organic hydrides and conventional hydrogen storage/supply system were surveyed to make use of the conceptual design of the hydrogen supply system using an organic hydrides method with VHTR-IS hydrogen production process (hydrogen production: 85,400 Nm 3 /h). Conceptual specifications of the main equipments were designed for the hydrogen supply system consisting of hydrogenation and dehydrogenation process. It was also clarified the problems of hydrogen supply system, such as energy efficiency and system optimization. (author)

  9. Corrective maintenance support system for nuclear power plants

    International Nuclear Information System (INIS)

    Kakiuchi, Tetsuo

    1996-01-01

    With increase of share of nuclear power generation in electric power supply in Japan, requirement for further safe operation and improvement of economics for the nuclear power plants is promoting. The pressed water type (PWR) nuclear power plant in operation in Japan reaches to 22 sets, application rate of the instruments is 74% as mean value for 7 years since 1989 and in high level, which is due to a result of preventive maintenance in ordinary and periodical inspections. The present state of maintenance at the nuclear power plant is mainly preventive maintenance, which is mainly conducted in a shape of time planning maintenance but partially in a shape of state monitoring maintenance for partial rotating appliances. Concretely speaking, the periodical inspection was planned on a base of daily inspection and a long term program on maintenance, and executed on a base of feedback function to think of the long term program again by evaluating the periodical inspection results. Here were introduced on the monitoring diagnosis and periodical inspection regionalization equipment, fatigue monitoring system, automatic supersonic wave damage inspection equipment for reactor, steam evaporator heat conductive tube inspection equipment, automatic testing equipment for measuring controller, air working valve property testing equipment, as maintaining support system in the PW generation plant. (G.K.)

  10. ILK statement on sustainability - evaluation of nuclear energy and other electricity supply technologies

    International Nuclear Information System (INIS)

    2004-01-01

    The electricity utility sector is of central importance for economic growth and societal development. While numerous societal and economic benefits arise from electricity consumption, its production can also have impacts which may not be fully and unanimously reconciled with the concept of sustainability. Consideration of sustainability issues plays an increasingly important role in decisions affecting the current and future energy supply. Judgements on the sustainability of specific electricity supply options are, however, mostly made in an ad hoc manner, and are susceptible to bias and arbitrariness. The German Federal Government singles out nuclear energy in particular as not sustainable for the future and considers it in a fundamentally critical manner separately from the other options. The ILK's opinion is that all options of interest, including nuclear, need to be evaluated in a comparative perspective based on a systematic and comprehensive approach. Therefore, the ILK considered it worthwhile to investigate this matter in more detail and express its views in the form of the present statement. The ILK statement on sustainability takes into consideration the most relevant international and national developments. These form the background and input for the establishment of ILK's position. A limited scope comparative study on the sustainability of different electricity supply technologies under German conditions was carried out by the Paul Scherrer Institut (PSI) in order to demonstrate the applicability of a systematic approach and generate reasonably consistent results from which robust conclusions can be derived. (orig.) [de

  11. New supply for canyon fire foam system

    International Nuclear Information System (INIS)

    Gainey, T.

    1995-01-01

    The raw water supply for the B-Plant Canyon fire foam system is being replaced. The 4 inche water supply line to the foam system is being rerouted from the 6 inches raw water line in the Pipe Gallery to the 10 inches raw water main in the Operating Gallery. This document states the acceptance criteria for the flushing and testing to be performed by the contractor

  12. Nuclear fuel pellet collating system and method

    International Nuclear Information System (INIS)

    Rieben, S.L.; Kugler, R.W.; Scherpenberg, J.J.; Wiersema, D.T.

    1990-01-01

    This patent describes a method of collating nuclear fuel pellets. It comprises: supporting a plurality of pellet supply trays and a plurality of pellet storage trays at a tray positioning station. Each of the supply trays containing in at least one row thereon a plurality of nuclear fuel pellets of an enrichment different from the enrichment pellets on at least some other of the supply trays; transferring one pellet supply tray from the tray positioning station and disposing the same at an input station of a pellet collating line; transferring one pellet storage tray from the tray positioning station and disposing the same at an output station of the pellet collating line; sweeping pellets in the at least one row thereof from the one pellet supply tray onto a work station of the pellet collating line located between the input and output stations thereof; measuring a desired length of pellets in the at least one row on the work station and separating the measured desired length of pellets from the remaining pellets, if any, in the row thereof; sweeping the remaining pellets, if any, in the row from the work station back onto the one pellet supply tray; transferring the one pellet supply tray and remaining pellets, if any, back to the tray positioning station; sweeping the measured desired length of pellets from the work station onto the one pellet storage tray; and transferring the one pellet storage tray and measured desired length of pellets back to the tray positioning station

  13. Experience with reactor power cutback system at Palo Verde nuclear generating station

    International Nuclear Information System (INIS)

    Chari, D.R.; Rec, J.R.; Simoni, L.P.; Eimar, R.L.; Sowers, G.W.

    1987-01-01

    Palo Verde Nuclear Generating Station (PVNGS) is a three unit site which illustrates System 80 nuclear steam supply system (NSSS) design. The System 80 NSSS is the Combustion Engineering (C-E) standard design rated at 3817 Mwth. PVNGS Units 1 and 2 achieved commercial operation on February 13, 1986 and September 22, 1986, respectively, while Unit 3 has a forecast date for commercial operation in the third quarter of 1987. The System 80 design incorporates a reactor power cutback system (RPCS) feature which reduces plant trips caused by two common initiating events: loss of load/turbine trip (LOL) and loss of one main feedwater pump (LOMFWP). The key design objective of the RPCS is to improve overall plant availability and performance, while minimizing challenges to the plant safety system

  14. Supply risk under the condition of discontinuous demand in the field of nuclear power industry

    International Nuclear Information System (INIS)

    Wei Qiyan; Tian Zhilong

    2006-01-01

    Demands can be divided into two kinds: continuous and discontinuous demands. Based on the analysis of the results on common supply risk studies, discontinuous demand is studied concerning its definition, characteristics, and the more obvious and severe risks and consequences induced by its characteristics. Furthermore, the discontinuous characteristics and relevant precautions of demand of nuclear power industry are analyzed. Analysis and research on supply risks under the condition of discontinuous demand would be helpful to enterprises to take this issue serious and prevent the risks. (authors)

  15. Status of helium-cooled nuclear power systems. [Development potential

    Energy Technology Data Exchange (ETDEWEB)

    Melese-d' Hospital, G.; Simnad, M

    1977-09-01

    Helium-cooled nuclear power systems offer a great potential for electricity generation when their long-term economic, environmental, conservation and energy self-sufficiency features are examined. The high-temperature gas-cooled reactor (HTGR) has the unique capability of providing high-temperature steam for electric power and process heat uses and/or high-temperature heat for endothermic chemical reactions. A variation of the standard steam cycle HTGR is one in which the helium coolant flows directly from the core to one or more closed cycle gas turbines. The effective use of nuclear fuel resources for electric power and nuclear process heat will be greatly enhanced by the gas-cooled fast breeder reactor (GCFR) currently being developed. A GCFR using thorium in the radial blanket could generate sufficient U-233 to supply the fuel for three HTGRs, or enough plutonium from a depleted uranium blanket to fuel a breeder economy expanding at about 10% per year. The feasibility of utilizing helium to cool a fusion reactor is also discussed. The status of helium-cooled nuclear energy systems is summarized as a basis for assessing their prospects. 50 references.

  16. Strategic and policy issues raised by the transition from thermal to fast nuclear systems

    International Nuclear Information System (INIS)

    2009-01-01

    The renewed interest in nuclear energy triggered by concerns about global climate change and security of supply, which could lead to substantial growth in nuclear electricity generation, enhances the attractiveness of fast neutron reactors with closed fuel cycles. Moving from the current fleet of thermal neutron reactors to fast neutron systems will require many decades and extensive RD-D efforts. This book identifies and analyses key strategic and policy issues raised by such a transition, aiming at providing guidance to decision makers on the best approaches for implementing transition scenarios. The topics covered in this book will be of interest to government and nuclear industry policy makers as well as to specialists working on nuclear energy system analyses and advanced fuel cycle issues. (author)

  17. Public Water Supply Systems (PWS)

    Data.gov (United States)

    Kansas Data Access and Support Center — This dataset includes boundaries for most public water supply systems (PWS) in Kansas (525 municipalities, 289 rural water districts and 13 public wholesale water...

  18. Communication received on 12 September 2006 from the Permanent Mission of Japan to the Agency concerning arrangements for the assurance of nuclear fuel supply

    International Nuclear Information System (INIS)

    2006-01-01

    The Secretariat has received on 12 September 2006 a communication from the Permanent Mission of Japan attaching a document entitled 'Japan's Proposal: IAEA Standby Arrangements System for the Assurance of Nuclear Fuel Supply'. As requested by the Permanent Mission, the text of the attachment is herewith reproduced for the information of Member States

  19. Comparison between Different Power Sources for Emergency Power Supply at Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lenasson, Magnus

    2015-01-01

    Currently the Swedish nuclear power plants are using diesel generator sets and to some extent gas turbines as their emergency AC power sources and batteries as their emergency DC power sources. In the laws governing Swedish nuclear activity, no specific power sources are prescribed. On the other hand, diversification of safety functions should be considered, as well as simplicity and reliability in the safety systems. So far the choices of emergency power sources have been similar between different power plants, and therefore this project investigated a number of alternative power sources and if they are suitable for use as emergency power on nuclear power plants. The goals of the project were to: - Define the parameters that are essential for rending a power source suitable for use at a nuclear power plant. - Present the characteristics of a number of power sources regarding the defined parameters. - Compile the suitability of the different power sources. - Make implementation suggestions for the less conventional of the investigated power sources. (unconventional in the investigated application) 10 different power sources in total have been investigated and to various degrees deemed suitable Out of the 10 power sources, diesel generators, batteries and to some extent gas turbines are seen as conventional technology at the nuclear power plants. In relation to them the other power sources have been assessed regarding diversification gains, foremost with regards to external events. The power sources with the largest diversification gains are: Internal steam turbine, Hydro power, Thermoelectric generators. The work should first and foremost put focus on the fact that under the right circumstances there are power sources that can complement conventional power sources and yield substantial diversification gains. This paper is a shortened version of the report 'Comparison between different power sources for emergency power supply at nuclear power plants'. The

  20. Bipolar programmable current supply for superconducting nuclear magnetic resonance magnets

    Science.gov (United States)

    Koivuniemi, Jaakko; Luusalo, Reeta; Hakonen, Pertti

    1998-09-01

    In high resolution continuous-wave nuclear magnetic resonance (NMR) work well-reproducible, linear sweeps of current are needed. We have developed a microcontroller based programmable current supply, tested with superconducting magnets with inductance of 10 mH and 10 H. We achieved a resolution and noise of 4 ppm. The supply has an internal sweep with programmable ramping rate and a possibility for remote operation from a computer with either GPIB or RS232 interface. It is based on an 18-bit D/A converter. The maximum output current is ±10 A, the sweep rate can be set between 1 μA/s-140 mA/s, and the maximum output voltage is ±2.5 V. In work at ultralow temperatures, especially in superconducting quantum interference device NMR, all rf interference to the experiment should be avoided. One of the sources of this kind of unwanted input is the digital switching noise of fast logic devices. We discuss this problem in the context of our design.

  1. Supply air filters after the nuclear reactor accident at Chernobyl

    International Nuclear Information System (INIS)

    Bonka, H.

    1989-01-01

    In the case of increased activity concentration in the air supply air filters are the facility compounds where enhanced activity is collected. Therefore, it was understandable that the people put questions about the doses caused by supply air filters after the nuclear reactor accident at Chernobyl. When comparing the local dose rate at a distance of 1 m in front of filters with the outdoor local dose rate due to dry deposited radionuclides, nearly the same local dose rate results assuming an air flow rate of approx. 60 m 3 /h. Supposing a 10 hours stay at a distance of 1 m in front of filters and an air flow rate of approx. 5000 m 3 /h the same dose is obtained after a 10 days delay as the dose due to outdoor inhalation. At Aachen, the local dose rate near to filters increased up to approx. 10 μSv/h. After a suitable time delay of one month filters could be rejected like normal waste. A review is given on individual measured values

  2. Prospects for development of heat supply systems in high-rise districts

    Science.gov (United States)

    Zhila, Viktor; Solovyeva, Elena

    2018-03-01

    The article analyzes the main advantages and disadvantages of centralized and decentralized heat supply systems in high-rise districts. The main schemes of centralized heat supply systems are considered. They include centralized heat supply from boiler houses, centralized heat supply from autonomous heat sources, heat supply from roof boiler houses and door-to-door heating supply. For each of these variant, the gas distribution systems are considered and analyzed. These systems vary depending on the heat source location. For each of these systems, technical and economic indicators are taken into account, the analysis of which allows choosing the best option for districts where high-rise buildings predominate.

  3. Super long-term scenario of world nuclear power generation and uranium supply and demand until 2030 and further 2100

    International Nuclear Information System (INIS)

    Komiyama, Ryoichi; Kakinoki, Tatsuro

    2007-01-01

    Based on latest nuclear policy and development trend in each country in the world, quantity of nuclear power generation and the uranium supply and demand until 2030 and further 2100 were predicted. As a result, the introduction of nuclear power stations spreads around Asia until 2030. The limitation on the uranium resources clearly does not exist until 2030, but a development period of around 10 years is necessary for exploitation of uranium resources. If timely development investment does not advance, it may invite shortage of uranium supply and promote a remarkable rise of uranium supply price. If the reinforcement of the anti-global warming measure and the diversification of the energy source advance at the super long-term time span called 2100, the world coal power largely decreases and the introduction of the nuclear power enlarges steadily. Introduction of the light water reactor (LWR) extends until 2080 since the fuel uses uranium resources of about 70 year ratio of reserves to production, but quantity of LWR power stations and power generation changes for the decrease due to the limitation of uranium resources after it. On the other hand, sustained expansion of the plutonium utilization by the fuel cycle technology and the introduction of the fast breeder reactor (FBR) advance after 2050. Then the sustained expansion of nuclear power is surely expected to occupy the first share of power generation in 2100. On this account it is necessary to push forward the plutonium use, backend technology and FBR development globally, and Japan is expected to carry a positive role to lead international nuclear energy technology development as a nuclear energy developed nation. (T. Tanaka)

  4. Analysis on the Electric Power Supply - Demand Measures of Japan in 2011 Summer after Earthquake and Tsunami

    International Nuclear Information System (INIS)

    Lee, Y. E.; Chang, H. S.

    2011-01-01

    Only 12 of 54 nuclear reactors are in operation as of September 1, 2011 in the wake of the earthquake and tsunami in Japan. The share of nuclear power in the nation's installation capacity fell to about 14% in August from about 30% before March 11, 2011. Government or many of research institutes estimated that the power supply system in Japan would fall to the minus reserve margin, if the nuclear power stations could not be restarted as scheduled. However, the current situation of power supply system in Japan is less severe than expected before, because the power companies and public have engaged in various diligent efforts to boost supply capacity or reduce demand in response to the electric power crisis. This paper aims to analyze the how much Japan electric power supply system depends on the nuclear power, what kinds of countermeasures of electric power supply-demand are taken by electricity companies in summer time to avoid the blackouts and why the saving electricity in Japan could be possible unlike Korea. Insights from this paper would be taken into account in the long term energy planning, even though the further study in depth should be followed

  5. Knowledge management system for risk mitigation in supply chain uncertainty: case from automotive battery supply chain

    Science.gov (United States)

    Marie, I. A.; Sugiarto, D.; Surjasa, D.; Witonohadi, A.

    2018-01-01

    Automotive battery supply chain include battery manufacturer, sulphuric acid suppliers, polypropylene suppliers, lead suppliers, transportation service providers, warehouses, retailers and even customers. Due to the increasingly dynamic condition of the environment, supply chain actors were required to improve their ability to overcome various uncertainty issues in the environment. This paper aims to describe the process of designing a knowledge management system for risk mitigation in supply chain uncertainty. The design methodology began with the identification of the knowledge needed to solve the problems associated with uncertainty and analysis of system requirements. The design of the knowledge management system was described in the form of a data flow diagram. The results of the study indicated that key knowledge area that needs to be managed were the knowledge to maintain the stability of process in sulphuric acid process and knowledge to overcome the wastes in battery manufacturing process. The system was expected to be a media acquisition, dissemination and storage of knowledge associated with the uncertainty in the battery supply chain and increase the supply chain performance.

  6. Performance of different types of renewable power supply systems

    Energy Technology Data Exchange (ETDEWEB)

    Al-Motawakel, M K [Sana' a Univ. (Republic of Yemen). Dept. of Physics; Abu-El-Eizz, H M; Awwad, Z [Zagazig Univ. (EG). Dept. of Physics

    1991-10-01

    In this paper we investigate the performance of a hybrid Photovoltaic (PV)-Wind generator power supply system operating under good and fair insolation and wind regimes. The effectiveness of such a hybrid system is measured by the Relative Sizing Parameter (RSP), Money Saving Parameter (MSP), and the Overall Reliability Parameter (ORP). Under specified weather conditions and for a nominal load demand, the RSP relates the product of the PV-modules and storage batteries involved in sizing the PV-Wind hybrid system to those of a stand alone PV-system sized to meet the same load. The MSP reports the difference between the total costs of a stand-alone PV power supply system and a hybrid PV-Wind power supply system, both sized to meet the same load, as a percentage of the total costs involved in supplying the load with a stand-alone PV power supply system only. The ORP compares the yearly average of the daily excess energy (positive difference between generated and consumed energy) of the hybrid system to that of the stand-alone PV power system. Based on this strategy we were able to develop a number of design diagrams which can be used in judging the benefits of utilizing hybrid PW-Wind generators on both economic and energy reliability grounds. (author).

  7. DAΦNE magnet power supply system

    International Nuclear Information System (INIS)

    Ricci, R.; Sanelli, C.; Stecchi, A.

    1998-01-01

    The e + -e - , 1020 MeV at center of mass, Particle Accelerator Complex DAΦNE, consists of a linear accelerator (Linac), a damping ring (D.A.), nearly 180 m of transfer lines (T.L.) and two storage rings (S.R.), that intersect each other in two points (I.P.), for Φ particle production. The D.A., T.L. and S.R. magnets are powered by means of 462 power supplies, rating from 100 W to 1 MW. The very different output currents, from 10 A to 2300 A, and output voltages, from 8 V to 1300 V, imposed many different technical solution realized by the world industry. This paper describes the Power Supply System giving also a description of the different typologies, their characteristics and control systems. The paper reports also the power supply performances and gives information on their installation and first year operation period

  8. World energy supply and demand and the future of nuclear power

    International Nuclear Information System (INIS)

    Lantzke, U.

    1977-01-01

    The author discusses the OECD's report ''World Energy Outlook'', which concluded that a severe energy gap could, and probably would, develop by the mid-1980s if present energy policies continue. Should nuclear power fail to make a substantial contribution, this situation is predicted to become even worse. The author states that an energy gap can only be realistically avoided by a combination of (a) deep energy conservation, (b) even greater use of coal, and (c) nuclear power. New energy technologies cannot realistically be expected to make a significant contribution much before the end of the century. Conservation and coal alone, however, will not be sufficient. It is difficult to envisage energy savings of more than 10% without reducing economic activity to a degree that becomes politically unacceptable. Greater use of coal is undoubtedly feasible, but the potential is severely constrained in the medium term for economic, technological and environmental reasons. Nuclear power must also make a significant contribution. However, estimates of OECD nuclear energy supply for 1985 have been scaled drastically downwards during 1976 owing to: uncertainty in the utility sector over future growth in electricity demand; continued, and in some cases increased, opposition to nuclear power; and delays and uncertainties in government nuclear policies and programmes. The author concludes that we cannot afford any further shortfall and we must move urgently to: (a) give strong and unswerving support to thermal nuclear reactor programmes (requiring that governments adopt clear and coherent nuclear policies, taking into account the legitimate concern expressed by the public); (b) develop stable and long-term international arrangements so that the necessary nuclear fuel facilities can be made available on a secure basis for peaceful uses of nuclear power; (c) decide what the real proliferation risk is and agree on action to avoid it; and (d) make renewed and stronger efforts to solve

  9. Power supply control system for experimental physical facilities

    International Nuclear Information System (INIS)

    Zelepukin, S.A.; Osipov, Eh.V.; Petrov, V.S.; Sergeev, V.A.; Uglekov, V.Ya.

    1979-01-01

    A multichannel (to 1024 channels) system for control of power supply voltage is descrited. The system consists of an analog commulator, a digital voltmeter and a special controller. The controller serves at the same time as an interface for connecting the system as a ''unit'' of the VECTOR and SUMMA unified electronic systems. The system has been realized for control of the photomultiplier power supply voltage of the MARK multipurpose experimental device (256 channels, the measurement accuracy is 0.2%, the measuring time is 500 ms per point). Software devised for the HP-2100 computer permits automatical comparison of photomultiplier power supply voltages with sample ones in the mode of continuous control of a single voltage or in the mode of programmed selection of voltages to provide the control in arbitrary order or automatic scanning

  10. The Complex Economic System of Supply Chain Financing

    Science.gov (United States)

    Zhang, Lili; Yan, Guangle

    Supply Chain Financing (SCF) refers to a series of innovative and complicated financial services based on supply chain. The SCF set-up is a complex system, where the supply chain management and Small and Medium Enterprises (SMEs) financing services interpenetrate systematically. This paper establishes the organization structure of SCF System, and presents two financing models respectively, with or without the participation of the third-party logistic provider (3PL). Using Information Economics and Game Theory, the interrelationship among diverse economic sectors is analyzed, and the economic mechanism of development and existent for SCF system is demonstrated. New thoughts and approaches to solve SMEs financing problem are given.

  11. Optimal Control and Optimization of Stochastic Supply Chain Systems

    CERN Document Server

    Song, Dong-Ping

    2013-01-01

    Optimal Control and Optimization of Stochastic Supply Chain Systems examines its subject in the context of the presence of a variety of uncertainties. Numerous examples with intuitive illustrations and tables are provided, to demonstrate the structural characteristics of the optimal control policies in various stochastic supply chains and to show how to make use of these characteristics to construct easy-to-operate sub-optimal policies.                 In Part I, a general introduction to stochastic supply chain systems is provided. Analytical models for various stochastic supply chain systems are formulated and analysed in Part II. In Part III the structural knowledge of the optimal control policies obtained in Part II is utilized to construct easy-to-operate sub-optimal control policies for various stochastic supply chain systems accordingly. Finally, Part IV discusses the optimisation of threshold-type control policies and their robustness. A key feature of the book is its tying together of ...

  12. JIT supply chain; an investigation through general system theory

    Directory of Open Access Journals (Sweden)

    O P Mishra

    2013-03-01

    Full Text Available This paper explains theoretical approach of the four theories of General system Theory (GST developed by Yourdon (1989 [Yourdon, E. (1989. Modern Structured Analysis. Yourdon Press, Prentice-Hall International, Englewood Cliffs, New Jersey. Senge] while applying it in information technology and subsequently used by caddy (2007 [Caddy I.N., & Helou, M.M. (2007. Supply chains and their management: Application of general systems theory. Journal of Retailing and Consumer Services, 14, 319–327.] in field of supply chain and management. JIT philosophy in core activities of supply chain i.e. procurement, production processes, and logistics are discussed through general system theory. The growing structure of the supply chain poses the implication restrictions and requires a heavy support system, many times a compromise is done while implementing JIT. The study would be useful to understand the general trends generated naturally regarding the adoption of the JIT philosophy in the supply chain.

  13. Energy-Cost Optimisation in Water-Supply System

    OpenAIRE

    Farrukh Mahmood; Haider Ali

    2013-01-01

    Households as well as community water-supply systems for utilisation of underground aquifers are massive consumers of energy. Prevailing energy crisis and focus of the government on demand-side energy policies (i.e., energy conservation) in Pakistan raises need of using energy efficient techniques in almost every aspect of life. This paper analyses performance of community relative to household water-supply system in connection with efficient energy utilisation. Results suggest that total ope...

  14. The imperative for stronger vaccine supply and logistics systems.

    Science.gov (United States)

    Zaffran, Michel; Vandelaer, Jos; Kristensen, Debra; Melgaard, Bjørn; Yadav, Prashant; Antwi-Agyei, K O; Lasher, Heidi

    2013-04-18

    With the introduction of new vaccines, developing countries are facing serious challenges in their vaccine supply and logistics systems. Storage capacity bottlenecks occur at national, regional, and district levels and system inefficiencies threaten vaccine access, availability, and quality. As countries adopt newer and more expensive vaccines and attempt to reach people at different ages and in new settings, their logistics systems must be strengthened and optimized. As a first step, national governments, donors, and international agencies have crafted a global vision for 2020 vaccine supply and logistics systems with detailed plans of action to achieve five priority objectives. Vaccine products and packaging are designed to meet the needs of developing countries. Immunization supply systems support efficient and effective vaccine delivery. The environmental impact of energy, materials, and processes used in immunization systems is minimized. Immunization information systems enable better and more timely decision-making. Competent and motivated personnel are empowered to handle immunization supply chain issues. Over the next decade, vaccine supply and logistics systems in nearly all developing countries will require significant investments of time and resources from global and national partners, donors, and governments. These investments are critical if we are to reach more people with current and newer vaccines. Copyright © 2012 Elsevier Ltd. All rights reserved.

  15. Regional energy-environment system analysis and the role of low-temperature nuclear heat in North China

    International Nuclear Information System (INIS)

    Lu Yingyun

    1984-01-01

    The consumption of commercial energy in China in 1980 amounted to 603 million tonnes of coal equivalent (tce). By the end of this century, according to preliminary forecasting, it will reach some 1200 million tce at least, but there may still be some gaps in the energy supply. Within the structure of China's current energy supply, coal is the dominating fuel, most of which is burned directly, thus causing serious air pollution particularly in urban areas during the winter season. To take into consideration the environmental impacts in formulating appropriate energy policies and carrying out rational energy planning, a practical regional energy system model in connection with environment impacts has been developed. It is essentially a linear programme model. The model has already been used to evaluate the role of alternative energies and technologies including the nuclear option in North China's future urban energy system. The preliminary results thus obtained have shown that nuclear energy, particularly low-temperature nuclear heat, must be introduced to reduce air pollution and fill the gaps in the energy supply. Since small- or medium-sized heat-only reactors have already been reported to be economical, safe and non-polluting, that will be developed in urban areas in North China to a certain extent by the end of this century. (author)

  16. An approach for high voltage power supply system for HCAL of LHCb experiment

    International Nuclear Information System (INIS)

    Cimpean, A.; Dumitru, D.; Kluger, A.; Magureanu, C.; Tarta, D.; Coca, C.; Orlandea, M.; Popescu, S.

    2003-01-01

    The main aim of the calorimeter system of the LHCb (Large Hadron Collider Beauty) experiment dedicated to precision measurements of CP violation and rare phenomena is to provide identification of the electrons, hadrons and photons, for the level-0 trigger and offline analysis with measurements of position and energy. The system consists in a scintillator pad/preshower (SPD/PS) detector, an electromagnetic calorimeter (ECAL) and a hadron calorimeter (HCAL), all the sub-detectors having a similar technology with scintillating tiles as active material and being read out via wavelength-shifting fibers and with an identical readout electronics for ECAL and HCAL and similar electronics for the PS. During 1997-1999 a computer controlled High Voltage (HV) distribution scheme was developed by Horia Hulubei National Institute for Physics and Nuclear Engineering (IFIN-HH) group and used to supply the PMTs of half HCAL prototype during the beam tests (1998-2000). This scheme consisted of three parts: 1) a control box which includes low voltage power supply, the RS232 interface to a PC and three modules of high voltage power supply; 2) two types of multichannel HV distributors with an individual voltage setting; 3) a software package to control all settings and refresh them periodically. Based on the acquired experience, a new design for a High Voltage Power Supply (HVPS) which satisfies the LHCb requirements has been developed for PMTs of the hadron calorimeter. The demands of this system are simplicity and low cost. This HVPS with multiple outputs (HV for photocathode and D1 - D4 dynodes) is destined to supply, with the same high voltage, groups of PMTs sorted by similar characteristics as gain and sensitivity. Because of the high rates (∼ 40 MHz) supported by PMTs, booster voltage sources are necessary to supply current for the last 4 dynodes. The box has 5 HV power supplies for photocathodes and the last 4 dynodes, each HV power supply being followed by a 4 channel

  17. Smart Power Supply for Battery-Powered Systems

    Science.gov (United States)

    Krasowski, Michael J.; Greer, Lawrence; Prokop, Norman F.; Flatico, Joseph M.

    2010-01-01

    A power supply for battery-powered systems has been designed with an embedded controller that is capable of monitoring and maintaining batteries, charging hardware, while maintaining output power. The power supply is primarily designed for rovers and other remote science and engineering vehicles, but it can be used in any battery alone, or battery and charging source applications. The supply can function autonomously, or can be connected to a host processor through a serial communications link. It can be programmed a priori or on the fly to return current and voltage readings to a host. It has two output power busses: a constant 24-V direct current nominal bus, and a programmable bus for output from approximately 24 up to approximately 50 V. The programmable bus voltage level, and its output power limit, can be changed on the fly as well. The power supply also offers options to reduce the programmable bus to 24 V when the set power limit is reached, limiting output power in the case of a system fault detected in the system. The smart power supply is based on an embedded 8051-type single-chip microcontroller. This choice was made in that a credible progression to flight (radiation hard, high reliability) can be assumed as many 8051 processors or gate arrays capable of accepting 8051-type core presently exist and will continue to do so for some time. To solve the problem of centralized control, this innovation moves an embedded microcontroller to the power supply and assigns it the task of overseeing the operation and charging of the power supply assets. This embedded processor is connected to the application central processor via a serial data link such that the central processor can request updates of various parameters within the supply, such as battery current, bus voltage, remaining power in battery estimations, etc. This supply has a direct connection to the battery bus for common (quiescent) power application. Because components from multiple vendors may have

  18. Comparison of centralized and decentralized energy supply systems

    OpenAIRE

    Pfeifer, Thomas; Fahl, Ulrich; Voß, Alfred

    1991-01-01

    Communal energy programs are often embedded in a conception of a decentralized energy supply system where electricity is produced by a number of smaller power plants. For a comprehensive survey the question arises whether these decentralized systems are more advantageous than centralized systems with regard to the criterions energy consumption, safety of supply, environmental compatibility and economy. In the following, after a definition of the term "decentralized", the present structure of ...

  19. Nuclear Co-generation: The Analysis of Technical Capabilities and Cost Estimates

    Directory of Open Access Journals (Sweden)

    Andrzej Reński

    2016-09-01

    Full Text Available This paper presents a concept of the parallel connection of a nuclear power plant fitted to provide heat for district heating application, with the CHP and heat plants existing in the supply region, in this case with the heating systems of Wejherowo and Gdynia. Presented variant proposes to add heat to a nuclear power plant’s total output by supplying heat exchangers with the steam from bleeders of low pressure (LP turbine stage and from the crossover pipe between its high pressure (HP and intermediate pressure (IP stages. A detailed diagram of the EPR nuclear turbine system adapted to supply district heat is also presented. Also determined are the formulas for: electric power output of a nuclear CHP plant; electric power generated strictly in cogeneration, and the decrease in the electric power and energy resulting from the operation in cogeneration mode. Finally, the profitability (competitiveness criteria for a nuclear power plant adapted to supply district heat in a selected heat supply region were proposed.

  20. ASCERTAINMENT OF ELECTRIC-SUPPLY SCHEMES RELIABILITY FOR THE ATOMIC POWER PLANT AUXILIARIES

    Directory of Open Access Journals (Sweden)

    A. L. Starzhinskij

    2015-01-01

    Full Text Available The paper completes ascertainment of electrical-supply scheme reliability for the auxiliaries of a nuclear power plant. Thereat the author considers the system behavior during the block normal operation, carrying out current maintenance, and capital repairs in combination with initiating events. The initiating events for reactors include complete blackout, i.e. the loss of outside power supply (normal and reserve; emergency switching one of the working turbogenerators; momentary dumping the normal rating to the level of auxiliaries with seating the cutout valve of one turbo-generator. The combination of any initiating event with the repairing mode in case of one of the system elements failure should not lead to blackout occurrence of more than one system of the reliable power supply. This requirement rests content with the help of the reliable power supply system self-dependence (electrical and functional and the emergency power-supply operational autonomy (diesel generator and accumulator batteries.The reliability indicators of the power supply system for the nuclear power plant auxiliaries are the conditional probabilities of conjoined blackout of one, two, and three sections of the reliable power supply conditional upon an initiating event emerging and the blackout of one, two, and three reliable power-supply sections under the normal operational mode. Furthermore, they also are the blackout periodicity of one and conjointly two, three, and four sections of normal operation under the block normal operational mode. It is established that the blackout of one bus section of normal operation and one section of reliable power-supply system of the auxiliaries that does not lead to complete blackout of the plant auxiliaries may occur once in three years. The probability of simultaneous power failure of two or three normal-operation sections and of two reliable power-supply sections during the power plant service life is unlikely.

  1. Security of supply and line flow following the shut-down of nuclear power plants in Germany. Have shortages to be expected?

    International Nuclear Information System (INIS)

    Kunz, Friedrich; Moest, Dominik

    2011-01-01

    This paper, which examines the impacts of phasing out nuclear power in Germany, is the first to include an analysis of energy supply security and critical line flows in both the German and Central European electricity networks. The technical-economic model of the European electricity market, ELMOD, is used to simulate alternative power plant dispatch, imports, exports, and network use for a representative winter day. The results suggest that the shutdown of Germany's nuclear plants will result in higher net imports, especially from the Netherlands, Austria, and Poland, and that electricity generation from fossil fuels will increase slightly in Germany and in Central Europe. We find that no additional imports will come from nuclear plants since they are already fully utilized in the merit order, and that electricity prices will rise on average by a few Euros per MWh. We conclude that closing the seven nuclear power plants within the government's moratorium will cause no significant supply security issues or network constraints and an eventual full phase-out seem to be possible due to the completion of several new conventional power plants now under construction. Finally, we suggest that a nuclear phase-out in Germany within the next 3-7 years will not undermine security of supply and network stability in Germany and Central Europe.

  2. Thermionic nuclear reactor systems

    International Nuclear Information System (INIS)

    Kennel, E.B.

    1986-01-01

    Thermionic nuclear reactors can be expected to be candidate space power supplies for power demands ranging from about ten kilowatts to several megawatts. The conventional ''ignited mode'' thermionic fuel element (TFE) is the basis for most reactor designs to date. Laboratory converters have been built and tested with efficiencies in the range of 7-12% for over 10,000 hours. Even longer lifetimes are projected. More advanced capabilities are potentially achievable in other modes of operation, such as the self-pulsed or unignited diode. Coupled with modest improvements in fuel and emitter material performance, the efficiency of an advanced thermionic conversion system can be extended to the 15-20% range. Advanced thermionic power systems are expected to be compatible with other advanced features such as: (1) Intrinsic subcritically under accident conditions, ensuring 100% safety upon launch abort; (2) Intrinsic low radiation levels during reactor shutdown, allowing manned servicing and/or rendezvous; (3) DC to DC power conditioning using lightweight power MOSFETS; and (4) AC output using pulsed converters

  3. Analysis of Nuclear Option in Planning on Java Bali Integrated Electricity System By Using Message Program

    International Nuclear Information System (INIS)

    Masdin; Sudi-Ariyanto; Nuryanti

    2004-01-01

    The growth of national energy demand in the future still become a great challenge for energy supply sector in Indonesia. The current energy supply strategy focuses the development and diversification of all energy options including fossil fuel, renewable energy and nuclear energy. Based on the Comprehensive Assessment Of Different Energy Source For Electricity Demand Study (CADES), final energy demand will grow from 4,065 PJ in 2000 to about 8,200 PJ in 2025. In this paper, the analysis of national energy system network will be divided into 2 regions, namely Java Bali region and Outside Java Bali region. Period of time horizon chosen in this study is 25 years (2000 to 2025). Simulation of network system configuration based on minimum objective function criteria was done by using MESSAGE (Model for Energy Supply Strategy Alternatives and their General Environmental Impacts) computer program. The focus of the analysis in this paper is simulation of electricity planning sector for Java Bali region. The result of simulation shows that for scenarios with no limitation on all fuel for power plant, scenario where fuel oil as constant supply for power plant and also configuration with limitation on gas supply, Nuclear Power Plant (NPP) does not appear during the study period using cost parameter set in this study. If there are limitations on gas supply and constrains of emissions (SO 2 and CO 2 ) due to coal combustion, NPP would become competitive and appear at about year 2015. (author)

  4. Public water supply sources - the practical problems

    International Nuclear Information System (INIS)

    Chambers, E.G.W.

    1990-01-01

    A complex system of reservoirs, streams, treatment works and pipe networks is used to provide the public water supply to consumers in Strathclyde. The manner in which a nuclear event would affect the quality of water available from this supply would depend on a wide variety of factors. The extent to which the quality from each source could be maintained or improved if found to be unsatisfactory would depend on the extent of contamination and the particular characteristics of each source. Development of contingency plans will incorporate monitoring of supplies and development of effective communications both internally and externally. (author)

  5. Future developments of power supply from nuclear fission and fusion until the middle of the 21st century

    International Nuclear Information System (INIS)

    1987-03-01

    The purpose of this study made by General Technology Systems (Netherlands) is to provide information about nuclear fission and fusion as methods for power generation, with which, in the framework of a study into the possibilities of durable energy sources, choices may be made from the various possibilities for future energy supply. The physical processes upon which the power generation relies are treated briefly. The technologies employed are discussed together with their changes and improvements, now and in the future, and the economic factors by which they are accompanied. How much of this energy will be used in the Netherlands, is discussed. In order to know the opinion of others about these subjects the dealers of the current nuclear power stations were asked to give their opinions which are collected in a supplement. 166 refs.; 18 figs.; 19 tabs

  6. Project for export system construction of nuclear equipment to IAEA; survey on current market status of the nuclear related international organizations and the domestic possible suppliers

    Energy Technology Data Exchange (ETDEWEB)

    Min, T S; Cho, H K; Kim, H J [Korea Atomic Industrial Forum, Seoul (Korea)

    2001-05-01

    Republic of Korea are keeping the dynamic activities in IAEA as the 8th advanced nuclear country over the world but has occupied very low late less than 0.01% in supplying the equipments to IAEA. About 6,000 nuclear equipment suppliers are registered in IAEA Supply Roster over the world but only 3 Suppliers of our country are registered in IAEA Supply Roster. The supply of nuclear industrial products equivalent to about 100 million dollars into IAEA market will endorse not only the international authorization for our technology and products but also give contribution to activate the domestic nuclear industries in order to increase its expert. The explanation for IAEA procurement market to the 53 nuclear companies will be made on May 16, 2001, and the participants for the export of their goods will be selected. And then we will do all possible supports by the government and related organizations for them to register in IAEA Supply Roster. 21 refs. (Author)

  7. Development and implementation of nuclear energy in energy system in Yugoslavia

    International Nuclear Information System (INIS)

    Ljubic, V.; Vukovic, D.; Vrhovac, S.

    1986-01-01

    All electrical demand analyses made in the last years show that besides hydro and thermal power plants in further development of electric power supply system in Yugoslavia, it will be necessary to approach successively with implementation of nuclear power plants. Quite a number of scientific and professional analyses have been done with the purpose to make the necessary conditions for the construction of nuclear power plants in the future. By reason of extra complexity and the necessity of the large amount of investment, it was concluded that the implementation, of nuclear energy in Yugoslavia has to be planned on uniform policy in development and uniform technological-technical concept. In the paper all till now finished activities in implementation of nuclear power plants in energy sector in Yugoslavia as well as planned future activities have been described. (author)

  8. Nuclear power and sustainable energy supply for Europe; Kernenergie im Kontext einer nachhaltigen Energieversorgung fuer Europa

    Energy Technology Data Exchange (ETDEWEB)

    Hilden, W. [Commission of the European Communities, Brussels (Belgium)

    2005-07-01

    The right energy mix is decisive. The European Commission feels that nuclear power can make an important contribution towards sustainable energy supply in Europe. Nuclear power should keep its place in the European energy mix. One important aspect in this regard is improved public acceptance through communication, transparency, and confidence building. High safety standards and a credible approach to the safe long-term management of radioactive waste are major components of this sustainable energy source. (orig./GL)

  9. Nuclear power supply (Japan Nuclear Safety Institute)

    International Nuclear Information System (INIS)

    Kameyama, Masashi

    2013-01-01

    After experienced nuclear disaster occurred on March 11, 2011, role of nuclear power in future energy share in Japan became uncertain because most public seemed to prefer nuclear power phase out to energy security or costs. Whether nuclear power plants were safe shutdown or operational, technologies were requisite for maintaining their equipment by refurbishment, partly replacement or pressure proof function recovery works, all of which were basically performed by welding. Nuclear power plants consisted of tanks, piping and pumps, and considered as giant welded structures welding was mostly used. Reactor pressure vessel subject to high temperature and high pressure was around 200mm thick and made of low-alloy steels (A533B), stainless steels (308, 316) and nickel base alloys (Alloy 600, 690). Kinds of welding at site were mostly shielded-metal arc welding and TIG welding, and sometimes laser welding. Radiation effects on welding of materials were limited although radiation protection was needed for welding works under radiation environment. New welding technologies had been applied after their technical validation by experiments applicable to required regulation standards. Latest developed welding technologies were seal welding to prevent SCC propagation and temper-bead welding for cladding after removal of cracks. Detailed procedures of repair welding of Alloy 600 at the reactor outlet pipe at Oi Nuclear Power Plants unit 3 due to PWSCC were described as an example of crack removal and water jet peening, and then overlay by temper-bead welding using Alloy 600 and clad welding using Alloy 690. (T. Tanaka)

  10. Nuclear reactor with makeup water assist from residual heat removal system

    Science.gov (United States)

    Corletti, Michael M.; Schulz, Terry L.

    1993-01-01

    A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path.

  11. Nuclear reactor with makeup water assist from residual heat removal system

    International Nuclear Information System (INIS)

    Corletti, M.M.; Schulz, T.L.

    1993-01-01

    A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path. 2 figures

  12. Nuclear reactor with makeup water assist from residual heat removal system

    Science.gov (United States)

    Corletti, M.M.; Schulz, T.L.

    1993-12-07

    A pressurized water nuclear reactor uses its residual heat removal system to make up water in the reactor coolant circuit from an in-containment refueling water supply during staged depressurization leading up to passive emergency cooling by gravity feed from the refueling water storage tank, and flooding of the containment building. When depressurization commences due to inadvertence or a manageable leak, the residual heat removal system is activated manually and prevents flooding of the containment when such action is not necessary. Operation of the passive cooling system is not impaired. A high pressure makeup water storage tank is coupled to the reactor coolant circuit, holding makeup coolant at the operational pressure of the reactor. The staged depressurization system vents the coolant circuit to the containment, thus reducing the supply of makeup coolant. The level of makeup coolant can be sensed to trigger opening of successive depressurization conduits. The residual heat removal pumps move water from the refueling water storage tank into the coolant circuit as the coolant circuit is depressurized, preventing reaching the final depressurization stage unless the makeup coolant level continues to drop. The residual heat removal system can also be coupled in a loop with the refueling water supply tank, for an auxiliary heat removal path. 2 figures.

  13. The situation of European power supply

    International Nuclear Information System (INIS)

    Zimmer, H.J.

    2008-01-01

    The requirement for energy worldwide is going to rise dramatically in the next few years and decades. Despite all developments of renewable energy sources, and despite the expansion of nuclear power in some industrialized countries and emerging countries, coal will turn out to be the key source of energy in the 21st century. Europe as a whole has a lot to offer which strengthens its position with respect to present and future requirements to be met in the construction of new power plants as well as in electricity and power supplies. As regards nuclear power in Germany, if it is to be given another chance, we must seek a dialog, pointing out that - nuclear power offers advantages in ensuring energy supply in Germany, given the development in the world energy markets; - nuclear power makes an important contribution to climate protection; - Germany's energy supply must be adapted to the global situation; - nuclear power offers opportunities in education, training, research and development; - nuclear power is contributing massively to our economic prosperity. The future viability of European power supply will not depend on the debate about nuclear power in Germany. The debate will be decided chiefly by the world market and on a European level. (orig.)

  14. An integrated mine development and supply system

    Energy Technology Data Exchange (ETDEWEB)

    Muguira, T. [Brambles Coal Services, Newcastle, NSW (Australia)

    1998-12-31

    In the face of intense global competition and other business pressures on coal miners, ongoing quality initiatives and continuous process improvements are needed to enhance business performance. By viewing a minesite interms of key processes, rather than departments, and employing innovative technologies and better applying organisational resources, there exists enormous potential to achieve reductions in process cost and time. The paper identifies and selects one critical coal mining process, namely the supply system, to think about how productivity improvements might occur and what changes might be employed to enhance overall system performance. While the supply system is one of few processes existing at a minesite, the paper addresses only the supply process, but includes interaction across traditional interdepartmental boundaries. The paper has been prepared for a wide audience and is based on experience and observation at several underground mines however some of the concepts are a result of dreaming in the face of global competition. 3 refs., 1 tab.

  15. French experience in transient data collection and fatigue monitoring of PWR's nuclear steam supply system

    International Nuclear Information System (INIS)

    Sabaton, M.; Morilhat, P.; Savoldelli, D.; Genette, P.

    1995-10-01

    Electricite de France (EDF), the french national electricity company, is operating 54 standardized pressurizer water reactors. This about 500 reactor-years experience in nuclear stations operation and maintenance area has allowed EDF to develop its own strategy for monitoring of age-related degradations of NPP systems and components relevant for plant safety and reliability. After more than fifteen years of experience in regulatory transient data collection and seven years of successful fatigue monitoring prototypes experimentation, EDF decided to design a new system called SYSFAC (acronym for SYsteme de Surveillance en FAtigue de la Chaudiere) devoted to transient logging and thermal fatigue monitoring of the reactor coolant pressure boundary. The system is fully automatic and directly connected to the on-site data acquisition network without any complementary instrumentation. A functional transient detection module and a mechanical transient detection module are in charge of the general transient data collection. A fatigue monitoring module is aimed towards a precise surveillance of five specific zones particularly sensible to thermal fatigue. After the first step of preliminary studies, the industrial phase of the SYSFAC project is currently going on, with hardware and software tests and implementation. The first SYSFAC system will be delivered to the pilot power plant by the beginning of 1996. The extension to all EDF's nuclear 900 MW is planned after one more year of feedback experience. (authors). 12 refs., 3 figs

  16. Troubleshooting of signal power supply system for Shanghai metro line 7

    Science.gov (United States)

    Lu, Kaixia; Xiao, Jie

    2018-03-01

    With the rapid development of Urban Rail Transit Signal Technology, the demand of signal power supply system for signal equipment is higher and higher. The signal intelligent power supply panel is the main component of the urban rail traffic signal power supply system. Whether the intelligent power supply panel working or not is directly related to traffic safety. The maintenance of intelligent signal power supply panel is particularly important. Line 7 of Shanghai Metro adopts PMZG Signal Intelligent Power Supply Panel, which is produced by Beijing Jinyujiaxin Polytron Technologies Inc. Maintenance of power supply system mainly includes routine maintenance and troubleshooting. This article will make clear the routine maintenance contents of PMZG Signal Intelligent Power Supply Panel, and put forward the common fault information and troubleshooting methods of PMZG Signal Intelligent Power Supply Panel. In accordance with the steps of fault handling, the faults can be eliminated in the shortest possible time, and PMZG Signal Intelligent Power Supply Panel can be quickly restored to normal working state.

  17. The Management System for Nuclear Installations. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This Safety Guide is applicable throughout the lifetime of a nuclear installation, including any subsequent period of institutional control, until there is no significant residual radiation hazard. For a nuclear installation, the lifetime includes site evaluation, design, construction, commissioning, operation and decommissioning. These stages in the lifetime of a nuclear installation may overlap. This Safety Guide may be applied to nuclear installations in the following ways: (a) To support the development, implementation, assessment and improvement of the management system of those organizations responsible for research, site evaluation, design, construction, commissioning, operation and decommissioning of a nuclear installation; (b) As an aid in the assessment by the regulatory body of the adequacy of the management system of a nuclear installation; (c) To assist an organization in specifying to a supplier, via contractual documentation, any specific element that should be included within the supplier's management system for the supply of products. This Safety Guide follows the structure of the Safety Requirements publication on The Management System for Facilities and Activities, whereby: (a) Section 2 provides recommendations on implementing the management system, including recommendations relating to safety culture, grading and documentation. (b) Section 3 provides recommendations on the responsibilities of senior management for the development and implementation of an effective management system. (c) Section 4 provides recommendations on resource management, including guidance on human resources, infrastructure and the working environment. (d) Section 5 provides recommendations on how the processes of the installation can be specified and developed, including recommendations on some generic processes of the management system. (e) Section 6 provides recommendations on the measurement, assessment and improvement of the management system of a nuclear

  18. Energy supply concepts in the 21st century - the role of nuclear power. 2002 winter meeting of 'Deutsches Atomforum'

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    The 2002 Winter Meeting organized by the Deutsches Atomforum e.V. was devoted to the topic of 'Energy Supply in the 21st Century - the Role of Nuclear Power'. Before a large audience of participants from Germany and abroad experts from science and research, industry and politics discussed a broad range of problems arising with respect to the future national, European, and global structure of energy supply. The new impulses nuclear power is receiving in the United States and in Finland were presented along with the contributions potentially coming from non-nuclear sources of energy, including the importance of renewable energies. The conclusion to be drawn from all contributions is the recognition that boundary conditions and constraints demand a balanced energy mix, which can be achieved only in a liberal environment free from any political or ideological discrimination. (orig.) [de

  19. Economic Analysis for Nuclear Hydrogen Production System Based on HyS Process

    International Nuclear Information System (INIS)

    Yang, Kyeong Jin; Lee, Ki Young; Lee, Tae Hoon; Chang, Jong Hwa

    2009-01-01

    The current promising base for massive hydrogen production on high temperature environment derives primarily from three sources: the commercial production of chemicals for the sulfur-iodine (SI) process, the development of solid-oxide fuel cells (SOFC), and the hybrid method of chemicals and fuel cells. The three kinds of process requires high temperature heat energy over 850∼950 .deg. C for the efficient and economic hydrogen production. One of the clean, economic, and moreover promising heat sources supplied to the process is nuclear plants. The nuclear plants producing high temperature heat energy over 950 .deg. C are well known as Very High Temperature Reactors (VHTR) which could have two types of prismatic and pebble-bed cores along reactor core shape. In this paper, we report on the Hybrid Sulfur Process (HyS), and the estimated costs for the system which composes of VHTR of prismatic core type and HyS plant. Nuclear hydrogen production system based on HyS process has been configured to optimally use the thermal energy from VHTR and electric energy to produce hydrogen and oxygen from clean water. High temperature thermal energy is transferred to the HyS process by way of intermediate heat exchanger (IHX) with associated piping. In this paper, the hydrogen production costs for a system composed of a VHTR with six 600MWth module, a power conversion unit (PCU) and a HyS plant are presented, where the thermal energy produced in two module was converted to electric energy in PCU and then transferred to the electrolysis cells for hydrogen production and circulating units on HyS plant, and the remaining thermal energy was supplied to chemical process on HyS plants. As a preliminary study of cost estimates for nuclear hydrogen systems, the hydrogen production costs of the nuclear energy sources benchmarking GT-MHR are estimated in the necessary input data on a Korean specific basis. G4- ECONS was appropriately modified to calculate the cost for hydrogen production

  20. Design of make-up water system for Tehran research reactor spent nuclear fuels storage pool

    Energy Technology Data Exchange (ETDEWEB)

    Aghoyeh, Reza Gholizadeh [Reactor Research Group, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), North Amirabad, P.O. Box 14155-1339, Tehran (Iran, Islamic Republic of); Khalafi, Hosein, E-mail: hkhalafi@aeoi.org.i [Reactor Research Group, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran (AEOI), North Amirabad, P.O. Box 14155-1339, Tehran (Iran, Islamic Republic of)

    2010-10-15

    Spent nuclear fuels storage (SNFS) is an essential auxiliary system in nuclear facility. Following discharge from a nuclear reactor, spent nuclear fuels have to be stored in water pool of SNFS away from reactor to allow for radioactive to decay and removal of generated heat. To prevent corrosion damage of fuels and other equipments, the storage pool is filled with de-ionized water which serves as moderator, coolant and shielding. The de-ionized water will be provided from make-up water system. In this paper, design of a make-up water system for optimal water supply and its chemical properties in SNFS pool is presented. The main concern of design is to provide proper make-up water throughout the storage time. For design of make-up water system, characteristics of activated carbon purifier, anionic, cationic and mixed-bed ion-exchangers have been determined. Inlet water to make-up system provide from Tehran municipal water system. Regulatory Guide 1.13 of the and graver company manual that manufactured the Tehran research reactor (TRR) make-up water system have been used for make-up water system of TRR spent nuclear fuels storage pool design.

  1. Design of make-up water system for Tehran research reactor spent nuclear fuels storage pool

    International Nuclear Information System (INIS)

    Aghoyeh, Reza Gholizadeh; Khalafi, Hosein

    2010-01-01

    Spent nuclear fuels storage (SNFS) is an essential auxiliary system in nuclear facility. Following discharge from a nuclear reactor, spent nuclear fuels have to be stored in water pool of SNFS away from reactor to allow for radioactive to decay and removal of generated heat. To prevent corrosion damage of fuels and other equipments, the storage pool is filled with de-ionized water which serves as moderator, coolant and shielding. The de-ionized water will be provided from make-up water system. In this paper, design of a make-up water system for optimal water supply and its chemical properties in SNFS pool is presented. The main concern of design is to provide proper make-up water throughout the storage time. For design of make-up water system, characteristics of activated carbon purifier, anionic, cationic and mixed-bed ion-exchangers have been determined. Inlet water to make-up system provide from Tehran municipal water system. Regulatory Guide 1.13 of the and graver company manual that manufactured the Tehran research reactor (TRR) make-up water system have been used for make-up water system of TRR spent nuclear fuels storage pool design.

  2. Protection and switching system for the RFX power supply

    International Nuclear Information System (INIS)

    Browning, J.L.; Gray, J.W.; Mace, T.A.; Varley, G.L.

    1986-01-01

    The RFX toroidal field power supply comprises a large 4.8MJ (max) modular capacitor bank and four 14MW AC/DC converter flat-top power supply modules. The high fault level associated with the capacitor banks presents a problem in the design of the switching system, since mistiming could produce large currents in the flat-top supplies. The poloidal circuit consists of four groups of magnetising windings connected in series, each with its own flat-top convertor supply and opening switch transfer system. The flat-top converter supplies are needed when the transfer voltage has fallen from approximately 40kV to 1kV. Solutions to the problem of designing a fault-tolerant system which presents no danger to the flat-top converters are described in the paper. The adopted methods make use of hybrid ignitron/mechanical switches to give the required combination of switching speed and current carrying capacity, together with careful attention to the circuit layout of different switching elements. (author)

  3. Technical and economic studies of small reactors for supply of electricity and steam

    International Nuclear Information System (INIS)

    Spiewak, I.; Klepper, O.H.; Fuller, L.C.

    1977-01-01

    Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out of several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 313 MW(t) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000 MW(t), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500 MW(t) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating or desalination

  4. Technical and economic studies of small reactors for supply of electricity and steam

    International Nuclear Information System (INIS)

    Spiewak, I.; Klepper, O.H.; Fuller, L.C.

    1977-02-01

    Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out for several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 365 MW(th) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000 MW(th), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500 MW(th) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule, and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating, or desalination

  5. Technical and economic studies of small reactors for supply of electricity and steam

    International Nuclear Information System (INIS)

    Spiewak, I.; Klepper, O.H.; Fuller, L.C.

    1977-01-01

    Several years ago conventional opinion held that nuclear power plants must be very large to be competitive with fossil fuels. This situation has changed markedly in most countries within recent years, as oil and gas supplies have become more scarce and costly. Studies have been carried out of several nuclear steam supply systems in the small and intermediate size range. Detail studies are reported of the Consolidated Nuclear Steam Generator (CNSG), a 313MW(th) pressurized water reactor being developed by Babcock and Wilcox, as applied to industrial energy needs. Both conventional and barge-mounted nuclear steam supply systems are considered. Conceptual studies have been started of pressurized and boiling water reactors in the range of 1000MW(th), which are envisioned for utility operation for supply of electric power and steam. Design studies of a 500MW(th) high temperature reactor are also reported. The small reactors are expected to have higher unit costs than the large commercial plants, but to have compensating advantages in higher plant availability, shorter construction schedule and greater siting flexibility. Studies are also reported of power cycle parameters and cost allocations for extraction of steam from steam turbine plants. This steam could be used for industrial energy, district heating or desalination. (author)

  6. The Regulation of Nuclear Trade: Non-Proliferation-Supply-safety

    International Nuclear Information System (INIS)

    1988-01-01

    Volume II of the study on the regulation of nuclear trade deals with the national legislation of OECD countries with significant nuclear programmes and regulations in that field and, in essence, covers two aspects. The first concerns political and administrative controls over imports and exports of sensitive products, namely fissile materials and large nuclear equipment as well as technology transfers. In most cases, this description of the provisions applicable is completed with the list of nuclear items whose export is restricted. The second aspect concerns the licensing system governing trade in as well as the import and export of nuclear material to protect users and the public against the hazards created by its radioactive properties. This volume also contains information on regulations concerning physical protection, industrial property and transport, as well as on multilateral and bilateral agreements involving nuclear trade. (NEA) [fr

  7. A new power supply for superconductive magnetic energy storage system

    International Nuclear Information System (INIS)

    Karady, G.G.; Han, B.M.

    1992-01-01

    In this paper a new power supply for a superconductive magnetic energy storage system, which permits a fast independent regulation of the active and reactive power, is presented. The power supply is built with several units connected in parallel. Each unit consists of a 24-pulse bridge converter, thyristor-switched tap-changing transformer, and thyristor-switched capacitor bank. Its system operation is analyzed by computer simulation and a feasible system realization is shown. A superconductive magnetic energy storage system with the proposed power supply has the capability of leveling the load variation, damping the low-frequency oscillation, and improving the transient stability in the power system. This power supply can be built with commercially available components using well-proven technologies

  8. The spanish electric system operation. The contribution of nuclear generation

    International Nuclear Information System (INIS)

    Duvison, M. R.; Torre, M. de la

    2009-01-01

    Operation of an electric system encloses the collection of activities which extend from affective generation dispatch to issuing instruction for network manoeuvring along with international exchange scheduling. Based on the market mechanisms that apply to energy transactions, these tasks guarantee the security of supply end consumers, which is the final goal of the System Operators actions. In Spain this function is executed by Red Electrica de Espana (REE) since 1985, after being constituted as the first Transmission and System Operator (TSO) in the world. Additionally the variations to Law 54/1997 introduced by law 17/2007 also assign REE the function of sole transmission owner in the Spanish electric system. In order to achieve the aforementioned goal, nuclear energy plays in Spain a fundamental role in electric generation thanks to its high availability rate, the predictability of its fuel recharges, its high operational reliability, its geographical location, the stability of its costs and the security of supply given by the possibility of on-site fuel storage in the power plant. (Author)

  9. Nuclear systems of the future. Stakes, R and D strategy, and international cooperation

    International Nuclear Information System (INIS)

    2005-01-01

    As demonstrated by prospective studies, nuclear energy will represent a decisive contribution in the future energy mix. The long-term strategy of development of nuclear energy requires to foresee a new generation of nuclear systems, named generation 4. The goal of these new systems is to optimize the use of nuclear fuels, to minimize the generation of wastes and to enlarge the field of applications of nuclear energy to other applications like: hydrogen and synthetic fuels generation, heat generation for the industry etc. This document presents the French R and D strategy on nuclear systems of 4. generation that has been approved by the public authorities. This strategy follows three axes: a priority research on fast neutron systems with fuel recycle (sodium fast reactors (SFR) and gas fast reactors (GFR)), a research on key-technologies for the supply of very high temperature heat (very high temperature reactor (VHTR), fast and thermal neutron reactors, and water decomposition processes), and a continuation of researches on PWR reactors improvement. An integral recycling of all actinides in fast neutron reactors requires the development of new fuel reprocessing and fuel re-fabrication processes. A reference scenario for the progressive renewal of French nuclear facilities foresees the simultaneous development of fast neutron systems and the start-up of a new spent fuel reprocessing plant. France in involved in the development of the SFR, GFR and VHTR systems thanks to its participation to the Generation 4 international forum and to bilateral cooperation with other big nuclear partners like Russia and China. One of the main stakes of the French nuclear industry is to be able to invest in the R and D of future nuclear systems in order to valorize the experience gained so far in sodium FBR systems and in fuel cycle processes. (J.S.)

  10. A nuclear power enterprise debt management system construction Based on Sanmen Nuclear Power Co., LTD, debt risk management case analysis

    International Nuclear Information System (INIS)

    Wu Yan; Liu Shuqing

    2010-01-01

    Building nuclear power enterprises need huge investment , often tens of billions RMB. How to do a good job in corporate debt risk management, becoming powerful large-scale development of nuclear power ,ensuring the supply of funds and existing debt service in the process of large-scale development of nuclear power ,is an important task. In this paper, managing the company's debt is very urgent and necessary through analysis of SMNPC financing and debt structure; through the analysis of SMNPC's debt risk management , the authors would like to explore how to build up the framework of the debt management under the large-scale development of nuclear power construction . Nuclear power enterprises need to strengthen supervision mechanism and internal control,build-up and perfect all-round debt risk manage system, keep watch on debt risk in order to ensure preservation and increment of the value of state assets. (authors)

  11. Analysis of uranium supply to 2050

    International Nuclear Information System (INIS)

    Underhill, D.H.

    2000-01-01

    Nuclear power is expected to be an important part of the world-wide energy mix at least through the next 50 years and by most projections well beyond. That is, of course, provided an adequate supply of uranium is available to sustain the nominal growth rate for nuclear power of 1 to 3% per year that is projected by many analysts. The importance that a reliable supply will have on the future of nuclear power led the IAEA to undertake a study of uranium supply-demand relationships through 2050. The ultimate goal of the study is to evaluate the adequacy of supply to meet demand, and to characterize the level of confidence that can be placed in the projected supply. This report describes key conclusions of the study. A detailed report describing the results of the study is available as an IAEA Special Publication

  12. Control system for a nuclear power producing unit

    International Nuclear Information System (INIS)

    Durrant, O.W.

    1978-01-01

    The invention provides in a control system for a nuclear power producing unit comprising a pressurized water reactor, a once-through steam generator provided with feedwater supply means, a turbine-generator supplied with steam from the steam generator and means maintaining a flow of pressurized water through the reactor and steam generator. The combination comprising; means generating a feed forward control signal proportional to the desired power output of the power producing unit, a second means for adjusting the reactor heat release, a third means for adjusting the rate of flow of feedwater to the steam generator, the second and third means solely responsive to and operated in parallel from the feed forward control signal whereby the reactor heat release and the rate of flow of feedwater to the steam generator are each maintained in a discrete functional relationship to the feed forward control signal

  13. Integral evaluation of energy supply systems at mountain refuges

    Energy Technology Data Exchange (ETDEWEB)

    Aschauer, C. [Univ. of Natural Resources and Applied Life Sciences, Vienna (Austria). Inst. for Chemical and Energy Engineering; Steinbacher, G. [Steinbacher and Steinbacher Civil Engineering Inc. (Austria); Weber, P. [DAV-Deutscher Alpenverein e.V. (Germany). Bundesgeschaeftsstelle; Deubler, Hubert

    2010-07-01

    Most of the mountain refuges scattered over the Alps (more than 1500) are not connected to public infrastructure, requiring decentralized supply and disposal and are therefore called island systems. The increasing number of guests goes along with a higher demand for comport and thus puts pressure on available resources. There are numerous challenges like remoteness, transport, low temperatures, seasonal operation and climate change to be faced. Furthermore, the supply and disposal system of an alpine hut has to merge different interests of the alpine associations, refuge operators, legal authorities and the alpine tourists. Therefore the respective infracstructure has to be managed as an overall-self-contained system. Energy supply is the central issue showing complex interaction with water supply, wastewater treatment and waste disposal. Many problems according to planning, decision-making, construction and operation concerning alpine infrastructure are reported. However detailed information on experiences made in these fields is missing at an international level so far. To correct this lack of data, the German Alpine Association (DAV) initiated the project ''Integral Evaluation of Supply and Disposal Systems of Mountain Refuges, IEVEBS'' in 2006, inviting all stakeholders (Alpine Associations, Legal Authorities, Planners, and Researchers) to participate. Additionally to the final project report which contains a detailed description and evaluation of the supply systems, guidelines will be elaborated in 2010 for planning, implementation and operation, all applicable at an international level. (orig.)

  14. Retrofit of existing Dow solidification system at quad cities nuclear station

    International Nuclear Information System (INIS)

    Dekitis, L.; Jarvis, N.; Petri, R.; Testa, J.

    1983-01-01

    Over the past year ATCOR has been involved in the design, testing and supply of an In-container Mixing System Retrofit for Commonwealth Edison's Quad Cities Nuclear Station Solidification System. The system supplied by DOW, itself a retrofit of a urea formaldehyde system, was based upon use of 50 cubic foot containers (liners). ATCOR's retrofit increased liner capacity to 170 cubic feet and allowed in-cask solidification of highly radioactive material. This paper discusses the reasons for the decision to replace equipment within the originally furnished system and the development of the ATCOR plan to proof-test this equipment prior to delivery at the site. Results of this pre-testing, and a comparison between pre-tested conditions and the actual in-plan start-up tests are presented. Development of improved instrumentation and mechanical modifications which enhance the reliability of the ATCOR/DOW process In-container Mixing System was provided as a part of this project. Test results are presented on instruments, controls and the unique method of mechanical attachment of the Mixing Head to the solidification container

  15. MODEL BASED BIOMASS SYSTEM DESIGN OF FEEDSTOCK SUPPLY SYSTEMS FOR BIOENERGY PRODUCTION

    Energy Technology Data Exchange (ETDEWEB)

    David J. Muth, Jr.; Jacob J. Jacobson; Kenneth M. Bryden

    2013-08-01

    Engineering feedstock supply systems that deliver affordable, high-quality biomass remains a challenge for the emerging bioenergy industry. Cellulosic biomass is geographically distributed and has diverse physical and chemical properties. Because of this feedstock supply systems that deliver cellulosic biomass resources to biorefineries require integration of a broad set of engineered unit operations. These unit operations include harvest and collection, storage, preprocessing, and transportation processes. Design decisions for each feedstock supply system unit operation impact the engineering design and performance of the other system elements. These interdependencies are further complicated by spatial and temporal variances such as climate conditions and biomass characteristics. This paper develops an integrated model that couples a SQL-based data management engine and systems dynamics models to design and evaluate biomass feedstock supply systems. The integrated model, called the Biomass Logistics Model (BLM), includes a suite of databases that provide 1) engineering performance data for hundreds of equipment systems, 2) spatially explicit labor cost datasets, and 3) local tax and regulation data. The BLM analytic engine is built in the systems dynamics software package PowersimTM. The BLM is designed to work with thermochemical and biochemical based biofuel conversion platforms and accommodates a range of cellulosic biomass types (i.e., herbaceous residues, short- rotation woody and herbaceous energy crops, woody residues, algae, etc.). The BLM simulates the flow of biomass through the entire supply chain, tracking changes in feedstock characteristics (i.e., moisture content, dry matter, ash content, and dry bulk density) as influenced by the various operations in the supply chain. By accounting for all of the equipment that comes into contact with biomass from the point of harvest to the throat of the conversion facility and the change in characteristics, the

  16. The expansion of nuclear energy in industrialized and developing countries: Reasons, market shares, fissile material supply and waste management

    International Nuclear Information System (INIS)

    Schwarz, D.

    1992-01-01

    At present there are more ethical-anthropological reasons than economic ones which speak for an expansion of nuclear energy: Ecological, climatic, peace and resource policy problems which most porbably will be unsolvable by real human beings and expensive methods leaving out nuclear energy. The risks resulting from that exceed by several orders of magnitude the risk which would be involved in the operation of various thousands of modern nuclear power plants. Most of the nuclear power plants are and will be operated today and tomorrow in industrialized countries; however, some of them are running already today in several threshold countries. Therefore the safety of nuclear power plants must be such as to permit their construction anywhere. Together with intensified saving, nuclear energy can solve energy policy problems in all sectors of the energy market predominantly in a non-fossil way, namely by taking over almost the entire power generation, by economical application of power instead of fossil fuels, rendering at the same time a large number of energy services, and supplying process and heating heat. Uranium supply will be solved internationally by prospection and increased uranium exploitation, or by the breeder, at economically reasonable cost. Safe waste management is technically feasible. Lack of acceptance neccessitates at present safe intermediate storage at reasonable cost. When discussing this question the ethical aspect of nuclear energy expansion should be stressed. (orig./UA) [de

  17. Financing of power supply systems and pollution control equipment. Models, dimensions, developments

    Energy Technology Data Exchange (ETDEWEB)

    Radtke, G; Raabe, G

    1988-11-01

    The authors explain the bankers' point of view of the financial and economic aspects of developments in the energy sector, discussing the financing of natural gas pipelines (Muro, Megal, etc.), of nuclear power plant construction, of projects in the oil supply sector, and of pollution abatement measures and equipment for the power industry and other industries. The different financial situations of small firms or large firms supplying pollution control equipment are discussed referring to the financing schemes to be set up, explaining among other things the profitability assessment taking into account long-term development or delays in return on capital investment from borrowed funds as induced, e.g., by delays in the licensing procedure. Future demand for borrowed capital for pollution control or nuclear power plant development is difficult to assess by the banking circles. (orig./RST).

  18. Instrumentation control system in nuclear power plant

    International Nuclear Information System (INIS)

    Hanai, Koi; Tai, Ichiro.

    1982-01-01

    Purpose: To improve the reliability of instrumentation control system in a nuclear power plant by using an optical fiber cable as a transmission path between a multiplexer and a central control room to thereby eliminate noises resulted from electromagnetic inductions or the likes. Constitution: Signals from neutron detectors are sent by way of ceramic-insulated cables to pre-amplifiers disposed outside of the pressure vessel of a nuclear reactor, converted into voltage pulse signals and then sent by way of coaxial cables to a multiplexer. The multiplexer receives a plurality of voltage pulse signals corresponding to the neutron detectors respectively, converts them into a time-shared electric signal train and sends it to an optical pulse transmitter. The transmitter converts the supplied signals into an optical pulse signal train corresponding to the electric signal train from the multiplexer and sends it by way of an optical fiber cable to an optical pulse receiver disposed in a central control room. (Kawakami, Y.)

  19. The upgraded PSI application in the BEPCⅡ power supply control system

    International Nuclear Information System (INIS)

    Li Jiangqi; Wang Xiaoli; Wang Chunhong; Liu Jia

    2011-01-01

    There are about 460 magnet power supplies in the two rings and the transport lines of the BEPCⅡ which are controlled by the power supply controller and the power supply interface. An upgraded Power Supply Interface (PSI-Ⅱ) was developed for replacing the old one in the power supply control system of the BEPCⅡ. It will firstly describe feature of the PSI-Ⅱ and difference from the PSI. Then, discuss performance test of the PSI-Ⅱ well as its application in the power supply control system. (authors)

  20. World nuclear performance report 2016. A new study by World Nuclear Association

    Energy Technology Data Exchange (ETDEWEB)

    Cobb, Jonathan [World Nuclear Association, London (United Kingdom)

    2016-08-15

    A larger number of nuclear power units are under construction than at any other time in the last 25 years, and with another ten new reactors coming online 2015 demonstrated improving new build performance all round. The existing global fleet, totally 439 by year-end, generated roughly 10 % of the world's electricity, making up around one-third of the world's low-carbon electricity supply. Nevertheless, there are challenges ahead for the global nuclear industry. The World Nuclear Association's vision for the future global electricity system consists of a diverse mix of low-carbon technologies - where renewables, nuclear and a fossil fuels work together in harmony to ensure a reliable, affordable and clean energy supply.

  1. World nuclear performance report 2016. A new study by World Nuclear Association

    International Nuclear Information System (INIS)

    Cobb, Jonathan

    2016-01-01

    A larger number of nuclear power units are under construction than at any other time in the last 25 years, and with another ten new reactors coming online 2015 demonstrated improving new build performance all round. The existing global fleet, totally 439 by year-end, generated roughly 10 % of the world's electricity, making up around one-third of the world's low-carbon electricity supply. Nevertheless, there are challenges ahead for the global nuclear industry. The World Nuclear Association's vision for the future global electricity system consists of a diverse mix of low-carbon technologies - where renewables, nuclear and a fossil fuels work together in harmony to ensure a reliable, affordable and clean energy supply.

  2. A simple levitation system using wireless power supply system and Lorentz force

    International Nuclear Information System (INIS)

    Oka, Koichi; Tanaka, Masako

    2016-01-01

    A new type of magnetic levitation mechanism has been proposed. The feature of this mechanism is using wireless power supply system and Lorentz forces for levitation. The stability of levitation is performed by passive control by magnetic flux configuration between permanent magnets and active control of electromagnets. In this paper, the concept of levitation mechanism is introduced, FEM analyses for levitation force and wireless power supply performance is examined. In concept two types of levitation systems which are different on the point of active control directions are introduced. In FEM analyses, the required current for levitation and the directions of generating forces are calculated. In the study of wireless power supply system, the required voltage for the levitation is expected. Finally the feasibility of the proposed levitation system will be verified. (paper)

  3. Korean experiences on nuclear power technology

    International Nuclear Information System (INIS)

    Kim, H.; Yang, H.

    1994-01-01

    This paper describes the outstanding performance of the indigenous development program of nuclear power technology such as the design and fabrication of both CANDU and PWR fuel and in the design and construction of nuclear steam supply system in Korea. The success has been accomplished through the successful technology transfer from foreign suppliers and efficient utilization of R and D manpower in the design and engineering of nuclear power projects. In order to implement the technology transfer successfully, the joint design concept has been introduced along with effective on-the-job training and the transfer of design documents and computer codes. Korea's successful development of nuclear power program has resulted in rapid expansion of nuclear power generation capacity in a short time, and the nuclear power has contributed to the national economy through lowering electricity price by about 50 % as well as stabilizing electricity supply in 1980s. The nuclear power is expected to play a key role in the future electricity supply in Korea. Now Korea is under way of taking a step toward advanced nuclear technology. The national electricity system expansion plan includes 18 more units of NPPs to be constructed by the year 2006. In this circumstance, the country has fixed the national long-term nuclear R and D program (lgg2-2001) to enhance the national capability of nuclear technology. This paper also briefly describes future prospects of nuclear technology development program in Korea

  4. Aerial radiological survey of the Washington. Date of survey: July 1982 Public Power Supply System (WPPSS) Nuclear Project and surrounding area, Richland, Washington

    International Nuclear Information System (INIS)

    1983-07-01

    An aerial radiological survey was performed from 14 to 20 July 1982 over a 270-square-kilometer area centered on the Washington Public Power Supply System (WPPSS) Nuclear Project located near Richland, Washington. All gamma ray data were collected by flying parallel lines spaed 152 meters (500 feet) apart at an altitude of 91 meters (300 feet) above ground level. Count rates obtained from the aerial platform were converted to total external exposure rates at 1 meter above the ground and are presented in the form of an isoradiation contour map. The observed exposure rates ranged from 5 to 15 microroentgens per hour (μR/h) with the average background ranging from 9 to 12μR/h. These values include an estimated cosmic ray contribution of 3.7 μR/h. The exposure rates obtained from ground-based measurements taken in background locations within the survey area displayed positive agreement the aerial data

  5. City gas supply management system. Toshi gas kyokyu kanri system

    Energy Technology Data Exchange (ETDEWEB)

    Ota, S [Tokyo Gas Co. Ltd., Tokyo (Japan)

    1991-07-05

    Supply and control system of city gas (about 90% is LNG) at Tokyo Gas Company is summarized. The LNG is delivered from the high pressure, A-middle pressure and B-middle pressure stations through the low pressure governors at about 3,000 locations to the low-pressure conduit networks. The information system department uses a large-size general purpose IBM computer as a host computer, control computers at each station, and communication networks consisted mainly of the in-house wireless networks. The trunk lines are all looped, and the important facilities are dualized. Characteristic functions include the supply prediction, which takes into account the past supply and ambient temperature records, a day of the week for a particular date, and demand fluctuation trends; adjustments of each holder based on the prediction and restrictions; and piping network simulation to decide gas manufacturing patterns, and determine reasonability of local construction of complicated conduits. The monitoring and control system as the central nerve includes a quick block-wide operation at an accident from earthquake and the like to prevent wide area disasters. 8 figs., 1 tab.

  6. Leaks in the internal water supply piping systems

    OpenAIRE

    Orlov Evgeniy Vladimirovich; Komarov Anatoliy Sergeevich; Mel’nikov Fedor Alekseevich; Serov Aleksandr Evgen’evich

    2015-01-01

    Great water losses in the internal plumbing of a building lead to the waste of money for a fence, purification and supply of water volumes in excess. This does not support the concept of water conservation and resource saving lying today in the basis of any building’s construction having plumbing. Leakage means unplanned of water losses systems in domestic water supply systems (hot or cold) as a result of impaired integrity, complicating the operation of a system and leading to high costs of ...

  7. Nuclear primary energy carriers. Short version

    Energy Technology Data Exchange (ETDEWEB)

    Jaeck, W

    1978-04-01

    Basing on our present knowledge the following energy sources for energy supply must be taken into consideration in the long term: regenerative energy sources, fission energy gained by breeder reactors, nuclear fusion. While regenerative energy sources were treated at full length in the study 'Energy Sources for Tomorrow' the present study specifies the other two energy options. The availability and the reliability of nuclear primary energy carrier supply is described in detail and the conversion systems available or still being developed are investigated with regard to their specific consumption of primary energy. Topical questions concerning the proliferation stability of the fuel cycles and techniques are subject to the INFCE program. With reference to the nuclear energy documentation activities of the Federal Government this study is supposed to supply further fundamental material on nuclear primary energy carriers, consumption and readiness for application. Thus it will contribute to the question: 'Is nuclear energy an option which guarantees energy supply in the long term for the Federal Republic of Germany'. (orig.) 891 UA 892 ARA.

  8. Nuclear primary energy carriers. Pt. 1

    International Nuclear Information System (INIS)

    1978-04-01

    Basing on our present knowledge the following energy sources for energy supply must be taken into consideration in the long term: regenerative energy sources, fission energy gained by breeder reactors, nuclear fusion. While regenerative energy sources were treated at full length in the study 'Energy Sources for tomorrow' the present study specifies the other two energy options. The availability and the reliability of nuclear primary energy carrier supply is described in detail and the conversion systems available or still being developed are investigated with regard to their specific consumption of primary energy. Topical questions concerning the proliferation stability of the fuel cycles and techniques are subject to the INFCE programme. With reference to the nuclear energy documentation activities of the Federal Govenment this study is supposed to supply further fundamental material on nuclear primary energy carriers, consumption and readiness for application. Thus it will contribute to the question: 'Is nuclear energy an option which guarantees energy supply in the long term for the Federal Republic of Germany'. (orig.) [de

  9. Reliability analyses of safety systems for WWER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Dusek, J.; Hojny, V.

    1985-01-01

    The UJV in Rez near Prague studied the reliability of the system of emergency core cooling and of the system for suppressing pressure in the sealed area of the nuclear power plant in the occurrence of a loss-of-coolant accident. The reliability of the systems was evaluated by failure tree analysis. Simulation and analytical calculation programs were developed and used for the reliability analysis. The results are briefly presented of the reliability analyses of the passive system for the immediate short-term flooding of the reactor core, of the active low-pressure system of emergency core cooling, the spray system, the bubble-vacuum system and the system of emergency supply of the steam generators. (E.S.)

  10. 2004 winter meeting: nuclear power and the continuity of supply in the enlarged European Union

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    This year's Winter Meeting organized by the Deutsches Atomforum e.V. focused on Nuclear Energy and Safety of Supply in the Enlarged European Union. Numerous participants from Germany and abroad discussed contributions from politics, industry, and science in Berlin, February 4 to 5, 2004. The general understanding was that a secure, economically viable and non-polluting supply of energy for Europe and the European Union was indispensable, and that the power industry faced major projects as a result of the foreseeable need to build new power plants, or replace decommissioned old plants, of 40,000 MW generating capacity in Germany and 200,000 MW in Europe. (orig.)

  11. Fuel supply security

    International Nuclear Information System (INIS)

    Wakabayashi, Hiroaki

    1987-01-01

    Stable fuel supply is a prerequisite for any nuclear power program including ISER-PIUS. It encompasses procurement of uranium ore, enriched uranium and fuel elements. Uranium is different from oil in that it can be stockpiled for more than a decade besides the fact that the core residence time is as long as six years, for example in the case of ISER-PIUS. These basic fuel characteristics are favoring nuclear fuel over others in terms of supply security. The central concern will be a gradual increase in prices of uranium and enrichment. Under the present glut situation with the worldwide prevalence of LWRs, fuel supply security seems ensured for the time being till the middle of 21st century. It is estimated that by the turn of the century, the free world will have roughly 450 GWe capacity of nuclear power. If 10 % is supplied for ISER-PIUS, more than 200 modules of 200 MWe ISER-PIUS may be deployed all over the world probably starting around 2000. As part of the fuel supply security consideration, heavy water reactor (HWR) may seem interesting to such a country as Indonesia where there is uranium resources but no enrichment capability. But it needs heavy water instead and the operation is not so easy as of LWR, because of the positive void coefficient as was seen at the Chernobyl-4. Safeguarding of the fuel is also difficult, because it lends itself to on line refueling. The current and future situation of the fuel supply security for LWR seem well founded and established long into the future. (Nogami, K.)

  12. Development of Nuclear Renewable Oil Shale Systems for Flexible Electricity and Reduced Fossil Fuel Emissions

    Energy Technology Data Exchange (ETDEWEB)

    Daniel Curtis; Charles Forsberg; Humberto Garcia

    2015-05-01

    We propose the development of Nuclear Renewable Oil Shale Systems (NROSS) in northern Europe, China, and the western United States to provide large supplies of flexible, dispatchable, very-low-carbon electricity and fossil fuel production with reduced CO2 emissions. NROSS are a class of large hybrid energy systems in which base-load nuclear reactors provide the primary energy used to produce shale oil from kerogen deposits and simultaneously provide flexible, dispatchable, very-low-carbon electricity to the grid. Kerogen is solid organic matter trapped in sedimentary shale, and large reserves of this resource, called oil shale, are found in northern Europe, China, and the western United States. NROSS couples electricity generation and transportation fuel production in a single operation, reduces lifecycle carbon emissions from the fuel produced, improves revenue for the nuclear plant, and enables a major shift toward a very-low-carbon electricity grid. NROSS will require a significant development effort in the United States, where kerogen resources have never been developed on a large scale. In Europe, however, nuclear plants have been used for process heat delivery (district heating), and kerogen use is familiar in certain countries. Europe, China, and the United States all have the opportunity to use large scale NROSS development to enable major growth in renewable generation and either substantially reduce or eliminate their dependence on foreign fossil fuel supplies, accelerating their transitions to cleaner, more efficient, and more reliable energy systems.

  13. Multiplicity in public health supply systems: a learning agenda.

    Science.gov (United States)

    Bornbusch, Alan; Bates, James

    2013-08-01

    Supply chain integration-merging products for health programs into a single supply chain-tends to be the dominant model in health sector reform. However, multiplicity in a supply system may be justified as a risk management strategy that can better ensure product availability, advance specific health program objectives, and increase efficiency.

  14. Supply Chain Collaboration Roles of Interorganizational Systems, Trust, and Collaborative Culture

    CERN Document Server

    Cao, Mei

    2013-01-01

    To survive and thrive in the competition, firms have strived to achieve greater supply chain collaboration to leverage the resources and knowledge of suppliers and customers.  Internet based technologies, particularly interorganizational systems, further extend the firms’ opportunities to strengthen their supply chain partnerships and share real-time information to optimize their operations.  Supply Chain Collaboration: Roles of Interorganizational Systems, Trust, and Collaborative Culture explores the nature and characteristics, antecedents, and consequences of supply chain collaboration from multiple theoretical perspectives.  Supply Chain Collaboration: Roles of Interorganizational Systems, Trust, and Collaborative Culture conceptualizes supply chain collaboration as seven interconnecting elements including information sharing, incentive alignment, goal congruence, decision synchronization, resource sharing, as well as communication and joint knowledge creation. These seven components define the occur...

  15. Feasibility of waste to Bio-diesel production via Nuclear-Biomass hybrid model. System dynamics analysis

    International Nuclear Information System (INIS)

    Nam, Hoseok; Kasada, Ryuta; Konishi, Satoshi

    2017-01-01

    Nuclear-Biomass hybrid system which takes waste biomass from municipal, agricultural area, and forest as feedstock produces Bio-diesel fuel from synthesis gas generated by endothermic pyrolytic gasification using high temperature nuclear heat. Over 900 degree Celsius of exterior thermal heat from nuclear reactors, Very High Temperature Reactor (VHTR) and some other heat sources, bring about waste biomass gasification to produce maximum amount of chemical energy from feedstock. Hydrogen from Biomass gasification or Bio-diesel as the product of Fischer-Tropsch reaction following it provide fuels for transport sector. Nuclear-Biomass hybrid system is a new alternatives to produce more energy generating synergy effects by efficiently utilizing the high temperature heat from nuclear reactor that might be considerably wasted by thermal cycle, and also energy loss from biomass combustion or biochemical processes. System Dynamics approach is taken to analyze low-carbon synthesis fuel, Bio-diesel, production with combination of carbon monoxide and hydrogen from biomass gasification. Feedstock cost considering collection, transportation, storage and facility for biomass gasification impacts the economic feasibility of this model. This paper provides the implication of practical nuclear-biomass hybrid system application with feedstock supply chain through evaluation of economic feasibility. (author)

  16. Improvements in or relating to cooling systems for nuclear fuel assemblies

    International Nuclear Information System (INIS)

    Ljubivy, A.G.; Batjukov, V.I.; Shkhian, T.G.; Fadeev, A.I.

    1980-01-01

    A cooling system is proposed which can be used to cool a set of nuclear fuel assemblies arranged in a reactor core or placed in a container for spent fuel assemblies. The object of the invention is to provide a system which would prevent leakage of coolant from the vessel in the event of a rupture of the coolant supply pipeline externally of the vessel. In the case of the reactor cooling system the level of the coolant is stopped from dropping below the level of the active portion of the fuel assemblies and thus prevents a breakdown of the reactor. (UK)

  17. A computer network system for mutual usage four databases of nuclear materials (Data-Free-Way)

    International Nuclear Information System (INIS)

    Fujita, M.; Kurihara, Y.; Shindou, M.; Yokoyama, N.; Tachi, Y.; Kano, S.; Iwata, S.

    1996-01-01

    Distributed database system named 'Data-Free-Way' for advanced nuclear materials has been developed by National Research Institute for Metals (NRIM), Japan Atomic Energy Research Institute (JAERI) and Power Reactor and Nuclear Fuel Development Corporation (PNC) under cooperation agreement between these three organizations. In the paper, features and functions of the system including input data are described together with method to share database among the three organizations as well as examples of the easy accessible search of material properties. Results of analysis of tensile and creep properties data on type 316 stainless steel collected by the different organizations and stored in the present system are also introduced as an example of attractive utilization of the system. Moreover, in order to consider the system in near future, some trails of WWW server of several sites in 'Data-Free-Way' to supply the information on nuclear materials to Internet are introduced. (author)

  18. Assessments of nuclear systems

    International Nuclear Information System (INIS)

    Ekholm, R.

    1978-01-01

    Assessments of competing energy systems are gaining increased importance as a means for an optimal choice of energy source for each specific major application considering the growing energy needs and the shortage of supply. However it is important to make sure that the assessments reflect scientific facts rather than private interests. If this is not achieved, scientists will lose credibility and one will lose the basis for political decisions. It is concluded that to accomplish the globally justified needs for thousands of nuclear reactors soon after the year 2000 and to save a maximum of lives with a minimum of environmental impact, emphasis must be put on low energy costs and on a good fuel and capital resource utilization. This goal can be best accomplished by expendient introduction of the fast breeders and of promising advanced reactors. The gas cooled breeder and the high temperature reactor have outstanding short and long terms merits on this respect, but are not enjoying the financial support that they deserve. (UK)

  19. Assessing reliability in energy supply systems

    International Nuclear Information System (INIS)

    McCarthy, Ryan W.; Ogden, Joan M.; Sperling, Daniel

    2007-01-01

    Reliability has always been a concern in the energy sector, but concerns are escalating as energy demand increases and the political stability of many energy supply regions becomes more questionable. But how does one define and measure reliability? We introduce a method to assess reliability in energy supply systems in terms of adequacy and security. It derives from reliability assessment frameworks developed for the electricity sector, which are extended to include qualitative considerations and to be applicable to new energy systems by incorporating decision-making processes based on expert opinion and multi-attribute utility theory. The method presented here is flexible and can be applied to any energy system. To illustrate its use, we apply the method to two hydrogen pathways: (1) centralized steam reforming of imported liquefied natural gas with pipeline distribution of hydrogen, and (2) on-site electrolysis of water using renewable electricity produced independently from the electricity grid

  20. Nuclear fuel market: Supplies remaining stable and secured in the mean range

    International Nuclear Information System (INIS)

    Braatz, U.; Dibbert, H.J.

    1988-01-01

    Installation of additional power plant will keep the demand for uranium at a level allowing a constant uranium production during the next few years to come, although production will have to be kept lower than demand, as inventories have to be cut in order to achieve a favourable price structure. Prospects on a mean-term basis show that natural uranium supplies are ensured, at favourable purchaser prices. Concluded contracts for new nuclear power plant indicate a better plant capacity utilization in uranium production to be attainable by the 1990s. Conversion capacity, however, is expected to remain as excessive as presently for quite a long period still, although reprocessing produces increasing amounts of recovered uranium to be converted. The capacity for uranium separative work is favourable for the customers. Existing and projected production facilities already today ensure safe supplies beyond the turn of the millenium, under conditions by far better in terms of long-term competing energy sources. (orig./HP) [de

  1. Symbiotic energy demand and supply system based on collaboration between rare-earth and thorium utilization

    International Nuclear Information System (INIS)

    Kamei, Takashi

    2011-01-01

    Progressive economic growth as well as prodigious consumption of energy are expected among Asian countries. Nuclear power has myriad advantages, among them particularly being its status as a low carbon technology and therefore nuclear power would make a significant contribution to curtailing CO 2 emissions. However, the prospects for nuclear power are hindered by some unresolved problems: perceived adverse safety, environmental, and health effects; potential security risks stemming from proliferation; and unresolved challenges in long-term management of nuclear wastes. Thorium utilization as a nuclear fuel will serve as a cornerstone of circumventing such problems, because thorium produces less radioactive waste (i.e. less plutonium) and thus safety, which is of paramount concern, will be enhanced. The deployment of electric vehicles (EVs) as an alternative to supplant gasoline engine cars in the transportation network, will significantly contribute in the reduction of global CO 2 emissions. Rare-earth materials such as neodymium and dysprosium will be essential as a new material for electric automobiles. Thorium is often obtained as a by-product of rare-earth metals, but it is still not utilized as a nuclear fuel currently due to the lack of its own fissionable isotopes and as such, it cannot be employed in the production of nuclear weapons. Recent trends of nuclear disarmament and accumulation of plutonium from uranium fuel cycle can propel the deployment of thorium. The implementation capacity of thorium nuclear power is estimated to be about 392 GWe at 2050. The utilization of thorium will both help to provide clean energy and to supply rare-earth materials for clean automobiles. In order for us to effect the commercial deployment of thorium resources, establishment of an international framework to supply resources from developing countries as well as to supply technology from developed countries is indeed imperative. Herein, the author propose 'The Bank

  2. Digital I and C for nuclear power plant

    International Nuclear Information System (INIS)

    Gemst, P. van

    1993-01-01

    A summary is given of the past experience (process I and C, digital controllers, Power Range Monitoring system) and future plans (integrated plant I and C, control room) of ABB Atom for programmable I and C at nuclear power plants. ABB Atom has designed and supplied an appreciable quantity of software based equipment for nuclear power plants. These have been supplied for both new plants as well as for backfitting. The well proven ABB Master system has been used for the supply of I and C equipment for these projects and will continue to be used in the future. (Z.S.) 1 fig

  3. Creation of reactor's reliable system of emergency energy supply

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  4. New Industrial Park Energy Supply (NIPES): a method of efficiently supplying energy to a community of industrial users

    International Nuclear Information System (INIS)

    1984-08-01

    The New Industrial Park Energy Supply (NIPES) concept allows the use of coal by small as well as large industrial users. The NIPES concept consists of a system of Energy Supply Stations groups of cogeneration plants) and steam transmission lines that supplies process heat and electricity to multiple existing and/or new users in an industrial park(s) setting. The Energy Supply Stations grow along with the industrial park(s) as new industries are attracted by a reliable reasonably priced energy source. The growth of the Energy Supply Stations over a period of years allows the introduction of new energy sources and technologies as they become established. This report describes the generic NIPES concept and the results of the evaluation of a specific NIPES system for the Lake Charles, Louisiana, area. A ten-year process steam load growth scenario is developed including both new and existing industrial users. During the initial years of the growth scenario, process steam is supplied to the industrial users by several coal-fired plants. Later, as the process steam load develops, a two-unit nuclear plant is integrated into the specific NIPES system. An evaluation is also performed for a NIPES system consisting of all coal-fired plants. The specific NIPES system is compared to: (1) individual user owned oil-fired facilities for existing industrial users; and (2) individual user owned coal-fired facilities for new industrial plants. A financial analysis is performed to determine the total economic advantages associated with the NIPES system: savings in a steam costs for industrial users, potential return on investment for investors

  5. New Industrial Park Energy Supply (NIPES): a method of efficiently supplying energy to a community of industrial users

    Energy Technology Data Exchange (ETDEWEB)

    1984-08-01

    The New Industrial Park Energy Supply (NIPES) concept allows the use of coal by small as well as large industrial users. The NIPES concept consists of a system of Energy Supply Stations groups of cogeneration plants) and steam transmission lines that supplies process heat and electricity to multiple existing and/or new users in an industrial park(s) setting. The Energy Supply Stations grow along with the industrial park(s) as new industries are attracted by a reliable reasonably priced energy source. The growth of the Energy Supply Stations over a period of years allows the introduction of new energy sources and technologies as they become established. This report describes the generic NIPES concept and the results of the evaluation of a specific NIPES system for the Lake Charles, Louisiana, area. A ten-year process steam load growth scenario is developed including both new and existing industrial users. During the initial years of the growth scenario, process steam is supplied to the industrial users by several coal-fired plants. Later, as the process steam load develops, a two-unit nuclear plant is integrated into the specific NIPES system. An evaluation is also performed for a NIPES system consisting of all coal-fired plants. The specific NIPES system is compared to: (1) individual user owned oil-fired facilities for existing industrial users; and (2) individual user owned coal-fired facilities for new industrial plants. A financial analysis is performed to determine the total economic advantages associated with the NIPES system: savings in a steam costs for industrial users, potential return on investment for investors.

  6. Nuclear based technologies for estimating microbial protein supply in ruminant livestock. Proceedings of the second research co-ordination meeting of a co-ordinated research project (phase 1)

    International Nuclear Information System (INIS)

    1999-06-01

    The Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture through its Co-ordinated Research Projects (CRPs), has been assisting national agricultural research systems in Member States to develop and apply nuclear and related techniques for improving livestock productivity. The programmes have focused on animal nutrition, animal reproduction and more recently on animal nutrition/reproduction interactions with emphasis on smallholder farming systems. The measurement of microbial protein supply to ruminant livestock has been an important area of research in ruminant nutrition. An estimate of microbial protein contribution to the intestinal protein flow is important for estimating the protein requirement of ruminant animals. Understanding the process of microbial protein synthesis has been difficult however, and due to the lack of simple and accurate methods for measuring microbial protein production in vivo, the methods used are based on complex microbial markers which require surgically prepared animals. As a result of a consultants meeting held in May 1995 to advise the Joint FAO/IAEA Division on the feasibility of using nuclear and related techniques for the development and validation of techniques for measuring microbial protein supply in ruminant animals, an FAO/IAEA Co-ordinated Research Project on Development, Standardization and Validation of Nuclear Based Technologies for Measuring Microbial Protein Supply in Ruminant Livestock for Improving Productivity was initiated in 1996, with a view to validating and adapting this technology for use in developing countries. To assist scientists participating in the CRP, a laboratory manual containing experimental protocols and methodologies for standardization and validation of the urine purine derivative technique and the development of models to suit local conditions, was published as IAEA-TECDOC-945. The present publication contains the final reports from participants in Phase 1 of the project

  7. Nuclear based technologies for estimating microbial protein supply in ruminant livestock. Proceedings of the second research co-ordination meeting of a co-ordinated research project (phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    The Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture through its Co-ordinated Research Projects (CRPs), has been assisting national agricultural research systems in Member States to develop and apply nuclear and related techniques for improving livestock productivity. The programmes have focused on animal nutrition, animal reproduction and more recently on animal nutrition/reproduction interactions with emphasis on smallholder farming systems. The measurement of microbial protein supply to ruminant livestock has been an important area of research in ruminant nutrition. An estimate of microbial protein contribution to the intestinal protein flow is important for estimating the protein requirement of ruminant animals. Understanding the process of microbial protein synthesis has been difficult however, and due to the lack of simple and accurate methods for measuring microbial protein production in vivo, the methods used are based on complex microbial markers which require surgically prepared animals. As a result of a consultants meeting held in May 1995 to advise the Joint FAO/IAEA Division on the feasibility of using nuclear and related techniques for the development and validation of techniques for measuring microbial protein supply in ruminant animals, an FAO/IAEA Co-ordinated Research Project on Development, Standardization and Validation of Nuclear Based Technologies for Measuring Microbial Protein Supply in Ruminant Livestock for Improving Productivity was initiated in 1996, with a view to validating and adapting this technology for use in developing countries. To assist scientists participating in the CRP, a laboratory manual containing experimental protocols and methodologies for standardization and validation of the urine purine derivative technique and the development of models to suit local conditions, was published as IAEA-TECDOC-945. The present publication contains the final reports from participants in Phase 1 of the project

  8. Business Intelligence tools as an element of information supply system

    Directory of Open Access Journals (Sweden)

    Agnieszka Szmelter

    2013-12-01

    Full Text Available This paper aims to present theBusiness Intelligence toolsas an element improvingflow of information withinthe management information systemand as atool to facilitate theachieving the objectives ofinformation supply system.In the firstpart of the paperthe author presents the issuesrelatedto the specific character of information as a kind of resource and functioning ofthe information supply systemin the enterprise. The secondpart of the articleincludethe characteristics ofBusiness Intelligence systems. The thirdpart deals withthe impact ofBusiness Intelligence toolsto the ongoingactivities ofinformation supply system.

  9. Power supply with nuclear reactor

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

    Each parameter of the processes of a nuclear reactor and components operatively associated therewith is monitored by a set of four like sensors. A trip system normally operates on a 'two out of four' configuration; i.e., to trip the reactor it is necessary that at least two sensors of a set sense an off-normal parameter. This assumes that all sensors are in normal operating condition. However, when a sensor is in test or is subject to maintenance or is defective or disabled, the 'two out of four' configuration would be reduced to a 'one out of three' configuration because the affected sensor is taken out of service. This would expose the system to the possibility that a single sensor failure, which may be spurious, will cause a trip of the reactor. To prevent this, it is necessary that the affected sensor be bypassed. If only one sensor is bypassed, the system operates on a 'two out of three' configuration. With two sensors bypassed, the sensing of an off-normal parameter by a third sensor trips the reactor

  10. Self-consistent nuclear energy systems

    International Nuclear Information System (INIS)

    Shimizu, A.; Fujiie, Y.

    1995-01-01

    A concept of self-consistent energy systems (SCNES) has been proposed as an ultimate goal of the nuclear energy system in the coming centuries. SCNES should realize a stable and unlimited energy supply without endangering the human race and the global environment. It is defined as a system that realizes at least the following four objectives simultaneously: (a) energy generation -attain high efficiency in the utilization of fission energy; (b) fuel production - secure inexhaustible energy source: breeding of fissile material with the breeding ratio greater than one and complete burning of transuranium through recycling; (c) burning of radionuclides - zero release of radionuclides from the system: complete burning of transuranium and elimination of radioactive fission products by neutron capture reactions through recycling; (d) system safety - achieve system safety both for the public and experts: eliminate criticality-related safety issues by using natural laws and simple logic. This paper describes the concept of SCNES and discusses the feasibility of the system. Both ''neutron balance'' and ''energbalance'' of the system are introduced as the necessary conditions to be satisfied at least by SCNES. Evaluations made so far indicate that both the neutron balance and the energy balance can be realized by fast reactors but not by thermal reactors. Concerning the system safety, two safety concepts: ''self controllability'' and ''self-terminability'' are introduced to eliminate the criticality-related safety issues in fast reactors. (author)

  11. Urban community perception towards intermittent water supply system.

    Science.gov (United States)

    Joshi, M W; Talkhande, A V; Andey, S P; Kelkar, P S

    2002-04-01

    While evaluating intermittent and continuous water supply systems, consumers opinion survey was undertaken for critical appraisal of both modes of operation. With the help of a pre-designed set of questions relating to various aspects of water supply and the opinion of consumers regarding degree of service, a house to house survey was conducted in the study area of Ghaziabad and Jaipur. The consumer opinion survey clearly indicated a satisfactory degree of service wherever adequate quantity of water was made available irrespective of the mode of water supply. Number of complaints regarding quality of water supplied, timings of supply, low pressures and breakdowns in supply were reported during intermittent water supply. Every family stored water for drinking and other uses. Most of the families discard drinking water once the fresh water supply is resumed next day. Discarded drinking water is usually used in kitchen for washing and gardening. Storage for other purposes depends on economic status and availability of other sources like open dug well in the house. While most of the respondents had no complaints on water tariff, all of them were in favour of continuous water supply.

  12. Emerging nuclear energy systems and nuclear weapon proliferation

    International Nuclear Information System (INIS)

    Gsponer, A.; Sahin, S.; Jasani, B.

    1983-01-01

    Generally when considering problems of proliferation of nuclear weapons, discussions are focused on horizontal proliferation. However, the emerging nuclear energy systems currently have an impact mainly on vertical proliferation. The paper indicates that technologies connected with emerging nuclear energy systems, such as fusion reactors and accelerators, enhance the knowledge of thermonuclear weapon physics and will enable production of military useful nuclear materials (including some rare elements). At present such technologies are enhancing the arsenal of the nuclear weapon states. But one should not forget the future implications for horizontal proliferation of nuclear weapons as some of the techniques will in the near future be within the technological and economic capabilities of non-nuclear weapon states. Some of these systems are not under any international control. (orig.) [de

  13. System Description of the Electrical Power Supply System for the ATLAS Integral Test Loop

    International Nuclear Information System (INIS)

    Moon, S. K.; Park, J. K.; Kim, Y. S.; Song, C. H.; Baek, W. P.

    2007-02-01

    An integral effect test loop for pressurized water reactors (PWRs), the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), is constructed by Thermal-Hydraulics Safety Research Team in Korea Atomic Energy Research Institute (KAERI). The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400. This report describes the design and technical specifications of the electrical power supply system which supplies the electrical powers to core heater rods, other heaters, various pumps and other systems. The electrical power supply system had acquired the final approval on the operation from the Korea Electrical Safety Corporation. During performance tests for the operation and control, the electrical power supply system showed completely acceptable operation and control performance

  14. Supply systems of forest chip production in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Kaerhae, K. (Metsaeteho Oy, Helsinki (Finland)), e-mail: kalle.karha@metsateho.fi

    2010-07-01

    The Metsaeteho study investigated how logging residue chips, stump wood chips, and chips from small-diameter thinning wood and large-sized (rotten) roundwood used by heating and power plants were produced in Finland in 2009. Almost all the major forest chip suppliers in Finland were involved in the study. The total volume of forest chips supplied in 2009 by these suppliers was 8,4 TWh. The study was implemented by conducting an e-mail questionnaire survey and telephone interviews. Research data was collected from March-May, 2010. The majority of the logging residue chips and chips from small-diameter thinning wood were produced using the roadside chipping supply system in Finland in 2009. The chipping at plant supply system was also significant in the production of logging residue chips. Nearly 70 % of all stump wood chips consumed were comminuted at the plant and 28 % at terminals. The role of the terminal chipping supply system was also significant in the production of chips from logging residues and small-diameter wood chips. When producing chips from large-sized (rotten) roundwood, similarly roughly 70 % of chips were comminuted at plants and 23 % at terminals. (orig.)

  15. An integrated approach to energy supply and demand: The role of nuclear energy in Southern Africa

    Energy Technology Data Exchange (ETDEWEB)

    Neethling, D C; Bredell, J H; Basson, J A [National Energy Council, Lynnwood Ridge (South Africa)

    1990-06-01

    The importance of an integrated approach to the development of an electricity strategy for Southern Africa is emphasized in view of the numerous options and initiatives that are available for supply and demand side management. Apart from present uncertainties concerning future electricity demand, other factors such as the availability of coal and uranium and the comparative costs of nuclear and coal-based electricity are regarded as the most important parameters which have as yet not been sufficiently quantified to decide on the timing and extent of nuclear energy in Southern Africa. (author)

  16. An integrated approach to energy supply and demand: The role of nuclear energy in Southern Africa

    International Nuclear Information System (INIS)

    Neethling, D.C.; Bredell, J.H.; Basson, J.A.

    1990-01-01

    The importance of an integrated approach to the development of an electricity strategy for Southern Africa is emphasized in view of the numerous options and initiatives that are available for supply and demand side management. Apart from present uncertainties concerning future electricity demand, other factors such as the availability of coal and uranium and the comparative costs of nuclear and coal-based electricity are regarded as the most important parameters which have as yet not been sufficiently quantified to decide on the timing and extent of nuclear energy in Southern Africa. (author)

  17. Verification of Safety Margins of Battery Banks Capacity of Class 1E DC System in a Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lukman, Abdulrauf; Zhu, Oon-Pyo

    2015-01-01

    According to Ref 'Station blackout (SBO) is generally a plant condition with complete loss of all alternating current (AC) power from off-site sources, from the main generator and from standby AC power sources important to safety to the essential and nonessential switchgear buses. Direct current (DC) power supplies and uninterruptible AC power supplies may be available as long as batteries can supply the loads, alternate AC power supplies are available'. The above IAEA document indicated the importance of batteries during SBO. Prior to the Fukushima accident, most batteries might be designed with coping capability of four hours. However, the accident showed the need for the coping capability to be increased to at least eight hours. The purpose of this research is to verify the safety capacity margin of the nuclear qualified battery banks of class 1E DC system and test the response to SBO using the load profile of a Korean design nuclear power plant (NPP). The capacity margins of class 1E batteries of DC power system batteries in a nuclear power plant were determined using the load profile of the plant. It was observed that if appropriate manufacturer Kt data are not available, the accuracy of the battery capacity might not be accurately calculated. The result obtained shows that the batteries have the coping capability of two hours for channel A and B, and eight hours for channel C and D. Also capacity margin as show in figure show a reasonable margin for each batteries of the DC system

  18. Flexibility of Supply Chain in Industrialised Building System (IBS

    Directory of Open Access Journals (Sweden)

    Kassim U.

    2014-01-01

    Full Text Available It is irrefutable that the construction industry is in need of a highly technological construction method or system for the simple aim of giving it a push it deserves. In Malaysia this technologically enhanced method is known as the Indutrialised Building System (IBS. Concerted efforts have been made for the past decade by various responsible parties especially by the government. Therefore, the IBS ‘Road Map’ 2003–2010 was introduced and now continues with the IBS ‘road map’ 2011-2015. However, its performance is still at its infancy, which target is only at an initial stage. This study seeks to identify and analyse the factor of the IBS’ system’s supply chain flexibility as a factor on the success of the system itself. It has been a suspicion that there exists a condition and situation where the supply chain is too rigid and is not flexible in fulfilling the needs and demands of the IBS development in Malaysia. This inflexible situation has brought about a broad range of problems and has stood in the way of the development of the industrialised building system, despite it being introduced since 1964, or 49 years ago. Flexibility in the IBS supply chain is very important and is associated with other industries like transportation, manufacturing industry, and others. Up until now, we have yet to discover any special studies related to the flexibility in the IBS supply chain in this country. Responding to this challenge, this research is hoped to be able to provide sufficient feedback to the solution to the IBS supply chain flexibility issue. The researcher is confident that the poor system flow of supply chain has impeded the advancement of the Industrialised Building System that has long been open to debate.

  19. A supply chain approach to biochar systems [Chapter 2

    Science.gov (United States)

    Nathaniel M. Anderson; Richard D. Bergman; Deborah S. Page-Dumroese

    2017-01-01

    Biochar systems are designed to meet four related primary objectives: improve soils, manage waste, generate renewable energy, and mitigate climate change. Supply chain models provide a holistic framework for examining biochar systems with an emphasis on product life cycle and end use. Drawing on concepts in supply chain management and engineering, this chapter presents...

  20. World supply of nuclear energy

    International Nuclear Information System (INIS)

    Pecqueur, Michel.

    1981-01-01

    At the end of 1980 nuclear energy accounted for 9% of the world production of electricity stemming from 262 power stations, utilising mainly the process of water reactors and representing an installed capacity of 142 GWe. This production, apparently limited, already represents the equivalent of 150 million TOE. The 600 nuclear power stations in service, under construction or ordered represent a total of 450 GWe. In 1985, their production ought to cover 15% of the world requirements of electricity, which corresponds to a doubling of the share of nuclear energy within 6 years. During these recent years, the development of nuclear energy has undergone a significant slowing down and the number of orders for new nuclear power stations has dropped considerably in particular in the United States. Considering the time required and the available industrial capacity, the accumulated capacity which could be installed worlwide by 1990 could attain 530 GWe, equivalent to 650 MTOE covering 24% of the world production of electricity and 7% of the world consumption of primary energy. A determined effort for the end of this century could end up by the installation of 1200 GWe of capacity, generating 1.5 GTOE. The share of nuclear energy would then represent 35% of the production of electricity [fr

  1. Nuclear power in Canada

    International Nuclear Information System (INIS)

    1980-01-01

    The Canadian Nuclear Association believes that the CANDU nuclear power generation system can play a major role in achieving energy self-sufficiency in Canada. The benefits of nuclear power, factors affecting projections of electric power demand, risks and benefits relative to other conventional and non-conventional energy sources, power economics, and uranium supply are discussed from a Canadian perspective. (LL)

  2. China's approach to nuclear safety — From the perspective of policy and institutional system

    International Nuclear Information System (INIS)

    Mu, Ruimin; Zuo, Jian; Yuan, Xueliang

    2015-01-01

    Nuclear energy plays an important role in the energy sector in the world. It has achieved a rapid development during the past six decades and contributes to over 11% of the world's electricity supply. On the other side, nuclear accidents have triggered substantial debates with a growing public concern on nuclear facilities. Followed by the Fukushima nuclear accident, some developed countries decided to shut down the existing nuclear power plants or to abandon plans to build new ones. Given this background, accelerating the development of nuclear power on the basis of safety in China will make it a bellwether for other countries. China assigns the top priority to the nuclear safety in nuclear energy development and has maintained a good record in this field. The policy and institutional system provide the necessary guarantee for the nuclear energy development and safety management. Furthermore, China's approach to nuclear safety provides a benchmark for the safe development and utilization of nuclear power. This research draws an overall picture of the nuclear energy development and nuclear safety in China from the policy and institutional perspective. - Highlights: • China's Approach to Nuclear Safety. • Policy and Institutional System for Nuclear Energy Development. • A Benchmark for the Peaceful and Safe Utilization of Nuclear Power. • Further Efforts for Specific Laws and Administrative System

  3. Numerical study on oil supply system of a rotary compressor

    International Nuclear Information System (INIS)

    Wu, Jianhua; Wang, Gang

    2013-01-01

    The oil supply system is a crucial reliability issue for rotary compressors. This paper provides a general method for analyzing the oil supply system of a rotary compressor by using computational fluid dynamics (CFD). The process includes establishing the physical model, dividing computational grid, setting boundary conditions, calculating leakage rates through the roller end clearances, translating the dynamic issue into the static issue and so on. Validation of the rationality of the oil supply system model has been made by the measurement of the main bearing oil flow rates. The effects of operating conditions of the compressor, the oil level height of the oil sump and the main design parameters of the oil supply system on the oil supply characteristics are analyzed by numerical simulation. It is found that the main bearing oil flow rate varies circularly along with the rotation of the shaft. The shape and inclination angle of the spiral groove also influence the main bearing oil flow rate. The oil leakage rates through the roller end clearances depend largely on the operating conditions. In addition, the oil level height of the oil sump has a huge effect on the total oil flow rate. -- Highlights: • A CFD method for analyzing the oil supply system of rotary compressor is presented. • Leakage through the roller end clearances depends on the operating condition. • Groove shape and inclination angle are the main design parameters of spiral grooves. • A parabolic interface of oil and gas can be formed in the gallery of the shaft. • Single-flow model and steady solver can be applied to the oil supply system

  4. Risk of the Maritime Supply Chain System Based on Interpretative Structural Model

    Directory of Open Access Journals (Sweden)

    Jiang He

    2017-11-01

    Full Text Available Marine transportation is the most important transport mode of in the international trade, but the maritime supply chain is facing with many risks. At present, most of the researches on the risk of the maritime supply chain focus on the risk identification and risk management, and barely carry on the quantitative analysis of the logical structure of each influencing factor. This paper uses the interpretative structure model to analysis the maritime supply chain risk system. On the basis of comprehensive literature analysis and expert opinion, this paper puts forward 16 factors of maritime supply chain risk system. Using the interpretative structure model to construct maritime supply chain risk system, and then optimize the model. The model analyzes the structure of the maritime supply chain risk system and its forming process, and provides a scientific basis for the controlling the maritime supply chain risk, and puts forward some corresponding suggestions for the prevention and control the maritime supply chain risk.

  5. Nuclear trade: an approach on the Argentine situation

    International Nuclear Information System (INIS)

    Antoniotti, Americo A.; Paez, Mariano R.

    2005-01-01

    The Argentine nuclear trade regime. Nuclear Materials. Definitions. Stages. From early times of nuclear development an actual and strict monopoly governed the transfers of nuclear materials. That meant: the Federal State took the control as user, producer, purchaser or seller. This policy was inspired and clearly echoed a similar one developed by countries with important development in the nuclear field. Types of contracts on nuclear commerce. Relation with costs implied with the nuclear industry. Uranium mining. System of supplies. Development of factories of nuclear supplies. Incentives. Nuclear Power. Radioisotopes. Human Resources. Ways of intervention of the State on nuclear Commerce. The right of veto. The ownership of shares in private or public corporations. Export- import controls. Security and Safety standards. National Act of Nuclear Activity. Veto of the Executive Power to the monopoly of the exclusive national supply of uranium. Comparative policies on other fields or products in Argentina. A proposal of lege ferenda. State's right of transformation applicable to purchases and sales of nuclear materials. Exchange and loans. Cosignature of contracts, etc. (author)

  6. ISABELLE magnet power supply system performance analysis

    International Nuclear Information System (INIS)

    Edwards, R.J.

    1981-01-01

    The power supply system that will energize the superconducting magnets in the ISABELLE 400 x 400 GeV accelerator must supply various voltages and currents. The voltages for the correction winding range from ten to one hundred twenty-five volts unipolar and bipolar with current rating of 50 to 300 amperes. The main field winding requires voltages from 90V (at flattop) to 600V during maximum ramp rate or acceleration cycle. The power supplies are programmable over their full range of output current with a reproducibility error varying from +- 10 ppM to +- 400 ppM of full scale. Included within the reproducibility error are the long and short term stability requirements of the power supplies. The purpose of this paper is to define some of the design goals and outline the approach taken in reaching these goals

  7. Re-examining uranium supply and demand: New insights

    International Nuclear Information System (INIS)

    Kahouli, Sondes

    2011-01-01

    In this paper, we derive a simultaneous system of equations which aims at analysing the uranium supply and demand. In addition to reviewing and updating previous studies dealing with the uranium market analysis, in particular , the contribution of the paper lies in putting attention to some questions which are still either controversial or unanswered. They are especially related to the controversial hypothesis of the interdependence between uranium market and other commodities markets, both, with respect to the demand side, i.e. oil and coal markets, and the supply side, i.e. gold market. The paper also casts lights on electricity and uranium price effects on uranium demand as well as on the simultaneous interdependencies that may exist between nuclear consumption and nuclear installed capacity. The model is estimated for three different time periods which takes into account the major events that have influenced the nuclear-uranium development, that is, that have constrained the growth rate of nuclear generating capacity, i.e. oil crisis and nuclear accidents. This permits to show if uranium market reaction is independent or it is correlated with specific events associated with each time periods. The model was estimated by using the 3SLS method that correct for the presence of contemporaneously error terms correlation and for the existence of simultaneity bias in the model. Main results give evidence of significant correlation between uranium price and competing fossil fuel prices. They also point-out that uranium price is significantly correlated with the supply forces where supply is significantly dependent on gold prices. Moreover, results show that the electricity prices have a significant effect on the uranium demand only in the post-1990 period, probably following the worldwide electricity prices increasing trend. Further, our estimations show that uranium demand is significantly correlated with uranium price only in the period of nuclear major expansion. As

  8. Re-examining uranium supply and demand: New insights

    Energy Technology Data Exchange (ETDEWEB)

    Kahouli, Sondes, E-mail: sondes.kahouli@univ-nantes.f [Universite de Nantes, Laboratoire d' Economie et de Management de Nantes Atlantique (LEMNA), Institut d' Economie et de Management de Nantes-I.A.E., Chemin de la Censive du Tertre-B.P. 52231, 44322 Nantes Cedex 3 (France)

    2011-01-15

    In this paper, we derive a simultaneous system of equations which aims at analysing the uranium supply and demand. In addition to reviewing and updating previous studies dealing with the uranium market analysis, in particular , the contribution of the paper lies in putting attention to some questions which are still either controversial or unanswered. They are especially related to the controversial hypothesis of the interdependence between uranium market and other commodities markets, both, with respect to the demand side, i.e. oil and coal markets, and the supply side, i.e. gold market. The paper also casts lights on electricity and uranium price effects on uranium demand as well as on the simultaneous interdependencies that may exist between nuclear consumption and nuclear installed capacity. The model is estimated for three different time periods which takes into account the major events that have influenced the nuclear-uranium development, that is, that have constrained the growth rate of nuclear generating capacity, i.e. oil crisis and nuclear accidents. This permits to show if uranium market reaction is independent or it is correlated with specific events associated with each time periods. The model was estimated by using the 3SLS method that correct for the presence of contemporaneously error terms correlation and for the existence of simultaneity bias in the model. Main results give evidence of significant correlation between uranium price and competing fossil fuel prices. They also point-out that uranium price is significantly correlated with the supply forces where supply is significantly dependent on gold prices. Moreover, results show that the electricity prices have a significant effect on the uranium demand only in the post-1990 period, probably following the worldwide electricity prices increasing trend. Further, our estimations show that uranium demand is significantly correlated with uranium price only in the period of nuclear major expansion. As

  9. Re-examining uranium supply and demand. New insights

    Energy Technology Data Exchange (ETDEWEB)

    Kahouli, Sondes [Universite de Nantes, Laboratoire d' Economie et de Management de Nantes Atlantique (LEMNA), Institut d' Economie et de Management de Nantes - I.A.E., Chemin de la Censive du Tertre - B.P. 52231, 44322 Nantes Cedex 3 (France)

    2011-01-15

    In this paper, we derive a simultaneous system of equations which aims at analysing the uranium supply and demand. In addition to reviewing and updating previous studies dealing with the uranium market analysis, in particular, the contribution of the paper lies in putting attention to some questions which are still either controversial or unanswered. They are especially related to the controversial hypothesis of the interdependence between uranium market and other commodities markets, both, with respect to the demand side, i.e. oil and coal markets, and the supply side, i.e. gold market. The paper also casts lights on electricity and uranium price effects on uranium demand as well as on the simultaneous interdependencies that may exist between nuclear consumption and nuclear installed capacity. The model is estimated for three different time periods which takes into account the major events that have influenced the nuclear-uranium development, that is, that have constrained the growth rate of nuclear generating capacity, i.e. oil crisis and nuclear accidents. This permits to show if uranium market reaction is independent or it is correlated with specific events associated with each time periods. The model was estimated by using the 3SLS method that correct for the presence of contemporaneously error terms correlation and for the existence of simultaneity bias in the model. Main results give evidence of significant correlation between uranium price and competing fossil fuel prices. They also point-out that uranium price is significantly correlated with the supply forces where supply is significantly dependent on gold prices. Moreover, results show that the electricity prices have a significant effect on the uranium demand only in the post-1990 period, probably following the worldwide electricity prices increasing trend. Further, our estimations show that uranium demand is significantly correlated with uranium price only in the period of nuclear major expansion. As

  10. Transient evaluation using EMTP at one phase opening with the offsite power transformer for the emergency power supply systems of nuclear power plants. This report is a follow-up of the report published two years ago. Verification related to the open-phase detection method of the transformer by United States Electric Power Research Institute (EPRI)

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2015-01-01

    The emergency power supply systems of nuclear power plants, as the objects of this research, are critical in supplying stable electric power to such systems as the emergency core cooling system (ECCS), and in maintaining safety of the nuclear power reactor; this was apparent in the accident at the Fukushima Daiichi Nuclear Power Station. The USNRC issued regulatory documents (BL 2012-01, IN 2012-03), and has commenced evaluations on newly emerged vulnerability in the design of power supply systems which cannot be detected with degraded-voltage protection relays, with certain kinds of configuration of coils and iron core structures, such as when the offsite power supply side is a wye-connection and the load side is a delta-connection etc., when the detection of one-phase open fault with the circuit of a transformer which is without a ground fault connected to the offsite power supply system. The report in the INSS JOURNAL 2013 used simulation by the electro-magnetic transients program (EMTP) and clearly described the response at the time of the power supply side one-phase open without ground fault for various configuration of coils and various iron core structures of the three-phase transformer, and identified the important issues in the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the one-phase open fault occurred without ground fault. The report in the INSS JOURNAL 2014 summarizes the previous results, and then presents the principles by which normal voltages are maintained in both the primary and the secondary sides when the one-phase open failure without ground fault occurs on the primary side of the transformer, and the results of the simulations of operations of the protection relays of the emergency power supply systems and the safety related components of representative a domestic PWR plant with EMTP. In a continuation of the previous reports, this report explains the method to detect

  11. Hybrid energy system evaluation in water supply system energy production: neural network approach

    Energy Technology Data Exchange (ETDEWEB)

    Goncalves, Fabio V.; Ramos, Helena M. [Civil Engineering Department, Instituto Superior Tecnico, Technical University of Lisbon, Av. Rovisco Pais, 1049-001, Lisbon (Portugal); Reis, Luisa Fernanda R. [Universidade de Sao Paulo, EESC/USP, Departamento de Hidraulica e Saneamento., Avenida do Trabalhador Saocarlense, 400, Sao Carlos-SP (Brazil)

    2010-07-01

    Water supply systems are large consumers of energy and the use of hybrid systems for green energy production is this new proposal. This work presents a computational model based on neural networks to determine the best configuration of a hybrid system to generate energy in water supply systems. In this study the energy sources to make this hybrid system can be the national power grid, micro-hydro and wind turbines. The artificial neural network is composed of six layers, trained to use data generated by a model of hybrid configuration and an economic simulator - CES. The reason for the development of an advanced model of forecasting based on neural networks is to allow rapid simulation and proper interaction with hydraulic and power model simulator - HPS. The results show that this computational model is useful as advanced decision support system in the design of configurations of hybrid power systems applied to water supply systems, improving the solutions in the development of its global energy efficiency.

  12. An integrated nuclear reactor unit for a floating low capacity nuclear power plant designed for power supply in remote areas with difficult access

    International Nuclear Information System (INIS)

    Achkasov, A.N.; Grechko, G.I.; Gladkov, O.G.; Pavlov, V.L.; Pepa, V.N.; Shishkin, V.A.

    1997-01-01

    The paper describes the conceptual design of an integrated advanced safety nuclear reactor unit for a low capacity floating, NPP designed for power supply in areas which are remote with difficult access. The paper describes the major structural and lay-out components of the steam generator and reactor units with main technical characteristics. (author)

  13. The future supply of and demand for candidate materials for the fabrication of nuclear fuel waste disposal containers

    International Nuclear Information System (INIS)

    Grover, L.K.

    1990-01-01

    This report summarizes the findings of a literature survey carried out to assess the future world supply of and demand for titanium, copper and lead. These metals are candidate materials for the fabrication of containers for the immobilization and disposal of Canada's nuclear used-fuel waste for a reference Used-fuel Disposal Centre. Such a facility may begin operation by approximately 2020, and continue for about 40 years. The survey shows that the world has abundant supplies of titanium minerals (mostly in the form of ilmenite), which are expected to last up to at least 2110. However, for copper and lead the balance between supply and demand may warrant increased monitoring beyond the year 2000. A number of factors that can influence future supply and demand are discussed in the report

  14. Accumulation of 137Cs in commercial fish of the Belyarsk nuclear power station cooling supply

    International Nuclear Information System (INIS)

    Trapeznikova, V.N.; Kulikov, N.V.; Trapeznikov, A.V.

    1984-01-01

    Results are presented of a comparative study of the accumulation of 137 Cs in basic species of commercial fish of the Beloyarsk reservoir which is used as the cooling supply for the Beloyarsk nuclear power station. Possible reasons for interspecies differences in accumulation of the radionuclide are indicated, and the increased accumulation of 137 Cs by free-living fish in the zone of heated water effluent from the station and the reduced accumulation of the emitter in carp, which are cultivated on artificial food in cages, are noted. Levels of the content of the radionuclide are compared in roach and farm carp from the cooling supplies of the Beloyarsk station and the Reftinsk power plant in the Urals

  15. power system reliability in supplying nuclear reactors

    International Nuclear Information System (INIS)

    Gad, M.M.M.

    2007-01-01

    this thesis presents a simple technique for deducing minimal cut set (MCS) from the defined minimal path set (MPS) of generic distribution system and this technique have been used to evaluate the basic reliability indices of Egypt's second research reactor (ETRR-2) electrical distribution network. the alternative system configurations are then studied to evaluate their impact on service reliability. the proposed MCS approach considers both sustained and temporary outage. the temporary outage constitutes an important parameter in characterizing the system reliability indices for critical load point in distribution system. it is also consider the power quality impact on the reliability indices

  16. [The development of hospital medical supplies information management system].

    Science.gov (United States)

    Cao, Shaoping; Gu, Hongqing; Zhang, Peng; Wang, Qiang

    2010-05-01

    The information management of medical materials by using high-tech computer, in order to improve the efficiency of the consumption of medical supplies, hospital supplies and develop a new technology way to manage the hospital and material support. Using C # NET, JAVA techniques to develop procedures for the establishment of hospital material management information system, set the various management modules, production of various statistical reports, standard operating procedures. The system is convenient, functional and strong, fluent statistical functions. It can always fully grasp and understand the whole hospital supplies run dynamic information, as a modern and effective tool for hospital materials management.

  17. Roles and prospect of nuclear power in China's energy supply strategy

    International Nuclear Information System (INIS)

    Wang Dazhong; Lu Yingyun

    2002-01-01

    China's annual energy demand is expected to amount to 3360 million tons of oil equivalent (toe) in 2050, the target year for the nation's economic development to reach the level of medium-developed countries in the middle of this century. The future energy supply, doubtless to go through a substantial increase and necessary mix shift with potential significant environmental impacts, will continue to rely on the domestic sources with coal-dominance but diversified mixes, in which nuclear power makes up a reasonable share. The large-scale development of nuclear energy is essential and promising, with the total installed capacity expectedly over 200-300 GW around 2050, and will be an effective response measure to mitigate the energy-derived environmental pollution and guarantee the national energy security. China is a developing country with the largest population in the world. The energy production had achieved remarkable progress over the last half century, particularly since the initiatives of reform and opening to the outside world in the late 1970s, and energy demand to fuel the continued socio-economic growth has been largely met. The current energy consumption of China is 896 Mtoe (China Stat. Abs. (2001) 130), accounting for about 11% of the world's total, the second largest energy consumer in the globe. However, the energy supply will face even tougher challenges in terms of demand increase, mix shift and potential environmental impacts to be posed by a sustained fast-growing economy in light of China's blueprint for future development. With the switch-over from the centrally planned economy to the socialist market economy and the gradual integration of China's energy trade into the international markets, the imported crude oil in 2000 amounted to 70.265 Mt (Int. Petrol. Econ. 9 (2000) 5), about 3.5% of the global petroleum trade, the long-term energy security for China would have great regional and global implications. It is, therefore, of great significance

  18. Technical evaluation report on the monitoring of electric power to the reactor protection system for the Nine Mile Point Nuclear Station, Unit 1 (Docket No. 50-220)

    International Nuclear Information System (INIS)

    Selan, J.C.

    1984-01-01

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Nine Mile Point Nuclear Station, Unit 1. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  19. Emergency water supply facility for nuclear reactor

    International Nuclear Information System (INIS)

    Karasawa, Toru

    1998-01-01

    Water is stored previously in an equipment storage pit disposed on an operator floor of a reactor building instead of a condensate storage vessel. Upon occurrence of an emergency, water is supplied from the equipment storage pit by way of a sucking pipeline to a pump of a high pressure reactor core water injection circuit and a pump of a reactor-isolation cooling circuit to supply water to a reactor. The equipment storage pit is arranged in a building so that the depth thereof is determined to keep the required amount of water by storing water at a level lower than the lower end of a pool gate during normal operation. Water is also supplied from the equipment storage pit by way of a supply pipeline to a spent fuel storage pool on the operation floor of the reactor building. Namely, water is supplied to the spent fuel storage pool by a pump of a fuel pool cooling and cleaning circuit. This can eliminate a suppression pool cleaning circuit. (I.N.)

  20. Route planning module as a part of Supply Chain Management system

    Directory of Open Access Journals (Sweden)

    Michal Košíček

    2012-01-01

    Full Text Available Today, the demand for creating a systematic approach for managing sales, ordering, and logistics has increased. Supply Chain Management (SCM is one of the responses to problems that have arose with the need for managing complex supply chains. Nowadays, most of the activities of Supply Chain Management is realized or supported with computing technologies. Route planning is an important part of Supply Chain Management related to both procurement and distribution. Route planning systems specify the sequences in which the selected transport vehicles should supply the demand points by requested quantities of goods at the right time. The paper is focused on the analysis of a route planning system which could be used as a part of Supply Chain Management information system or as a standalone application. It describes basic techniques and frameworks of transportation problems as well as important functional requirements, considering recent trends in the field of distribution planning. As a result, functional specification of basic features and other components of system are provided. The paper is a result of a joint initiative of the authors and a vendor of business information systems.

  1. Feedwater system in a nuclear power plant

    International Nuclear Information System (INIS)

    Shimizu, Tadayuki.

    1975-01-01

    Object: To improve the control property of a steam turbine for a feedwater pump and plant operation characteristics where water is supplied at a low rate. Structure: In a nuclear power plant where feedwater pumps of the reactor are driven by a steam turbine, the main feedwater duct on the discharge side of the feedwater pumps is provided with a cut-off valve and is connected parallel with a bypass duct having a pressure compensated flow control valve. With this arrangement, at the time when the rate of feedwater is high the cut-off valve is open so that water supplied from the feedwater pumps driven by the steam turbine is supplied through the main feedwater duct to the reactor while in case when the rate of feedwater is low the flow control valve is opened to let the water be supplied through the bypass duct. (Kamimura, M.)

  2. Fault Analysis of ITER Coil Power Supply System

    International Nuclear Information System (INIS)

    Song, In Ho; Jun, Tao; Benfatto, Ivone

    2009-01-01

    The ITER magnet coils are all designed using superconductors with high current carrying capability. The Toroidal Field (TF) coils operate in a steadystate mode with a current of 68 kA and discharge the stored energy in case of quench with using 9 interleaved Fast Discharge Units (FDUs). The Central Solenoid (CS) coils and Poloidal Field (PF) coils operate in a pulse mode with currents of up to 45 kA and require fast variation of currents inducing more than 10 kV during normal operation on the coil terminals using Switching Network (SN) systems (CSs, PF1 and 6) and Booster and VS converters (PF2 to 5), which are series connected to Main converters. SN and FDU systems comprise high current DC circuit breakers and resistors for generating high voltage (SN) and to dissipate magnetic energy (FDUs). High transient voltages can arise due to the switching operation of SN and FD and the characteristics of resistors and stray components of DC distribution systems. Also, faults in power supply control such as shorts or grounding faults can produce higher voltages between terminals and between terminal and ground. Therefore, the design of the coil insulation, coil terminal regions, feeders, feed throughs, pipe breaks and instrumentation must take account of these high voltages during normal and abnormal conditions. Voltage insulation level can be defined and it is necessary to test the coils at higher voltages, to be sure of reliable performance during the lifetime of operation. This paper describes the fault analysis of the TF, CS and PF coil power supply systems, taking account of the stray parameter of the power supply and switching systems and inductively coupled superconducting coil models. Resistor grounding systems are included in the simulation model and all fault conditions such as converter hardware and software faults, switching system hardware and software faults, DC short circuits and single grounding faults are simulated. The occurrence of two successive faults

  3. United States enrichment supply - policy and direction

    International Nuclear Information System (INIS)

    Voigt, W.R. Jr.; Peske, S.E.

    1982-01-01

    Recognizing our position as the leader in commercial enrichment services, DOE has established a flexible approach to meeting changing market realities and customer needs. The major elements of this strategy are aggressive deployment of advanced technologies, more flexible contract terms and conditions, and near-term production optimization, all of which are based on a supply strategy which carefully balances near-term requirements with long-range responsibilities. The current surplus of separative work in the world market may afford some near-term opportunities for economy. However, a secure nuclear energy system must be based on assured long-term supply availability at reasonable prices. By utilizing the flexibilities of our large production base and maintaining our demonstrated technological advantages, DOE is confident that the US will continue to be a vital and major competitor in the international nuclear fuel market. 4 figures

  4. Reliability of the electric power supply in the safety apparatus of nuclear power plants: a comparative analysis

    International Nuclear Information System (INIS)

    Cruz, L.A.

    1992-01-01

    This paper discusses the risk of total loss of electric power supply to the Class 1E system. Two alternatives are focused: a system with two off-site and two onsite power supplies emergency power supply, as recommended by the American Regulations, and a system with only one off-site and four on-site power supplies, applicable when two off-site are not available. To allow the fact that the equipment can be repaired, the method proper involves use of the Markov model, with which one can find, for each configuration of the system, the change over time of the probability of a simultaneous failure of all power sources. The sensitivity of each parameter is studied in each case and, on the basis of the results of the study, the author conclude that the system with two off-site power supplies is preferable in all alternatives analysed, although the system with one off-site power supply can be adopted with high reliability diesel-generators. (author)

  5. On adaptive modified projective synchronization of a supply chain management system

    Science.gov (United States)

    Tirandaz, Hamed

    2017-12-01

    In this paper, the synchronization problem of a chaotic supply chain management system is studied. A novel adaptive modified projective synchronization method is introduced to control the behaviour of the leader supply chain system by a follower chaotic system and to adjust the leader system parameters until the measurable errors of the system parameters converge to zero. The stability evaluation and convergence analysis are carried out by the Lyapanov stability theorem. The proposed synchronization and antisynchronization techniques are studied for identical supply chain chaotic systems. Finally, some numerical simulations are presented to verify the effectiveness of the theoretical discussions.

  6. Total energy supply for remote human habitations (Or 'Nuclear North of 60')

    International Nuclear Information System (INIS)

    Harris, J.

    2012-01-01

    This presentation will examine the direct application of nuclear energy solutions in the north, and remote areas of Canada. Further it will challenge the existing energy network based on the shipment of fossil fuels to remote areas, and examine the use of small, modular, and/or deployable nuclear plants in these communities. The use of these small reactors and some newly emerging technologies will likely provide a near total energy supply for these communities. In particular low grade heat processes, district heating, the 'local' production of motive fuels, and local food production will be examined. Additionally the economic and social impact of moving the value added side of many of these processes to the local communities will also be briefly discussed.

  7. Control system of power supply for resistance welding machine

    Directory of Open Access Journals (Sweden)

    Світлана Костянтинівна Поднебенна

    2017-06-01

    Full Text Available This article describes the existing methods of heat energy stabilizing, which are realized in thyristor power supplies for resistance welding machines. The advantages and features of thyristor power supplies have been described. A control system of power supply for resistance welding machine with stabilization of heat energy in a welding spot has been developed. Measurements are performed in primary winding of a welding transformer. Weld spot heating energy is calculated as the difference between the energy, consumed from the mains, and the energy losses in the primary and secondary circuits of the welding transformer as well as the energy losses in the transformer core. Algorithms of digital signal processing of the developed control system are described in the article. All measurements and calculations are preformed automatically in real-time. Input signals to the control system are: transformer primary voltage and current, temperature of the welding circuit. The designed control system ensures control of the welding heat energy and is not influenced by the supply voltage and impedance changes caused by insertion of the ferromagnetic mass in the welding circuit, the temperature change during the welding process. The developed control system for resistance welding machine makes it possible to improve the quality of welded joints, increase the efficiency of the resistance welding machine

  8. On things nuclear: the Canadian debate

    International Nuclear Information System (INIS)

    Mueller, P.G.

    1977-01-01

    An unbiased overview is given of the nuclear industry in Canada, with emphasis on its history, fundamentals of nuclear power plants and the CANDU reactor system, the need and ideal mix of future energy sources, economics of nuclear power, uranium supplies, radioactive releases, thermal pollution, physical security, and safety of nuclear power plants, and export of CANDU technology vs. nuclear proliferation. (E.C.B.)

  9. The 3He Supply Problem

    Energy Technology Data Exchange (ETDEWEB)

    Kouzes, Richard T.

    2009-05-01

    One of the main uses for 3He is in gas proportional counters for neutron detection. Radiation portal monitors deployed for homeland security and non-proliferation use such detectors. Other uses of 3He are for research detectors, commercial instruments, well logging detectors, dilution refrigerators, for targets or cooling in nuclear research, and for basic research in condensed matter physics. The US supply of 3He comes almost entirely from the decay of tritium used in nuclear weapons by the US and Russia. A few other countries contribute a small amount to the world’s 3He supply. Due to the large increase in use of 3He for homeland security, the supply has dwindled, and can no longer meet the demand. This white paper reviews the problems of supply, utilization, and alternatives.

  10. Nuclear hybrid energy systems: imperatives, prospects, and challenges

    International Nuclear Information System (INIS)

    Aumeier, Steven; Cherry, Robert; Boardman, Richard; Smith, Joseph

    2010-01-01

    In less than 60 years we have witnessed the transition of nuclear electricity production from an experiment on the high desert of the western United States to more than 430 commercial nuclear power reactors deployed in 31 countries, supplying nearly 14% of all global electricity consumed. The speed at which this transition took place was stunning, as has been the evolution of the technology, business management and operations approach to civil nuclear electricity production. Even as the United States took a two-decade hiatus from the construction of new nuclear electricity plants, other nations embraced the technology and continue to do so. Today, there are 53 nuclear power reactors under construction, 142 planned and 327 proposed for development, including a number in the United States

  11. PACS in nuclear medicine

    International Nuclear Information System (INIS)

    Kang, Keon Wook

    2000-01-01

    PACS (Picture Archiving and Communication System) is being rapidly spread and installed in many hospitals, but most of the system do not include nuclear medicine field. Although additional costs of hardware for nuclear medicine PACS is low, the complexity in developing viewing software and little market have made the nuclear medicine PACS not popular. Most PACS utilize DICOM 3.0 as standard format, but standard format in nuclear medicine has been Interfile. Interfile should be converted into DICOM format if nuclear images are to be stored and visualized in most PACS. Nowadays, many vendors supply the DICOM option in gamma camera and PET. Several hospitals in Korea have already installed nucler PACS with DICOM, but only the screen captured images are supplied. Software for visualizing pseudo-color with color lookup tables and expressing with volume view should be developed to fulfill the demand of referring physicians and nuclear medicine physicians. PACS is going to integrate not only radiologic images but also endoscopic and pathologic images. Web and PC based PACS is now a trend and is much compatible with nuclear medicine PACS. Most important barrier for nuclear medicine PACS that we encounter is not a technical problem, but indifference of investor such as administrator of hospital or PACS. Now it is time to support and invest for the development of nuclear medicine PACS

  12. A model for reliability avaliation of the electrical supply source of the 1A3 and 1A4 control rods assemblies of Angra I reactor

    International Nuclear Information System (INIS)

    Yang, T.

    1978-01-01

    The reliability of the electrical power supply to the 4.16KV buses for the safety system operation of a nuclear power plant was studied. Particularly, Angra Unit I system was focused. Initially, reliability of each electrical supply source was estimated. Using a probabilistic approach based on the Markov processes, the system reliability was evaluated in terms of frequency and duration of loss of power supply and of the system failure probability evolution when one or more sources remained unavailable. Based on these results, certain reactor operating rules were proposed concerning later shutdown of the plant without compromising the nuclear reactor safety. A sensitivity analysis was also performed to show the different reliability parameter influences on final results. This analysis showed that the diesel system performs an important role in the power supply for a nuclear power plant [pt

  13. Fill Rates of Single-Stage and Multistage Supply Systems

    OpenAIRE

    Matthew J. Sobel

    2004-01-01

    A supply system's fill rate is the fraction of demand that is met from on-hand inventory. This paper presents formulas for the fill rate of periodic review supply systems that use base-stock-level policies. The first part of the paper contains fill-rate formulas for a single-stage system and general distributions of demand. When demand is normally distributed, an exact expression uses only the standard normal distribution and density functions, and a good approximation uses only the standard ...

  14. Transfer system development for a remote inspection robot in nuclear power plants

    International Nuclear Information System (INIS)

    Mizuno, M.; Ohnuma, M.; Hamada, K.; Mizutani, T.; Shimada, A.; Segawa, M.; Kubo, K.

    1984-01-01

    A remote operated robot system has been developed for inspection inside the primary containment vessel (PCV) of nuclear power plants. This system consists of an inspection vehicle, a monorail driving system, a signal transmission system, a power supply system and an operator console.. The system has two main features. First is that the operator can transfer the vehicle at any time from outside the PCV to inside or vice versa through a personnel airlock. The second feature is that the vehicle can be transported from one inspection route to another route at junction points. A prototype inspection robot system was fabricated on a trial basis. Running and inspection performances were confirmed utilizing actual size test apparatus

  15. Nuclear power plants

    International Nuclear Information System (INIS)

    Margulova, T.Ch.

    1976-01-01

    The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

  16. TECDO-online, documentation system for nuclear engineering data

    International Nuclear Information System (INIS)

    Hoepfner, K.A.; Keusenhoff, J.; Riedel, U.

    1993-01-01

    TECDO-online is the database offered by GRS for information on nuclear installations. The system contains full-text information, illustrations and drawings, which are transmitted online to the PC of the user. The TECDO-online database has been established for the purpose of supplying a centralized database with expertly analysed, evaluated and processed data, offering a userfriendly retrieval and data handling software for the geographically distributed users, and regular file updating and compatibility checking by the database supplier. The system is fully implemented and meets with increasing interest among users. It currently contains approx. 120,000 full-text pages, 40000 images (pictures, drawings, and reproduced textual information) as well as data on about 25,000 large-size technical drawings from the drawing archive of the GRS. (orig./DG) [de

  17. An intelligent traceability system: Efficient tool for a supply chain sustainability

    Science.gov (United States)

    Bougdira, Abdesselam; Ahaitouf, Abdelaziz; Akharraz, Ismail

    2016-07-01

    The supply chain sustainability becomes a necessity for a smooth, a rapid and a fluid economic transaction. To reach a sustainable supply chain, we propose to focus attention on products and their lifecycle. So, we consider the traceability as a major success key to ensure the supply chain sustainability. For that, we consider a supply chain design that use an intelligent products traced by an intelligent traceability system. This system identifies, restores history and properties of a product, besides it tracks, in real-time a product. This solution can, also, bring, in the product environment, appropriate adjustments to prevent any risk of threatening qualities for the product. So, it helps supply chain contributors making the sustainable adjustments and the instant benchmark of the supply chain sustainability.

  18. Perspectives of energy supply. Possibilities for restructuring the energy supply of Baden-Wuerttemberg with special regard to power supply. Materials volume 6. Nuclear power. Pt. 2. Perspektiven der Energieversorgung. Moeglichkeiten der Umstrukturierung der Energieversorgung Baden-Wuerttembergs unter besonderer Beruecksichtigung der Stromversorgung. Materialienband 6. Kernenergie. T. 2

    Energy Technology Data Exchange (ETDEWEB)

    Voss, A; Schatz, A; Herold, H

    1987-01-01

    The accident of Chernobyl certainly is a good reason to make once more a critical and very thorough review of the part nuclear energy will play in future in the supply of energy. The government of the Land Baden-Wuerttemberg commissioned an expert opinion in the summer of 1986 with the following intentions: To make a comprehensive analysis of ways technically feasible to safeguard the energy supply of Baden-Wuerttemberg in the long term, evaluate these as to their ecological, economic, and social repercussions, and to investigate in particular whether, to what extent and by what steps nuclear energy use can be made superfluous and what consequences this will entail. Building on the current state of knowledge, the expert opinion is to provide the basic data for weighing the benefits and risks of different technically feasible forms that the energy supply of Baden-Wuerttemberg may take in future. This publication presents the results of more than a year's intensive research work. This volume contains the complete scientific data of the sub-project 'Nuclear Power'. The summarizing final report indicates the position of this sub-project within the overall problem.

  19. DC power supplies power management and surge protection for power electronic systems

    CERN Document Server

    Kularatna, Nihal

    2011-01-01

    Modern electronic systems, particularly portable consumer electronic systems and processor based systems, are power hungry, compact, and feature packed. This book presents the most essential summaries of the theory behind DC-DC converter topologies of both linear and switching types. The text discusses power supply characteristics and design specifications based on new developments in power management techniques and modern semiconductors entering into the portable electronics market. The author also addresses off-the-line power supplies, digital control of power supply, power supply protection

  20. OVERVIEW OF THE RHIC INSERTION REGION, SEXTUPOLE, AND SNAKE POWER SUPPLY SYSTEMS

    International Nuclear Information System (INIS)

    BRUNO, D.; ENG, W.; GANETIS, G.; LAMBIASE, R.F.; SANDBERG, J.

    2001-01-01

    The Relativistic Heavy Ion Collider (RHIC) was commissioned in 1999 and 2000. RHIC requires power supplies to supply currents to highly inductive superconducting magnets. The RHIC Insertion Region (IR) contains many shunt power supplies to trim the current of different magnet elements in a large superconducting magnet circuit. There are a total of 237 Insertion Region power supplies in both RHIC rings. RHIC also requires sextupole power supplies. One sextupole power supply is connected across 12 sextupole magnets. There are a total of 24 sextupole power supplies in both rings. Snake magnets are also a part of the RHIC ring, and these snake magnets also require power supplies. There shall be a total of 24 snake power supplies in both rings. Power supply technology, connections, control systems and interfacing with the Quench Protection System will be presented