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Sample records for chugoku electric power company reactor

  1. Alteration in reactor installation (addition of Unit 2) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (inquiry)

    International Nuclear Information System (INIS)

    1983-01-01

    An inquiry was made by the Ministry of International Trade and Industry to Nuclear Safety Commission on the addition of Unit 2 in Shimane Nuclear Power Station of The Chugoku Electric Power Co., Inc., concerning the technical capability of Chugoku Electric Power Co., Inc., and the plant safety. The NSC requested the Committee on Examination of Reactor Safety to make a deliberation on this subject. Both the technical capability and the safety of Unit 1 were already confirmed by MITI. Unit 2 to be newly added in the Shimane Nuclear Power Station is a BWR power plant with electric output of 820 MW. The examination made by MITI is described: the technical capability of Chugoku Electric Power Co., Inc., the safety of Unit 2 about its siting, reactor proper, reactor cooling system, radioactive waste management, etc. (J.P.N.)

  2. Treatment of opinions, etc. in the public hearing on the alteration of reactor installation (addition of Unit 2) in the Shimane Nuclear Power Station of The Chugoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1983-01-01

    The Nuclear Safety Commission has acknowledged the governmental policy, and further decided on the treatment of the opinions expressed by the local people in the public hearing held in May, 1983, in Shimane Prefecture on the addition of Unit 2 to the Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. The NSC has directed the Committee on Examination of Reactor Safety to take into consideration the opinions in its later examination. The opinions expressed by the local people in the form of question are given as follows: siting conditions (earthquake, ground, weather, etc.), the safety design for reactor installation (general aspect, aseismatic design, core design, ECCS, the teaching of TMI accident, etc.), radioactive wastes, radiation exposure, site evaluation. (Mori, K.)

  3. Progress of innovation of electrical power technology in FY2013

    International Nuclear Information System (INIS)

    Mayumi, Akihiko; Tanaka, Masanori; Yamaguchi, Hiroshi

    2014-01-01

    The following is the description of technical innovations at 12 companies including Tokyo Electric Power Company, Chubu Electric Power Company, and Japan Atomic Power Company. Tokyo Electric Power Company presented (1) the developments of a wet-type air decontaminating apparatus for inside/outside of power plant, (2) a robot to be used for field investigation at the Fukushima Daiichi nuclear power plant, (3) a visualization technology using laser for detection, and (4) removal of debris at the power plant. Chubu Electric Power Company presented application of a flap gate to the opening on exterior wall of building as a countermeasure against tsunami at the Hamaoka nuclear power plant. Hokuriku Electric Power Company presented a nuclear reactor operation training simulator for full-scope operation training for the Shika nuclear power station. Chugoku Electric Power Company presented their efforts in implementing a predictive monitoring system at the Shimane Nuclear Power Station. Shikoku Electric Power Company presented the installation of a weir with a flap gate to the interior of seawater pit as a countermeasure against tsunami. Japan Atomic Power Company presented an impact assessment method of fallout during transportation of materials caused by nuclear reactor accident, design and development of a square-type shielding container for radioactive wastes, a strength test on concrete materials for the safety design of Tsuruga Power Station Units 3 and 4, decommissioning of nuclear power plant, and research and development of the fast breeder reactor. (S.Y.)

  4. Experiences for construction and preoperation test of Shimane nuclear power station

    International Nuclear Information System (INIS)

    Niki, Yoshiya; Taniguchi, Takashi.

    1975-01-01

    Shimane nuclear power station of Chugoku Electric Power Company has begun its commercial operation on March 29, 1974 after the construction period of 49.5 months. The fundamental construction process which Chugoku Electric Power Company and Hitachi Ltd. had agreed was 45 month process, which was the readjustment of the construction process which General Electric Company had presented for preceding nuclear power plants in Japan and its results. The achieved construction and test process required 49.5 months with 4.5 months delay. This delay occurred in two points. The one was caused by the ''upside down'' problem of control rods which had been imported from G.E. The another was caused by the restriction of the rate of load increasing. Fuel charging which indicates the substantial finish of construction works, had begun at May 1, 1973 on schedule. Therefore it can be said that the construction works had been carried out just according to the fundamental process. However, analyzing the result of progress, the pressure test of a reactor containment vessel and the set-up and the first pressure test of a reactor pressure vessel led the schedule by about 2 months. On the contrary, the subsequent works delayed by just that leading time. (Tai, I.)

  5. Advance of technological innovations of electric power in 2012

    International Nuclear Information System (INIS)

    Mayumi, Akihiko; Tanaka, Masanori; Takebe, Toshiro

    2013-01-01

    Twelve companies in Japan reported on the technological innovations in 2012. The Japan Atomic Power Company mainly studied five projects; (1) control of wall thinning of the secondary system in PWR by injection of molybdic acid, (2) application of pipe test method using electromagnetic acoustic resonance to existing equipment, (3) developed high performance Co-60 crud removal resin for Tsuruga Power Station Unit 2, (4) improvement of technology for safety of core in FBR, and (5) improvement of technology for coolant of FBR by dispersing nano-particles in liquid sodium metal. Tokyo Electric Power Company developed mainly three projects; (1) the support for the mental health care activities by industry protection staff at the Fukushima Daiichi and Daini Nuclear Power Plant, (2) laboratory test method using non-radioactive cesium for performance of decontamination reagent, and (3) decontamination effects estimation code (DeConEP). Hokuriku Electric Power Company reported the operations management measures in accordance with the safety enhancement measures to Shika nuclear power station. Other nine reports are published by Hokkaido Electric Power Co., Inc. Tohoku Electric Power Co., Inc. Chubu Electric Power Co., Inc., The Kansai Electric Power Co., Inc., The Chugoku Electric Power Co., Inc., Shikoku Electric Power Co., Inc., Kyushu Electric Power Co., Inc., Okinawa Electric Power Company Inc. and J-Power. (S.Y.)

  6. Modification of reactor installation in the Genkai nuclear power plant No. 1 of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 25, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Genkai nuclear power plant No. 1 of the Kyushu Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kyushu Electric Power Company, Inc., to the Minister of International Trade and Industry on July 24, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  7. Inquiry relating to modifications of reactor installation in Ikata No. 1 and 2 nuclear power plants of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Ikata No. 1 and 2 nuclear power plants of the Shikoku Electric Power Company, Inc., on February 13, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the Atomic Energy Safety Commission (AESC) on June 15, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for No. 1 plant and the modification of driving mechanism from the roller nut type to the magnetic jack type for the control rod cluster for adjusting power distribution in the No. 2 plant. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. Relating to the driving mechanism for the control rod cluster adjusting power distribution, the driving speed is not modified and the reliability is kept by carrying out the continuous operation test and the electric power black out test as the demonstration test. The magnetic jack type mechanism has the locking device to prevent reactor tripping at the time of electric power black out, and the cluster is held at the location where the cluster existed at the time of black out. (Nakai, Y.)

  8. Modification of reactor installation in the Takahama nuclear power plants No.1 and No.2 of Kansai Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    The Nuclear Safety Commission recognized the adequacy concerning the inquiry which was offered from the Minister of International Trade and Industry on July 24, 1979, following the safety evaluation in the Ministry of International Trade and Industry, and decided to submit a report to the Minister of International Trade and Industry on July 26, 1979, about the modification of reactor installation in the Takahama nuclear power plants No. 1 and No. 2 of the Kansai Electric Power Company, Inc. This is concerned to the application which was made from the president of the Kansai Electric Power Company, Inc., to the Minister of International Trade and Industry on July 23, 1979. The content of the modification is to add a control circuit which is actuated by the signal of abnormal low pressure in a reactor to the circuit of actuating the emergency core cooling system of the plant. The influences on the safety protection system by the addition of the circuit for transmitting safety injection signal and by the additions of an interlock circuit preventing the misoperation of pressurizer spray and of a block circuit of safety injection signal in case of the abnormal low pressure in a reactor were evaluated. The effects on the function and characteristics of the emergency core cooling system due to the addition of the control circuit were investigated, and it was recognized by the analysis that there is no effect in the pipe ruptures of both small and large scales. (Nakai, Y.)

  9. New energy introduction guidebook for Chugoku area; Shin energy donyu guidebook. Chugoku chiiki

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-05

    A guidebook was edited for the purpose of assisting introduction of new energies. Sections consist of Section 1, new energies available in the Chugoku area; Section 2, procedure for new energy introduction; Section 3, assistance institutions by energy; and Section 4, the status of new energy introduction in the Chugoku area, the future introduction targets, and referential materials. Section 1, upon defining the new energies, summarized features of photovoltaic power generation, solar heat utilization, wind power generation, wastes power generation, cogeneration, fuel cells, clean energy fueled automobiles, and introduction records up to the year 2000. Section 2 summarizes the general roles of local governments in the introduction, processing procedures for individual programs, related regulations, and summary of the assistance institutions. Section 3 puts into order the assistance institutions by energy. Section 4 summarizes precautions, targets and records in introduction by each new energy. The referential materials include a list of the Japanese assistance institutions, and subsidy institutions related to new energies for local governments in the Chugoku area. (NEDO)

  10. Installation modification of the reactor No.2 of Ikata nuclear power plant of Shikoku Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1980-01-01

    The application was made on August 25, 1979, from the president of the Shikoku Electric Power Company, Inc., to the Minister of International Trade and Industry, relating to the installation modification of the reactor No. 2 in the Ikata nuclear power plant. The inquiry was submitted on September 28, 1979, from the Minister of International Trade and Industry to the Nuclear Safety Commission, after the safety evaluation in the Ministry of International Trade and Industry, and the investigation and deliberation were started on October 1, 1979, in the Nuclear Safety Commission. The content of the modification is to add the circuit actuated by the abnormal low pressure signal of the reactor to the actuating circuit of the emergency core cooling system (ECCS) and to increase the new fuel storage capacity from about 1/3 core to about 2/3 core. The additional signal circuit is composed of the logic circuit of ''2 out of 4'' and is multichannel design. The circuit is independent from the reactor control system and the conventional signal circuit of the concurrence of low pressure in the reactor and low level in the pressurizer. With the addition of the circuit of abnormal low pressure signal of the reactor, the countermeasures for preventing ECCS start by mistake are also added. These modifications give no influence to the functions of the reactor control system and reactor protection system. The function and the performance of ECCS were analyzed and evaluated accompanying these modifications assuming the loss of coolant accident. Concerning the new fuel storage capacity, the type of racks is modified from angle type to can type, and the subcriticality is kept even at the time of water flood. (Nakai, Y.)

  11. Advance in technologies of electric power in 2008

    International Nuclear Information System (INIS)

    Hamada, Kenichi; Maekawa, Fumiaki; Nakamura, Akio

    2008-01-01

    Ten electric power companies and two related companies reported their advance in technologies. The technologies of nuclear power plants were stated by ten companies, which consisted of introduction of new main control board to Tomari-3 in Hokkaido Electric Power Co., Inc., reduction methods of exposure dose of Higashidori-1 in Tohoku Electric Power, hot water based two-phase flow testing device for pipe thinning test by Tokyo Electric Power Company, Guideline for prevention of piping damage caused by combustion of mixture gases in BWR (the second edition) published by Thermal and Nuclear Power Engineering Society, setting up distributor in the low-pressure turbine of Shika-2 in Hokuriku Electric Power Company, development of rapid estimation method of release radioactivity and application of high density neutron source to nuclear transmutation of nuclear fuel cycle and introduction of new core monitor system by The Kansai Electric Power Co., Inc., upgrade of investigation of the effects of hot waste water and development of detector for dropout parts of cooling system in reactor by Shikoku Electric Power Co., Inc., change of transformer in Sendai-1 by Kyushu Electric Power Co., Inc., and reactor core design for Oma ABWR by J-Power. The Japan Atomic Power Company reported four articles such as development of technologies for established nuclear power plants, promotion of Tsuruga-3 and Tsuruga-4, application of clearance system in Japan and development of future reactors. (S.Y.)

  12. Experience of electric power conservation in COELBA (Bahia Electric Company)

    International Nuclear Information System (INIS)

    Bastos, A.C.F.

    1990-01-01

    The electric power crisis of Brazilian north-east in 1987 imposes the Bahia Electric Company-COELBA to management a electric power conservation. The institutional, organizational and operational aspects are presented, including the tariff system, the market, the consumption and the relation with public. (author)

  13. Innovation in electric power technologies in 2009

    International Nuclear Information System (INIS)

    Ohfusa, Takahiro; Hayasaka, Eiji; Ino, Hiroyuki

    2010-01-01

    This is a report of the title by Tokyo Electric Power Company, Kansai Electric Power Co., Inc, Tohoku Electric Power and other nine enterprises in Japan. The outline is as follows. Tokyo Electric Power Company stated pipe thinning by the hot water based two-phase flow testing device, development of technologies for corrosion protection of nuclear reactor using titanium oxide, evaluation of fatigue damage by EBSD, and study of duty on the nuclear power plant. Japan Atomic Power Company (JAPC) stated the mechanism of decrease in exposure dose of the primary coolant system by zinc infusion, outline of Air Operated Valve Intelligent Diagnostic Analysis System (AVIDAS) and the grand packing system, development of SAPLS, the automatic search program of fuel position for design of PWR related core, development of compact containment water reactor (CCR) and FBR cycle system, investigation of the chain destruction of active fault under consideration of dynamic interaction of active faults and decommissioning of Tokai Nuclear Power Plant. Electric Power Development Company reported construction of the Oma Nuclear Power Plant, a future nuclear plant in Oma, Aomori. The reactor will be capable of using 100% MOX fuel core (MOX-ABWR). The operation will start November 2014. (S.Y.)

  14. TU Electric reactor physics model verification: Power reactor benchmark

    International Nuclear Information System (INIS)

    Willingham, C.E.; Killgore, M.R.

    1988-01-01

    Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

  15. Reactor power control method upon accidents of electrical power system

    International Nuclear Information System (INIS)

    Hirose, Masao.

    1983-01-01

    Purpose: To enable to continue the operation of a BWR type reactor by avoiding the scram while suppressing the reactor power, just after the external disturbance such as earth-trouble in power-transmission network. Method: Steep power drop of an electrical generator is to be detected not only by a current-type power-load-unbalance relay but also with a power-type power-load-unbalance-relay. If steep power-drop was detected by the latter relay, a previously selected control rod is rapidly inserted into the reactor. In this way, in the case where there is a possibility of the reactor scram, the scram can be avoided by suppressing the reactor power, thus the reactor operation can be continued. (Kamimura, M.)

  16. 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)

  17. Service hall in Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc

    International Nuclear Information System (INIS)

    Tawara, Shigesuke

    1979-01-01

    There are six BWR type nuclear power plants in the Number 1 Fukushima Nuclear Power Station, Tokyo Electric Power Company, Inc. The service hall of the station is located near the entrance of the station. In the center of this service hall, there is the model of a nuclear reactor of full scale. This mock-up shows the core region in the reactor pressure vessel for the number one plant. The diameter and the thickness of the pressure vessel are about 5 m and 16 cm, respectively. The fuel assemblies and control rods are set just like the actual reactor, and the start-up operation of the reactor is shown colorfully and dynamically by pushing a button. When the control rods are pulled out, the boiling of water is demonstrated. The 1/50 scale model of the sixth plant with the power generating capacity of 1100 MWe is set, and this model is linked to the mock-up of reactor written above. The operations of a recirculating loop, a turbine and a condenser are shown by switching on and off lamps. The other exhibitions are shielding concrete wall, ECCS model, and many kinds of panels and models. This service hall is incorporated in the course of study and observation of civics. The good environmental effects to fishes and shells are explained in this service hall. Official buildings and schools are built near the service hall utilizing the tax and grant concerning power generation. This service hall contributes to give much freedom from anxiety to the public by the tour. (Nakai, Y.)

  18. History of electric power technological innovation in 2017

    International Nuclear Information System (INIS)

    Yamaguchi, Hiroshi; Okabe, Kazuhiko; Ichimura, Yasunori

    2017-01-01

    This is an overview of the electric power technology innovation of 12 electric power companies in 2016. Among them, this paper outlines the technological contents related to nuclear power of three major companies. TEPCO group applied a sealant from the outside to the back-up seal of reactor containment vessel that had deteriorated. It developed a good sealing system by combining with an improved sealant, and confirmed the effect at an experimental level. Regarding environmental restoration in Fukushima, TEPCO developed a personal dosimetry technology, environmental monitoring technology, and a technology to simulate radiation reduction amount after decontamination. Chubu Electric Power Company conducted researches on the applicability of the start-up range neutron monitor count rate prediction method related to fuel loading after a long-term shut-down of nuclear power generation, basic examination for practical use of laser decontamination, and possibility of tsunami prediction using satellite positioning information. With regard to the decommissioning measures of nuclear power plants, Japan Nuclear Power Electric Generation Co., Ltd. conducted studies on the decommissioning work of the Tokai Power Station, the safe dismantling method of the Tsuruga Power Station Unit 1 as decommissioning measures and fuel management, and the disposal method of radioactive contaminants. In the development of future reactor, this company conducted research on the development of fast breeder reactor system, etc. (A.O.)

  19. Inquiry relating to modification of reactor installation of Hamaoka No. 2 nuclear power plant of Chubu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modification of reactor installation of the Hamaoka No. 2 nuclear power plant, Chubu Electric Power Company, Inc., on February 8, 1979, from the president of the company. After the safety evaluation in the Ministry of International Trade and Industry was finished, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on May 25, 1979, from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on May 28, 1979. The modification of the reactor installation is the increase of spent fuel storage capacity from about 220% of in-core fuel at present to about 325%. The fundamental philosophy of the safety evaluation includes the following items; 1) the storage capacity of spent fuel is adequate, 2) the design is such that the criticality is prevented under any assumed condition, 3) the sufficient cooling capacity is kept for decay heat removal, 4) and others required for the safety. The contents of the safety examination for each philosophical item written above are presented. The increased spent fuel storage capacity is equivalent to the quantity produced in about eight years. The prevention of criticality in the spent fuel storage is carefully practiced by putting fuel assemblies in the stainless steel racks with large neutron absorption cross section and locating spent fuel assemblies at the proper distances. The effective multiplication factor is less than 0.95 at the most severe arrangement in the fuel pool. The water temperature in the pool is less than 65 deg C at about 325% core storage by operating the spent fuel pool water cooling system. The spent fuel storage racks are designed as the A class aseismatic structure. (Nakai, Y.)

  20. Progress of technological innovation on electric power in FY2014

    International Nuclear Information System (INIS)

    Nishikawa, Yoshikazu; Fujii, Yutaka; Sasagawa, Toshiro

    2015-01-01

    This paper overviews the technological development in FY2014 at Tokyo Electric Power Company, Chubu Electric Power Company, Hokuriku Electric Power Company, Shikoku Electric Power Company, and Electric Power Development Company. In this overview, further breakdown was made for the following departments of each company: nuclear power generation, thermal power generation, hydraulic power generation, power transmission, power distribution, transformation, research and development and technological development, and information and communication. In addition, this paper outlines the achievement of technological development at Japan Atomic Power Company, such as the technological development related to the existing power station, development of new technology, and the development of future reactor. Fukushima Daiichi Nuclear Power Station has developed an investigative system using a high altitude survey robot and a movable monitoring system. Hamaoka Nuclear Power Station examined the feasibility of state diagnostic technique based on multi-point analysis, and studied stress corrosion cracking at the newly established Nuclear Safety Research Laboratory. Shika Nuclear Power Station (Unit 1) applied a pipe stress improvement process by means of high frequency induction heating as a stress corrosion cracking countermeasure. Ikata Nuclear Power Station newly adopted high degree cross-linking cation resin, and high cracking strength anion resin as the primary resins. Oma Nuclear Power Station worked on the all reactor core utilization technology of MOX fuel. (A.O.)

  1. Table of written agreements on securing safety of nuclear power plants (Saga, Shimane, Fukushima, Ehime, Miyagi, Ibaraki, Fukui and Shizuoka prefectures)

    International Nuclear Information System (INIS)

    1981-01-01

    A table collecting the written agreements concluded between local city, town and village offices, prefectural governments and the local nuclear enterprises on securing nuclear power safety is given, which was prepared by the study committee on local development and finance problems in Japan Atomic Industrial Forum, Inc. The prefectures, with each of which the agreement was concluded are Saga, Shimane, Fukushima, Ehime, Miyagi, Ibaraki, Fukui and Shizuoka. The local nuclear enterprises are Kyushu, Chugoku, Tokyo, Shikoku, Tohoku, Chubu and Kansai Electric Power Companies, Japan Atomic Power Company, Japan Atomic Energy Research Institute, Power Reactor and Nuclear Fuel Development Corporation, etc. The contents of the agreements are as follows: radioactive waste and material control, understanding in advance of plans, environmental radioactivity measurement, presentation of measured results, hazard countermeasures, communication in normal plant operation and others, on the spot inspection, damage compensation, etc. (J.P.N.)

  2. Evaluation of efficiency in Japan electric power companies

    International Nuclear Information System (INIS)

    Ghaderi, F.; Muyajima, M.

    2001-01-01

    Achieving energy efficiency also must consider supply efficiency, how much energy it takes to generate electricity and transmit it to the end user. system efficiency reflects the loss of energy during the processes of generation, transmission and distribution of electricity. Of the millions of tons of coal that are burned to produce heat in generation of electricity every year, only one third is converted into electricity.The electric power plant immediately uses 5 to 10 percent of that energy for use in the plant. Around another 10 percent of this energy is consumed in the transmission and distribution of electric energy to end users. Overall,more that 70 percent of the energy used to produce and deliver electricity never gets to the end user. The costs of this wasted energy are reflected in the customer's electricity bill. Furthermore, once delivered, users of electricity are subjected to more h idden c osts the demand charge which reflects the rate at which consumers draw energy from the power plant during a particular time of day, are also affected by the time of year. This additional charge c n be dramatic. For example, the cost for using electric air conditioning at the w rong t ime of the day , are also affected by the time of year. This additional charge can be dramatic. For example, the cost for using electric air conditioning at the wrong time of the day could be as much as 25 to 40 percent higher than what a facility normally pays for electricity during off-peak times. Minimizing the costs of operations, therefor, is a must for all electric companies. In the other hand utility rates, such as the cost of electricity, are a necessary element of operating in all enterprises.In some industries the payment over electricity make a large percentage of their total expenses, but that doesn't mean that every effort should not be made to reduce their impact on the bottom line, it should be considered that a very small change in operating procedure can change

  3. Inquiry relating to modifications of reactor installation in Genkai No. 1 and 2 nuclear power plants of Kyushu Electric Power Company, Inc

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the Minister of International Trade and Industry for the license relating to the modifications of reactor installation in the Genkai No. 1 and 2 nuclear power plants, Kyushu Electric Power Company, Inc., on February 27, 1979, from the president of the company. After the safety evaluation was finished by the Ministry of International Trade and Industry, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 15, 1979 from the Minister of International Trade and Industry. The investigation and discussion were commenced by the AESC on June 19, 1979. The modifications of the reactor installation are the increase of new fuel storage capacity from about 1/3 to about 2/3 of in-core fuel for each plant, the new establishment of a miscellaneous solid waste incinerator which is common to both plants, and the enlargement of a solid waste storage which is also common to both plants. The contents of the safety examination for each item written above are presented. The prevention of criticality is carefully practiced for the new fuel storage by putting fuel assemblies in stainless steel can type racks and locating the fuel assemblies at the proper distance. The miscellaneous solid waste incinerator building is designed as the B class aseismatic structure and also as the controlled area with adequate shielding and ventilating facilities. The decontamination factor of the incinerator facility is more than 10 5 , and the necessary monitoring system is provided in the building. Concerning the solid waste storage, the additional storage area is about 1600 m 2 , and the storage capacity is about ten years quantity. This building is designed as the B class aseismatic structure. (Nakai, Y.)

  4. Innovations in techniques of electric power in 2008

    International Nuclear Information System (INIS)

    Ohfusa, Takahiro; Endo, Yukio; Ino, Hiroyuki

    2009-01-01

    Tokyo Electric Power Company (TEPCO), Kansai Electric Power Co., Inc., Tohoku Electric Power and other nine companies reported the results of innovations in techniques of electric power in 2008, Japan. J-Power started construction of the Ohma Nuclear Power Plant (power generating capacity: 1,383 MW, ABWR) in Ohma Town, Aomori prefecture, Japan, in May 2008. TEPCO developed the low vibration control valve and carried out the model experiments using air as fluid and the simulation by computational fluid dynamics. Mach number distribution (ε L =0.068) at the valve showed change of the supersonic jet flow as time advanced and a periodic pressure change on the valve and valve seat. Japan Atomic Power Company reported development of techniques for the established nuclear power station such as control of pipe thinning of the secondary system of PWR by insertion of oxygen at Tsuruga Power Station Unit 2, risk evaluation, the effects of increase of generating power on aging deterioration, and development of heat protective clothing. Researched are a power generation plant of small-and-medium-size reactors which took in reforming technology using the location to a narrow site, funds by stakeholders and the idea of future 'fast breeder reactor system', sodium-cooled loop type reactor, which uses TRU as fuel. The accumulator tank of new type safety system for Tsuruga Power Station Unit 3 and 4 is designed and tested. Decommissioning process of Tokai Power Plant and recycling of shielding materials, blocks and concrete powder are stated. (S.Y.)

  5. Electric Holding Company Areas

    Data.gov (United States)

    Department of Homeland Security — Holding companies are electric power utilities that have a holding company structure. This vector polygon layer represents the area served by electric power holding...

  6. Electric power from near-term fusion reactors

    International Nuclear Information System (INIS)

    Longhurst, G.R.; Deis, G.A.; Miller, L.G.

    1981-01-01

    This paper examines requirements and possbilities of electric power production on near-term fusion reactors using low temperature cycle technology similar to that used in some geothermal power systems. Requirements include the need for a working fluid with suitable thermodynamics properties and which is free of oxygen and hydrogen to facilitate tritium management. Thermal storage will also be required due to the short system thermal time constants on near-time reactors. It is possbile to use the FED shield in a binary power cycle, and results are presented of thermodynamic analyses of this system

  7. Thermionic reactor power conditioner design for nuclear electric propulsion.

    Science.gov (United States)

    Jacobsen, A. S.; Tasca, D. M.

    1971-01-01

    Consideration of the effects of various thermionic reactor parameters and requirements upon spacecraft power conditioning design. A basic spacecraft is defined using nuclear electric propulsion, requiring approximately 120 kWe. The interrelationships of reactor operating characteristics and power conditioning requirements are discussed and evaluated, and the effects on power conditioner design and performance are presented.

  8. Development of small and medium reactors for power and heat production

    International Nuclear Information System (INIS)

    Becka, J.

    1978-01-01

    Data are given on the current state of development of small and medium-power reactors designed mainly for electric power production in small power grids, for heat production for small- and medium-power desalination plants with possible electric power generation, for process steam production and heat development for district heating systems, again combined with electric power generation, and for propelling big and fast passenger ships. A diagram is shown of the primary system of an integrated PWR derived from the Otto Hahn reactor. The family is listed of the standard sizes of the integral INTERATOM company pressurized water reactors. Also listed are the specifications and design of CAS 2CG and AS 3G type reactors used mainly for long-distance heating systems. (J.B.)

  9. Nuclear reactors for space electric power

    International Nuclear Information System (INIS)

    Buden, D.

    1978-06-01

    The Los Alamos Scientific Laboratory is studying reactor power plants for space applications in the late 1980s and 1990s. The study is concentrating on high-temperature, compact, fast reactors that can be coupled with various radiation shielding systems and thermoelectric, dynamic, or thermionic electric power conversion systems, depending on the mission. Lifetimes of 7 to 10 yr at full power, at converter operating temperatures of 1275 to 1675 0 K, are being studied. The systems are being designed such that no single-failure modes exist that will cause a complete loss of power. In fact, to meet the long lifetimes, highly redundant design features are being emphasized. Questions have been raised about safety since the COSMOS 954 incident. ''Fail-safe'' means to prevent exposure of the population to radioactive material, meeting the environmental guidelines established by the U.S. Government have been and continue to be a necessary requirement for any space reactor program. The major safety feature to prevent prelaunch and launch radioactive material hazards is not operating the reactor before achieving the prescribed orbit. Design features in the reactor ensure that accidental criticality cannot occur. High orbits (above 400 to 500 nautical miles) have sufficient lifetimes to allow radioactive elements to decay to safe levels. The major proposed applications for satellites with reactors in Earth orbit are in geosynchronous orbit (19,400 nautical miles). In missions at geosynchronous orbit, where orbital lifetimes are practically indefinite, the safety considerations are negligible. Orbits below 400 to 500 nautical miles are the ones where a safety issue is involved in case of satellite malfunction. The potential missions, the question of why reactors are being considered as a prime power candidate, reactor features, and safety considerations will be discussed

  10. Nuclear reactor capable of electric power generation during in-service inspection

    International Nuclear Information System (INIS)

    Nakamura, Shinsuke; Nogami, Hitoshi.

    1992-01-01

    The nuclear power plant according to the present invention can generate electric power even in a period when one of a pair of reactors is put to in-service inspection. That is, the nuclear power plant of the present invention comprises a system constitution of two nuclear reactors each of 50% thermal power and one turbine power generator of 100% electric power. Further, facilities of various systems relevant to the two reactors each of 50% thermal power, as a pair, are used in common as much as possible in order to reduce the cost for construction and maintenance/ inspection. Further, a reactor building and a turbine building disposed in adjacent with each for paired two reactors each of 50% thermal power are arranged vertically. This arrangement can facilitate the common use of the facilities for various systems and equipments to attain branching and joining of fluids in reactor feed water systems and main steam system pipelines easily with low pressure loss and low impact shocks. The facility utilization factor of such reactors is remarkably improved by doubling the period of continuous power generation. As a result, economic property is remarkably improved. (I.S.)

  11. Own power: Motives of having electricity without the energy company

    International Nuclear Information System (INIS)

    Leenheer, Jorna; Nooij, Michiel de; Sheikh, Omer

    2011-01-01

    New technologies will enable households to generate an increasing amount of their own electricity. Intentions to generate own power are a preliminary step towards actual behavior. Because own generation is still very limited and the behavior of early adopters may not be representative for the complete population, our study focuses on intentions rather than actual behavior. A consumer survey among 2047 Dutch households reveals that environmental concerns are the most important driver of a household's intention to generate its own power. Affinity with technology and energy and the reputation of electricity companies are also significant drivers, but financial factors and power outages are not. About 40% of Dutch households have an intention to generate their own power, with an overrepresentation of young households. This group falls apart in two sub segments; for the 'generating savers' (21%) a high intention to generate own power coincides with a high intention to save energy, whereas generating users (18%) combine a high intention to generate own power with a low intention to save energy. - Highlights: → A consumer survey studies household intentions to generate own power. → Environmental concerns are the most important motive for generating own power. → Other drivers are affinity with technology and reputation of electricity companies. → About 40% of Dutch households feel a need to generate their own electricity.

  12. Design study of electrical power supply system for tokamak fusion power reactor

    International Nuclear Information System (INIS)

    1977-01-01

    Design study of the electrical power supply system for a 2000MWt Tokamak-type fusion reactor has been carried out. The purposes are to reveal and study problems in the system, leading to a plan of the research and development. Performed were study of the electrical power supply system and design of superconducting inductive energy storages and power switches. In study of the system, specification and capability of various power supplies for the fusion power reactor and design of the total system with its components were investigated. For the superconducting inductive energy storages, material choice, design calculation, and structural design were conducted, giving the size, weight and performance. For thyristor switches, circuit design in the parallel / series connection of element valves and cooling design were studied, providing the size and weight. (auth.)

  13. Attitudes of the general public and electric power company employees toward nuclear power generation

    International Nuclear Information System (INIS)

    Komiyama, Hisashi

    1997-01-01

    We conducted an awareness survey targeted at members of the general public residing in urban areas and in areas scheduled for construction of nuclear power plants as well as employees of electric power company in order to determine the awareness and attitude structures of people residing near scheduled construction sites of nuclear power plants with respect to nuclear power generation, and to examine ways of making improvements in terms of promoting nuclear power plant construction sites. Analysis of those results revealed that there are no significant differences in the awareness and attitudes of people residing in urban areas and in areas near scheduled construction sites. On the contrary, a general sense of apprehension regarding the construction of nuclear power plants was observed common to both groups. In addition, significant differences in awareness and attitudes with respect to various factors were determined to exist between members of the general public residing in urban areas and scheduled construction sites and employees of electric power company. (author)

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

    International Nuclear Information System (INIS)

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

    1990-05-01

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

  15. 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)

  16. 78 FR 43197 - Duke Energy Florida, Inc.; Florida Power & Light Company; Tampa Electric Company; Orlando...

    Science.gov (United States)

    2013-07-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [ER13-1922-000; ER13-1929-000; ER13-1932-000; NJ13-11-000] Duke Energy Florida, Inc.; Florida Power & Light Company; Tampa Electric Company; Orlando Utilities Commission; Notice of Compliance Filings Take notice that on July 10, 2013, Duke Energy...

  17. 76 FR 54259 - Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North Anna Power Station...

    Science.gov (United States)

    2011-08-31

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0185] Virginia Electric and Power Company, Docket Nos. 50.... NPF-4 and NPF-7, issued to Virginia Electric Power Company (the licensee), for operation of the North...) and (d) during declarations of severe weather conditions involving tropical storm or hurricane force...

  18. Status report on nuclear reactors for space electric power

    International Nuclear Information System (INIS)

    Buden, D.

    1978-01-01

    The Los Alamos Scientific Laboratory is studying reactor power plants for space applications in the late 1980s and 1990s. The study is concentrating on high-temperature, compact, fast reactors that can be coupled with various radiation shielding systems and thermoelectric, dynamic, or thermionic electric power conversion systems, depending on the mission. Increased questions have been raised about safety since the COSMOS 954 incident. High orbits (above 400 to 500 nautical miles) have sufficient lifetimes to allow radioactive elements to decay to safe levels. The major proposed applications for satellites with reactors in Earth orbit are in geosynchronous orbit (19,400 nautical miles). In missions at geosynchronous orbit where orbital lifetimes are practically indefinite, the safety considerations are negligible. The potential missions, why reactors are being considered as a prime power candidate, reactor features, and safety considerations are discussed

  19. Selection of power plant elements for future reactor space electric power systems

    International Nuclear Information System (INIS)

    Buden, D.; Bennett, G.A.; Copper, K.

    1979-09-01

    Various types of reactor designs, electric power conversion equipment, and reject-heat systems to be used in nuclear reactor power plants for future space missions were studied. The designs included gas-cooled, liquid-cooled, and heat-pipe reactors. For the power converters, passive types such as thermoelectric and thermionic converters and dynamic types such as Brayton, potassium Rankine, and Stirling cycles were considered. For the radiators, heat pipes for transfer and radiating surface, pumped fluid for heat transfer with fins as the radiating surface, and pumped fluid for heat transfer with heat pipes as the radiating surface were considered. After careful consideration of weights, sizes, reliabilities, safety, and development cost and time, a heat-pipe reactor design, thermoelectric converters, and a heat-pipe radiator for an experimental program were selected

  20. Development on power distribution technologies of four electric power companies in Japan. The Tokyo Electric Power Co. , Inc

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Electric power companies have been needed to cope with various needs in accordance with the progress of highly information-oriented society, the improvement of industrial technology, and the advancement and diversification of the living environment. In such situation, the power distribution section of Tokyo Electric Power has promoted technical development, setting up following priority items to put into operation: to reduce power failure caused by works and accidents, to improve reliability in supply, to reduce costs of construction and all over business management, to serve customers to answer various needs, to develop new technology and new methods based on the medium- and long-term prospect, and so forth. Several examples of recent technical development are introduced here. They are as follows; compact equipment and materials for electric poles to match the circumstances of cities and to simplify the construction method for power distribution, a 750kVA large high-voltage power-generation truck to make provision against an emergency such as a disaster by a typhoon, a compact transformer used on the ground, a high-voltage automatic cabinet, and a detector to find the failure of indoor power distribution works in resistances in a short time. 8 figs.

  1. Development of management systems for nuclear power plant of Hokuriku Electric Power Company

    International Nuclear Information System (INIS)

    Nakamura, Tatsuaki; Hasunuma, Junichi; Suzuki, Shintaro

    2009-01-01

    Hokuriku Electric Power Company has been operating the Shika Nuclear Power Station that it constructed in Shika city, Ishikawa prefecture, for over 15 years since bringing Unit 1 of this plant online in July 1993. In addition to electricity generation, maintenance and inspection tasks constitute a big part of operating a large-scale nuclear power plant, and in recent years, problems at power stations in the nuclear power industry have led to several revisions of nationally regulated maintenance and inspection systems. This paper describes the background, objectives, development method, and features of the Maintenance Management System and Maintenance History Management System that make effective use of information technology to promote safer and more efficient maintenance work at large-scale nuclear power plants. (author)

  2. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  3. To question of NPP power reactor choice for Kazakhstan

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  4. Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

  5. Scottish Nuclear, the company

    International Nuclear Information System (INIS)

    Yeomans, R.M.

    1991-01-01

    A former chief executive of Scottish Nuclear, formed when United Kingdom electricity generation was privatized, describes the financial viability of the company and considers the future of nuclear power. Scottish Nuclear owns and operates the Advanced Gas Cooled (AGR) and Magnox reactors at Hunterston and the AGR reactor at Torness and is a separate company from those dealing with hydro-electric and non-nuclear generation of electricity. Costs of running the reactors is identified as a proportion of the whole for certain key issues such as station costs, depreciation, decommissioning and insurance. While nuclear power generation using outmoded Magnox reactors is costly, the ecological cost of global warming is seen as more of a problem. Future policy for nuclear power in Scotland must include new plant, probably pressurized water reactors and a clear policy of safety enhancement. (UK)

  6. The development strategies of the european electric power companies

    International Nuclear Information System (INIS)

    Heddebaud, D.

    2005-01-01

    This study takes stock on the european market of the electric power and of its development perspectives. It details the strategy and the place of the main operators and shows their forces and weaknesses. It provides a comparison of the financial performances of 28 companies (growth, margins, profitability, debt and war chest). (A.L.B.)

  7. New maintenance strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for effective ageing management and safe long-term operation

    International Nuclear Information System (INIS)

    Inagaki, Takeyuki; Yamashita, Norimichi

    2009-01-01

    Fukushima Dai-ichi Nuclear Power Plant is the oldest among three nuclear power plants owned and operated by Tokyo Electric Power Company, which consists of six boiling water reactor units. The commercial operation of Unit 1 was commenced in 1971 (37 years old) and Unit 6 in 1978 (29 years old). Currently ageing degradations of systems, structures and components are managed through maintenance programs, component replacement/refurbishment programs and long-term maintenance plans. The long-term maintenance plans are established through ageing management component replacement/refurbishment programs reviews performed before the 30th year of operation and they are for safe and reliable operation after 30 years (long-term operation). However the past maintenance actions and past component replacement/refurbishment programs were not always proactive and past operational experience and maintenance practices suggest that effective/proactive ageing management programs be introduced in earlier stage of the plant operation. In this circumstance, Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant are setting up a new maintenance strategy that includes 1) improving the normal maintenance programs by using ageing degradation data, 2) effective use of information on internal/external operational experience and maintenance practices related to ageing, and 3) proactive component/equipment refurbishment programs during a refreshment outage for safe and reliable long-term operation. To accomplish the goal of this strategy, strengthening engineering capability of plant staff members is a crucial required for the plant. The objective of this paper is to briefly explain main results ageing management reviews, past and current significant ageing issues and management programs against them, and the new maintenance strategy established by Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant. (author)

  8. A design study of high electric power for fast reactor cooled by supercritical light water

    International Nuclear Information System (INIS)

    Koshizuka, Seiichi

    2000-03-01

    In order to evaluate the possibility to achieve high electric power by a fast reactor with supercritical light water, the design study was carried out on a large fast reactor core with high coolant outlet temperature (SCFR-H). Since the reactor coolant circuit uses once-through direct cycle where all feedwater flows through the core to the turbine at supercritical pressure, it is possible to design much simpler and more compact reactor systems and to achieve higher thermal efficiency than those of current light water reactors. The once-through direct cycle system is employed in current fossil-fired power plants. In the present study, three types of core were designed. The first is SCFR-H with blankets cooled by ascending flow, the second is SCFR-H with blankets cooled by descending flow and the third is SCFR-H with high thermal power. Every core was designed to achieve the thermal efficiency over 43%, positive coolant density reactivity coefficient and electric power over 1600 MW. Core characteristics of SCFR-Hs were compared with those of SCLWR-H (electric power: 1212 MW), which is a thermal neutron spectrum reactor cooled and moderated by supercritical light water, with the same diameter of the reactor pressure vessel. It was shown that SCFR-H could increase the electric power about 1.7 times maximally. From the standpoint of the increase of a reactor thermal power, a fast reactor has advantages as compared with a thermal neutron reactor, because it can increase the power density by adopting tight fuel lattices and eliminating the moderator region. Thus, it was concluded that a reactor cooled by supercritical light water could further improve the cost competitiveness by using a fast neutron spectrum and achieving a higher thermal power. (author)

  9. Safety evaluation report: related to the operation of Perry Nuclear Power Plant, Units 1 and 2, Docket Nos. 50-440 and 50-441, Cleveland Electric Illuminating Company

    International Nuclear Information System (INIS)

    1982-08-01

    Supplement No. 1 to the Safety Evaluation Report on the application filed by the Cleveland Electric Illuminating Company on behalf of itself and as agent for the Duquesne Light Company, the Ohio Edison Company, the Pennsylvania Power Company, and the Toledo Edison Company (the Central Area Power Coordination Group, CAPCO), as applicants and owners, for a license to operate the Perry Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-440 and 441). The facility is located near Lake Erie in Lake County, Ohio. This supplement has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission and reports the status of certain items that had not been resolved at the time of publication of the Safety Evaluation Report

  10. Multi-reactor power system configurations for multimegawatt nuclear electric propulsion

    Science.gov (United States)

    George, Jeffrey A.

    1991-01-01

    A modular, multi-reactor power system and vehicle configuration for piloted nuclear electric propulsion (NEP) missions to Mars is presented. Such a design could provide enhanced system and mission reliability, allowing a comfortable safety margin for early manned flights, and would allow a range of piloted and cargo missions to be performed with a single power system design. Early use of common power modules for cargo missions would also provide progressive flight experience and validation of standardized systems for use in later piloted applications. System and mission analysis are presented to compare single and multi-reactor configurations for piloted Mars missions. A conceptual design for the Hydra modular multi-reactor NEP vehicle is presented.

  11. The adaptation of the electric power companies to the power market

    International Nuclear Information System (INIS)

    Otterstad, B.; Ottosen, R.

    1993-02-01

    This report describes the challenges met by the Norwegian electric power companies in adapting to a more market oriented business and their possibilities and strategies when facing the uncertainties on the market side. The main principles of adaptation to the market are described and various strategies are illustrated by means of simple calculations and figures. The theoretical basis for analyses of adaptation to the market and for pricing period contracts and options are discussed. The report concludes with a discussion of the de-regulation of the North American gas market and draws parallels to the Norwegian power market. 17 figs

  12. Design of investment management optimization system for power grid companies under new electricity reform

    Science.gov (United States)

    Yang, Chunhui; Su, Zhixiong; Wang, Xin; Liu, Yang; Qi, Yongwei

    2017-03-01

    The new normalization of the economic situation and the implementation of a new round of electric power system reform put forward higher requirements to the daily operation of power grid companies. As an important day-to-day operation of power grid companies, investment management is directly related to the promotion of the company's operating efficiency and management level. In this context, the establishment of power grid company investment management optimization system will help to improve the level of investment management and control the company, which is of great significance for power gird companies to adapt to market environment changing as soon as possible and meet the policy environment requirements. Therefore, the purpose of this paper is to construct the investment management optimization system of power grid companies, which includes investment management system, investment process control system, investment structure optimization system, and investment project evaluation system and investment management information platform support system.

  13. The effect of electric transmission constraints on how power generation companies bid in the Colombian electrical power market

    Directory of Open Access Journals (Sweden)

    Luis Eduardo Gallego Vega

    2010-05-01

    Full Text Available This paper presents the results of research about the effect of transmission constraints on both expected electrical energy to be dispatched and power generation companies’ bidding strategies in the Colombian electrical power market. The proposed model simulates the national transmission grid and economic dispatch by means of optimal power flows. The proposed methodology allows structural problems in the power market to be analyzed due to the exclusive effect of trans- mission constraints and the mixed effect of bidding strategies and transmission networks. A new set of variables is proposed for quantifying the impact of each generation company on system operating costs and the change in expected dispatched energy. A correlation analysis of these new variables is presented, revealing some interesting linearities in some generation companies’ bidding patterns.

  14. Nuclear reactor power for an electrically powered orbital transfer vehicle

    Science.gov (United States)

    Jaffe, L.; Beatty, R.; Bhandari, P.; Chow, E.; Deininger, W.; Ewell, R.; Fujita, T.; Grossman, M.; Kia, T.; Nesmith, B.

    1987-01-01

    To help determine the systems requirements for a 300-kWe space nuclear reactor power system, a mission and spacecraft have been examined which utilize electric propulsion and this nuclear reactor power for multiple transfers of cargo between low earth orbit (LEO) and geosynchronous earth orbit (GEO). A propulsion system employing ion thrusters and xenon propellant was selected. Propellant and thrusters are replaced after each sortie to GEO. The mass of the Orbital Transfer Vehicle (OTV), empty and dry, is 11,000 kg; nominal propellant load is 5000 kg. The OTV operates between a circular orbit at 925 km altitude, 28.5 deg inclination, and GEO. Cargo is brought to the OTV by Shuttle and an Orbital Maneuvering Vehicle (OMV); the OTV then takes it to GEO. The OTV can also bring cargo back from GEO, for transfer by OMV to the Shuttle. OTV propellant is resupplied and the ion thrusters are replaced by the OMV before each trip to GEO. At the end of mission life, the OTV's electric propulsion is used to place it in a heliocentric orbit so that the reactor will not return to earth. The nominal cargo capability to GEO is 6000 kg with a transit time of 120 days; 1350 kg can be transferred in 90 days, and 14,300 kg in 240 days. These capabilities can be considerably increased by using separate Shuttle launches to bring up propellant and cargo, or by changing to mercury propellant.

  15. Nuclear reactor power for an electrically powered orbital transfer vehicle

    International Nuclear Information System (INIS)

    Jaffe, L.; Beatty, R.; Bhandari, P.

    1987-01-01

    To help determine the systems requirements for a 300-kWe space nuclear reactor power system, a mission and spacecraft have been examined which utilize electric propulsion and this nuclear reactor power for multiple transfers of cargo between low Earth orbit (LEO) and geosynchronous Earth orbit (GEO). A propulsion system employing ion thrusters and xenon propellant was selected. Propellant and thrusters are replaced after each sortie to GEO. The mass of the Orbital Transfer Vehicle (OTV), empty and dry, is 11,000 kg; nominal propellant load is 5000 kg. The OTV operates between a circular orbit at 925 km altitude, 28.5 deg inclination, and GEO. Cargo is brought to the OTV by Shuttle and an Orbital Maneuvering Vehicle (OMV); the OTV then takes it to GEO. The OTV can also bring cargo back from GEO, for transfer by OMV to the Shuttle. OTV propellant is resupplied and the ion thrusters are replaced by the OMV before each trip to GEO. At the end of mission life, the OTV's electric propulsion is used to place it in a heliocentric orbit so that the reactor will not return to Earth. The nominal cargo capability to GEO is 6000 kg with a transit time of 120 days; 1350 kg can be transferred in 90 days, and 14,300 kg in 240 days. These capabilities can be considerably increased by using separate Shuttle launches to bring up propellant and cargo, or by changing to mercury propellant

  16. The Canadian Niagara Power Company story

    International Nuclear Information System (INIS)

    Ball, N.R.

    2005-01-01

    This book chronicles the history and contributions of the Canadian Niagara Power Company and its employees toward the establishment of electricity generation and distribution in Niagara Falls and Fort Erie, Ontario, dating back to its founding in 1892. Through historical photographs, maps and drawings, the book demonstrates the impact of electricity on the Niagara region. It emphasizes the many skills and jobs required to run the company that generated electricity and maintained a complete system to deliver power, metering, and billing services through the depression, wars, and postwar booms, even during lightning, snow and ice storms. The company began producing power in 1905 with what had been the world's largest-capacity turbines and generators that supplied power to both sides of the Niagara River. Initially, most of the electricity was exported to New York State. The company eventually expanded its Canadian customer service area from Niagara Falls, Ontario, to Fort Erie, Bridgeburg, Amigari, Ridgeway, Stevensville, Crystal Beach and Point Abino. Throughout its history, the Canadian Niagara Power Company provided power at a lower cost than its neighbouring competitors. The William Birch Rankine Generating Station became an important tourist attraction, showcasing the latest electrical appliances of the time in an effort to promote the use of electricity in homes and offices. Today, the station remains a tribute to the fact that natural beauty can coincide with industry. The book also chronicles the difficult business challenges caused by restructuring in the electric power industry in the 1990s, repairing aging equipment and applying the latest in automation and remote sensing technology. Today, the company as FortisOntario is expanding to other communities around Ontario. refs., tabs., figs

  17. Generation of net electric power with a tokamak reactor under foreseeable physical and engineering conditions

    International Nuclear Information System (INIS)

    Hiwatari, R.; Asaoka, Y.; Okano, K.; Yoshida, T.; Tomabechi, K.

    2004-01-01

    This study reveals for the first time the plasma performance required for a tokamak reactor to generate net electric power under foreseeable engineering conditions. It was found that the reference plasma performance of the ITER inductive operation mode with β N = 1.8, HH = 1.0, andf nGW 0.85 had sufficient potential to achieve the electric break-even condition (net electric power P e net = 0MW) under the following engineering conditions: machine major radius 6.5m ≤ R p ≤ 8.5m, the maximum magnetic field on TF coils B tmax = 16 T, thermal efficiency η e 30%, and NBI system efficiency η NBI = 50%. The key parameters used in demonstrating net electric power generation in tokamak reactors are β N and fη GW . ≥ 3.0 is required for P e net ∼ 600MW with fusion power P f ∼ 3000MW. On the other hand, fη GW ≥ 1.0 is inevitable to demonstrate net electric power generation, if high temperatures, such as average temperatures of T ave > 16 keV, cannot be selected for the reactor design. To apply these results to the design of a tokamak reactor for demonstrating net electric power generation, the plasma performance diagrams on the Q vs P f (energy multiplication factor vs fusion power) space for several major radii (i.e. 6.5, 7.5, and 8.5 m) were depicted. From these figures, we see that a design with a major radius R p ∼ 7.5m seems preferable for demonstrating net electric power generation when one aims at early realization of fusion energy. (author)

  18. Sale of electric energy: the case of Electric Power Company of Santa Catarina State (CELESC)

    International Nuclear Information System (INIS)

    Aurich, D.S.

    1990-01-01

    An electric power system assuring the electric supply to the investor client was developed by CELESC, linking the sale resources to one generation construction. It was related the cost of enlargement work from Pery plant, with the participation of Manville Forest Products in the investments. The economic aspects of this contract are presented, including the supply assure, the costs and the advantage each company will receive. (C.G.C.)

  19. Effort to grapple with improvement of security and reliability of nuclear power plant. Actions of the Japan Atomic Power Company

    International Nuclear Information System (INIS)

    Ishiguma, Kazuo

    2012-01-01

    Following the Great Tohoku Earthquake in 2011, Tokai No.2 reactor was shut down automatically. Three of emergency diesel generators worked automatically at loss-of-offsite-power and began to work the cooling system of reactor. The reactor could be kept stable and safe in cold state by management of power from the gas turbine electric generator and power source car. Actions of Japan Atomic Power Company (JAPC) for cold shutdown and Tsunami were stated. Inspection results after the earthquake and testimony of staff was described. Countermeasure of improvement of safety of nuclear power station is explained by ensuring of power source and water supply, crisis management system, countermeasure of accident, ensuring, and training of workers, and action for better understanding of reliance. (S.Y.)

  20. Data on loss of off-site electric power simulation tests of the high temperature engineering test reactor

    International Nuclear Information System (INIS)

    Takeda, Takeshi; Nakagawa, Shigeaki; Fujimoto, Nozomu; Tachibana, Yukio; Iyoku, Tatsuo

    2002-07-01

    The high temperature engineering test reactor (HTTR), the first high temperature gas-cooled reactor (HTGR) in Japan, achieved the first full power of 30 MW on December 7 in 2001. In the rise-to-power test of the HTTR, simulation tests on loss of off-site electric power from 15 and 30 MW operations were carried out by manual shutdown of off-site electric power. Because helium circulators and water pumps coasted down immediately after the loss of off-site electric power, flow rates of helium and water decreased to the scram points. To shut down the reactor safely, the subcriticality should be kept by the insertion of control rods and the auxiliary cooling system should cool the core continuously avoiding excessive cold shock to core graphite components. About 50 s later from the loss of off-site electric power, the auxiliary cooling system started up by supplying electricity from emergency power feeders. Temperature of hot plenum block among core graphite structures decreased continuously after the startup of the auxiliary cooling system. This report describes sequences of dynamic components and transient behaviors of the reactor and its cooling system during the simulation tests from 15 and 30 MW operations. (author)

  1. Electric utility companies and geothermal power

    Science.gov (United States)

    Pivirotto, D. S.

    1976-01-01

    The requirements of the electric utility industry as the primary potential market for geothermal energy are analyzed, based on a series of structured interviews with utility companies and financial institution executives. The interviews were designed to determine what information and technologies would be required before utilities would make investment decisions in favor of geothermal energy, the time frame in which the information and technologies would have to be available, and the influence of the governmental politics. The paper describes the geothermal resources, electric utility industry, its structure, the forces influencing utility companies, and their relationship to geothermal energy. A strategy for federal stimulation of utility investment in geothermal energy is suggested. Possibilities are discussed for stimulating utility investment through financial incentives, amelioration of institutional barriers, and technological improvements.

  2. Clean coal technology project to Polk Power Station, Tampa Electric Company, Florida, Volume 1: Report

    International Nuclear Information System (INIS)

    1994-06-01

    Tampa Electric Company proposes to construct and operate a 1,150-MW power station in southwestern Polk County, Florida. The proposed Polk Power Station would require an EPA NPDES permit for a new source and would include a 260-MW IGCC unit as a DOE Clean Coal Technology demonstration project. This EIS document assesses the proposed project and alternatives with respect to environmental impacts. Mitigative measures are also evaluated for the preferred alternative. Included in this Volume I are the following: alternatives including Tampa Electric Companies proposed project (preferred alternative with DOE financial assistance); affected environment; environmental consequences of the alternatives

  3. Power conditioning system for a nuclear reactor

    International Nuclear Information System (INIS)

    Higashigawa, Yuichi; Joge, Toshio.

    1981-01-01

    Purpose: To provide a power conditioning system for a BWR type reactor which has a function to be automatically operated within a range that the relationship between the heat power of the reactor and the electric power of an electric generator does not lose the safety of fuel by eliminating the unnecessary fluctuation of the power of the reactor. Constitution: A load request error signal fed from a conventional turbine control system to recirculation flow regulator is eliminated, and a reactor power conditioning system is newly provided, to which an electric generator power signal, a reactor average power area monitor signal and a load request signal are inputted. Thus, the load request signal is compared directly with the electric power of the electric generator, the recirculation flow rate is controlled by the compared result, and whether the correlation between the heat power of the reqctor and the electric power of the generator satisfies the correlation determined to prove the safety of fuel or not is checked. If this correlation is satisfied, the recirculation flow rate is merely automatically controlled. (Yoshino, Y.)

  4. Forecasted electric power demands for the Baltimore Gas and Electric Company. Volume 1 and Volume 2. Documentation manual

    International Nuclear Information System (INIS)

    Estomin, S.L.; Beach, J.E.; Goldsmith, J.V.

    1991-05-01

    The two-volume report presents the results of an econometric forecast of peak load and electric power demand for the Baltimore Gas and Electric Company (BG ampersand E) through the year 2009. Separate energy sales models were estimated for residential sales in Baltimore City, residential sales in the BG ampersand E service area excluding Baltimore City, commercial sales, industrial sales, streetlighting sales, and Company use plus losses. Econometric equations were also estimated for electric space heating and air conditioning saturation in Baltimore City and in the remainder of the BG ampersand E service territory. In addition to the energy sales models and the electric space conditioning saturation models, econometric models of summer and winter peak demand on the BG ampersand E system were estimated

  5. 76 FR 66333 - Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental...

    Science.gov (United States)

    2011-10-26

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2011-0247] Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant... Facility Operating License No. DPR-23, issued to Carolina Power & Light Company (the licensee), for...

  6. Power reactors in Member States. 1978 edition

    International Nuclear Information System (INIS)

    1978-01-01

    The computer-based reactor listing gives information on reactor core characteristics and plant systems for all power reactors in operation under construction and planned. The following two tables are included to give a general picture of the overall situation: Reactor types and net electrical power; Reactor units and net electrical power by country and cumulated by year

  7. Power unit with GT-MHR reactor plant for electricity production and district heating

    International Nuclear Information System (INIS)

    Kiryushin, A.L.; Kodochigov, N.G.; Kuzavkov, N.G.; Golovko, V.F.

    2000-01-01

    Modular helium reactor with the gas turbine (GT-MHR) is a perspective power reactor plant for the next century. The project reactor is based on experience of operation more than 50 gas-cooled reactors on carbon dioxide and helium, and also on subsequent achievements in the field of realization direct gas turbine Brayton cycle. To the beginning of 90 years, achievements in technology of gas turbines, highly effective recuperators and magnetic bearings made it possible to start development of the reactor plant project combining a safe modular gas cooled reactor and a power conversion system, realizing the highly effective Brayton cycle. The conceptual project of the commercial GT-MHR reactor plant fulfilled in 1997 by joint efforts of international firms, combines a safe modular reactor with an annular active core of prismatic fuel blocks and a power conversion system with direct gas turbine cycle. The efficiency of GT-MHR gas turbine cycle at level of about 48% makes it competitive in the electricity production market in comparison with any fossil or nuclear power stations

  8. 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.)

  9. High-Temperature Reactor For Power Generation and District Heating

    International Nuclear Information System (INIS)

    Herzberger, Karlheinz

    1987-01-01

    The multinational BBC Brown Brave Group, which has its head-quarters in Baden/Switzerland, was founded in 1891. Its German company is Brown, Brave and CIEs AGM, Mannheim. The field of operation covers wide areas of electrical engineering: These includes mainly the manufacture of installations and equipment for the generation, conversion, distribution and utilization of electric power, with special emphasis on the capital goods sector. BBC erects turnkey power plants and manufactures electrical equipment for industrial plants and urban transport and main line trains. Also of major importance are standard electrical products such as motors, switches, cables, semiconductor devices as well as measuring and control equipment. In the field of nuclear power BBC is engaged in particular in the development and construction of high-temperature reactors for the generation of electric power and process heat. The following presentation gives a short view on the milestones of the HTR development achieved in 1987

  10. Financing the electric power utilities, especially the nuclear power in Japan

    International Nuclear Information System (INIS)

    Tajima, T.

    1975-04-01

    Electric power demands in Japan have shown a remarkable growth at an annual rate of 12% since 1965. Nine electric power companies have invested large amounts of money so far, amounting to over 1 trillion yen every year since 1972. A survey of the electric power supply system and an estimation of the electric power demands in 1980 and in 1985 are given. It is expected that the main portion of electric power in the future will gradually be generated by nuclear plants. Financial features of the electrical power utilities, the credit risk of the electric power utilities, and the raising of funds by electric power utilities are discussed. It is concluded that it will be necessary (1) to expand the capital market, (2) to enable the electric power companies to issue a sufficient amount of bonds, (3) to make the Government financing institutions, such as the Japan Development Bank, provide the electric power companies with larger funds on a long-term and low-interest rate basis, and (4) even to take such drastic steps as subsidizing interest on private loans to the electric power companies. (B.P.)

  11. Very High Efficiency Reactor (VHER) Concepts for Electrical Power Generation and Hydrogen Production

    International Nuclear Information System (INIS)

    PARMA JR, EDWARD J.; PICKARD, PAUL S.; SUO-ANTTILA, AHTI JORMA

    2003-01-01

    The goal of the Very High Efficiency Reactor study was to develop and analyze concepts for the next generation of nuclear power reactors. The next generation power reactor should be cost effective compared to current power generation plant, passively safe, and proliferation-resistant. High-temperature reactor systems allow higher electrical generating efficiencies and high-temperature process heat applications, such as thermo-chemical hydrogen production. The study focused on three concepts; one using molten salt coolant with a prismatic fuel-element geometry, the other two using high-pressure helium coolant with a prismatic fuel-element geometry and a fuel-pebble element design. Peak operating temperatures, passive-safety, decay heat removal, criticality, burnup, reactivity coefficients, and material issues were analyzed to determine the technical feasibility of each concept

  12. 76 FR 77022 - In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2...

    Science.gov (United States)

    2011-12-09

    ... and 72-3] In the Matter of Carolina Power & Light Company, H.B. Robinson Steam Electric Plant, Unit No. 2, H. B. Robinson Steam Electric Plant, Unit 2, Independent Spent Fuel Storage Installation; Order Approving Indirect Transfer of Control of Licenses I. Carolina Power & Light Company (CP&L, the licensee) is...

  13. The development of multimedia communication system for electric power company

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1995-12-31

    It is a final report of the research project that is a development of PC-LAN based multimedia desktop conference system, which is research on the essential technologies and application and development of multimedia communication services for electric power company. This report is consisted of -Survey and study of the multimedia related technologies, -Multimedia communication protocols and network configurations, and -Design, developments of pilot model, evaluation, and applications of multimedia conference system. (author). 112 refs., 250 figs.

  14. The development of multimedia communication system for electric power company

    Energy Technology Data Exchange (ETDEWEB)

    Woo, Hee Gon; Kim, Seong Bok [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

    1996-12-31

    It is a final report of the research project that is a development of PC-LAN based multimedia desktop conference system, which is research on the essential technologies and application and development of multimedia communication services for electric power company. This report is consisted of -Survey and study of the multimedia related technologies, -Multimedia communication protocols and network configurations, and -Design, developments of pilot model, evaluation, and applications of multimedia conference system. (author). 112 refs., 250 figs.

  15. 75 FR 82414 - Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

    Science.gov (United States)

    2010-12-30

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company; H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... authorizes operation of the H.B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among...

  16. 75 FR 11579 - Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption

    Science.gov (United States)

    2010-03-11

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-261; NRC-2010-0062] Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2; Exemption 1.0 Background Carolina Power & Light... of the H. B. Robinson Steam Electric Plant, Unit 2 (HBRSEP). The license provides, among other things...

  17. Modular Lead-Bismuth Fast Reactors in Nuclear Power

    Directory of Open Access Journals (Sweden)

    Vladimir Petrochenko

    2012-09-01

    Full Text Available On the basis of the unique experience of operating reactors with heavy liquid metal coolant–eutectic lead-bismuth alloy in nuclear submarines, the concept of modular small fast reactors SVBR-100 for civilian nuclear power has been developed and validated. The features of this innovative technology are as follows: a monoblock (integral design of the reactor with fast neutron spectrum, which can operate using different types of fuel in various fuel cycles including MOX fuel in a self-providing mode. The reactor is distinct in that it has a high level of self-protection and passive safety, it is factory manufactured and the assembled reactor can be transported by railway. Multipurpose application of the reactor is presumed, primarily, it can be used for regional power to produce electricity, heat and for water desalination. The Project is being realized within the framework of state-private partnership with joint venture OJSC “AKME-Engineering” established on a parity basis by the State Atomic Energy Corporation “Rosatom” and the Limited Liability Company “EuroSibEnergo”.

  18. Chapter 3. The economical power of the company

    International Nuclear Information System (INIS)

    1998-01-01

    In the third chapter of this CD ROM the economic power of the Slovak Electric, Plc. (Slovenske elektrarne, a.s.), is presented. It consist of next paragraphs (1) Property of Slovak Electric, Plc, the company; (2) Position of the Company; (3) Business performance of the Company (Economic results, Installed capacity, Generation of electricity and heat; Electricity trade, Distribution of electricity and heat trade are reviewed); (4) Shareholdings in other companies and international co-operation

  19. Analytical evaluation on loss of off-side electric power simulation of the High Temperature Engineering Test Reactor

    International Nuclear Information System (INIS)

    Takeda, Takeshi; Nakagawa, Shigeaki; Tachibana, Yukio; Takada, Eiji; Kunitomi, Kazuhiko

    2000-03-01

    A rise-to-power test of the high temperature engineering test reactor (HTTR) started on September 28 in 1999 for establishing and upgrading the technological basis for the high temperature gas-cooled reactor (HTGR). A loss of off-site electric power test of the HTTR from the normal operation under 15 and 30 MW thermal power will be carried out in the rise-to-power test. Analytical evaluations on transient behaviors of the reactor and plant during the loss of off-site electric power were conducted. These estimations are proposed as benchmark problems for the IAEA coordinated research program on 'Evaluation of HTGR Performance'. This report describes an event scenario of transient during the loss of off-site electric power, the outline of major components and system, detailed thermal and nuclear data set for these problems and pre-estimation results of the benchmark problems by an analytical code 'ACCORD' for incore and plant dynamics of the HTGR. (author)

  20. Electrical system regulations of the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Mello, Jose Roberto de; Madi Filho, Tufic

    2013-01-01

    The IEA-R1 reactor of the Nuclear and Energy Research Institute (IPEN-CNEN/SP), is a research reactor open pool type, designed and built by the U.S. firm Babcock and Wilcox, having, as coolant and moderator, deionized light water and beryllium and graphite, as reflectors. Until about 1988, the reactor safety systems received power from only one source of energy. As an example, it may be cited the control desk that was powered only by the vital electrical system 220V, which, in case the electricity fails, is powered by the generator group: no-break 220V. In the years 1989 and 1990, a reform of the electrical system upgrading to increase the reactor power and, also, to meet the technical standards of the ABNT (Associacao Brasileira de Normas Tecnicas) was carried out. This work has the objective of showing the relationship between the electric power system and the IEA-R1 reactor security. Also, it demonstrates that, should some electrical power interruption occur, during the reactor operation, this occurrence would not start an accident event. (author)

  1. Utilization of nuclear energy for generating electric power in the FRG, with special regard to LWR-type reactors

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    Comments on interdependencies in energy industry and energy generation as seen by energy supply utilities, stating that the generation of electric power in Germany can only be based on coal and nuclear energy in the long run, are followed by the most important, fundamental, nuclear-physical, technological and in part political interdependencies prevailing in the starting situation of 1955/58 when the construction of nuclear power plant reactors began. Then the development ranging to the 28000 MW nuclear power output to be expected in 1985 is outlined, totalling in 115000 MW electric power in the FRG. Finally, using the respectively latest order, the technical set up of each of the reactor types with 1300 MWe unit power offered by German manufacturers are described: BBC/BBR PWR-type reactor Neupotz, KWU-PWR-type reactor Hamm and KWU PWR-type reactor double unit B+C Gundremmingen. (orig.) [de

  2. Research on service strategy of electricity selling company under the reform of electricity market

    Science.gov (United States)

    Long, Zhuhan; Meng, Shiyu; Dou, Jinyue; Zeng, Ming; Sun, Chenjun

    2017-10-01

    The opening of the sale side of electricity market is an important goal of the new round of power system reform in China, and it is necessary to speed up the establishment and development of the electricity selling companies to achieve this goal. First of all, this paper defines the key problems, which are needed to be solved in the establishment of the sale side market, such as demand side response, optimization of users' power consumption mode, profit mode of electricity selling companies and fair competition in the market. On this basis, this paper analyzes the business of electricity selling company, from the aspects of the transition of business ideas, improving the energy efficiency level, providing integrated energy solutions and innovating business management mode; and then, the service strategies of electricity selling companies are put forward.

  3. Taiwan Power Company's power distribution analysis and fuel thermal margin verification methods for pressurized water reactors

    International Nuclear Information System (INIS)

    Huang, P.H.

    1995-01-01

    Taiwan Power Company's (TPC's) power distribution analysis and fuel thermal margin verification methods for pressurized water reactors (PWRs) are examined. The TPC and the Institute of Nuclear Energy Research started a joint 5-yr project in 1989 to establish independent capabilities to perform reload design and transient analysis utilizing state-of-the-art computer programs. As part of the effort, these methods were developed to allow TPC to independently perform verifications of the local power density and departure from nucleate boiling design bases, which are required by the reload safety evaluation for the Maanshan PWR plant. The computer codes utilized were extensively validated for the intended applications. Sample calculations were performed for up to six reload cycles of the Maanshan plant, and the results were found to be quite consistent with the vendor's calculational results

  4. Potential of Electric Power Production from Microbial Fuel Cell (MFC) in Evapotranspiration Reactor for Leachate Treatment Using Alocasia macrorrhiza Plant and Eleusine indica Grass

    Science.gov (United States)

    Zaman, Badrus; Wardhana, Irawan Wisnu

    2018-02-01

    Microbial fuel cell is one of attractive electric power generator from nature bacterial activity. While, Evapotranspiration is one of the waste water treatment system which developed to eliminate biological weakness that utilize the natural evaporation process and bacterial activity on plant roots and plant media. This study aims to determine the potential of electrical energy from leachate treatment using evapotranspiration reactor. The study was conducted using local plant, namely Alocasia macrorrhiza and local grass, namely Eleusine Indica. The system was using horizontal MFC by placing the cathodes and anodes at different chamber (i.e. in the leachate reactor and reactor with plant media). Carbon plates was used for chatode-anodes material with size of 40 cm x 10 cm x1 cm. Electrical power production was measure by a digital multimeter for 30 days reactor operation. The result shows electric power production was fluctuated during reactor operation from all reactors. The electric power generated from each reactor was fluctuated, but from the reactor using Alocasia macrorrhiza plant reach to 70 μwatt average. From the reactor using Eleusine Indica grass was reached 60 μwatt average. Electric power production fluctuation is related to the bacterial growth pattern in the soil media and on the plant roots which undergo the adaptation process until the middle of the operational period and then in stable growth condition until the end of the reactor operation. The results indicate that the evapotranspiration reactor using Alocasia macrorrhiza plant was 60-95% higher electric power potential than using Eleusine Indica grass in short-term (30-day) operation. Although, MFC system in evapotranspiration reactor system was one of potential system for renewable electric power generation.

  5. Oxygen transport membrane reactor based method and system for generating electric power

    Science.gov (United States)

    Kelly, Sean M.; Chakravarti, Shrikar; Li, Juan

    2017-02-07

    A carbon capture enabled system and method for generating electric power and/or fuel from methane containing sources using oxygen transport membranes by first converting the methane containing feed gas into a high pressure synthesis gas. Then, in one configuration the synthesis gas is combusted in oxy-combustion mode in oxygen transport membranes based boiler reactor operating at a pressure at least twice that of ambient pressure and the heat generated heats steam in thermally coupled steam generation tubes within the boiler reactor; the steam is expanded in steam turbine to generate power; and the carbon dioxide rich effluent leaving the boiler reactor is processed to isolate carbon. In another configuration the synthesis gas is further treated in a gas conditioning system configured for carbon capture in a pre-combustion mode using water gas shift reactors and acid gas removal units to produce hydrogen or hydrogen-rich fuel gas that fuels an integrated gas turbine and steam turbine system to generate power. The disclosed method and system can also be adapted to integrate with coal gasification systems to produce power from both coal and methane containing sources with greater than 90% carbon isolation.

  6. Power reactors in Member States. 1979 edition

    International Nuclear Information System (INIS)

    1979-01-01

    This is the fifth issue of a periodic computer-based listing of nuclear power reactors, presenting the situation as of 1 May 1979. The basic design data for all reactors in operation, under construction, planned and shut down have been included. The following two tables are included to give a general picture of the overall situation: Table I: Reactor types and net electrical power. Table II: Reactor units and net electrical powered by country cummulated by year

  7. TU electric reactor model verification

    International Nuclear Information System (INIS)

    Willingham, C.E.; Killgore, M.R.

    1989-01-01

    Power reactor benchmark calculations using the code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles include gadolinia as a burnable absorber, natural uranium axial blankets, and increased water-to-fuel ratio. The calculated results for both low-power physics tests (boron end points, control rod worths, and isothermal temperature coefficients) and full-power operation (power distributions and boron letdown) are compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important physics parameters for power reactors

  8. Potential of Electric Power Production from Microbial Fuel Cell (MFC in Evapotranspiration Reactor for Leachate Treatment Using Alocasia macrorrhiza Plant and Eleusine indica Grass

    Directory of Open Access Journals (Sweden)

    Zaman Badrus

    2018-01-01

    Full Text Available Microbial fuel cell is one of attractive electric power generator from nature bacterial activity. While, Evapotranspiration is one of the waste water treatment system which developed to eliminate biological weakness that utilize the natural evaporation process and bacterial activity on plant roots and plant media. This study aims to determine the potential of electrical energy from leachate treatment using evapotranspiration reactor. The study was conducted using local plant, namely Alocasia macrorrhiza and local grass, namely Eleusine Indica. The system was using horizontal MFC by placing the cathodes and anodes at different chamber (i.e. in the leachate reactor and reactor with plant media. Carbon plates was used for chatode-anodes material with size of 40 cm x 10 cm x1 cm. Electrical power production was measure by a digital multimeter for 30 days reactor operation. The result shows electric power production was fluctuated during reactor operation from all reactors. The electric power generated from each reactor was fluctuated, but from the reactor using Alocasia macrorrhiza plant reach to 70 μwatt average. From the reactor using Eleusine Indica grass was reached 60 μwatt average. Electric power production fluctuation is related to the bacterial growth pattern in the soil media and on the plant roots which undergo the adaptation process until the middle of the operational period and then in stable growth condition until the end of the reactor operation. The results indicate that the evapotranspiration reactor using Alocasia macrorrhiza plant was 60-95% higher electric power potential than using Eleusine Indica grass in short-term (30-day operation. Although, MFC system in evapotranspiration reactor system was one of potential system for renewable electric power generation.

  9. Cost structure analysis of commercial nuclear power plants in Japan based on corporate financial statements of electric utility companies

    International Nuclear Information System (INIS)

    Kunitake, Norifumi; Nagano, Koji; Suzuki, Tatsujiro

    1998-01-01

    In this paper, we analyze past and current cost structure of commercial nuclear power plants in Japan based on annual corporate financial statements published by the Japanese electric utility companies, instead of employing the conventional methodology of evaluating the generation cost for a newly constructed model plant. The result of our study on existing commercial nuclear plants reveals the increasing significance of O and M and fuel cycle costs in total generation cost. Thus, it is suggested that electric power companies should take more efforts to reduce these costs in order to maintain the competitiveness of nuclear power in Japan. (author)

  10. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, S.; Campbell, C.A.

    1993-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 1800 deg F) and to simulate Regulatory Guide 1.99 database materials (austenitized at 1600 deg. F). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (U. of Michigan Test Reactor) which had never been used for this type of irradiation program. Materials taken from plate surface locations (vs. 1/4T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, is maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (500 deg. F and 550 deg. F) to determine the effect of irradiation temperature on embrittlement. The preliminary results of the irradiation program show an increase in T 30 shift of 69 deg. F for a decrease in irradiation temperature of 50 deg. F. The results suggest that for nickel bearing steels, the superior toughness of plate surface material is maintained after irradiation and for the copper content tested, nickel had no apparent effect on irradiation response. No apparent microstructure

  11. The comparative analysis of safety and economic competitiveness of the advanced high-power reactor projects of NPP

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Makhanov, U.M.; Philimonova, R.A.; Kichutkina, E.G.

    2002-01-01

    The comparative analysis results of the safety and economic competitiveness of the seven advanced large sized reactors projects (900 MW and more) are submitted in that report: EPR, Frameatome France, Siemens Germany; EP-1000 Westinghouse, USA and Genesi Italy; Candu 9, Atomic Energy of Canada Ltd; System 80 +, ABB, USA; KNGR, group NSSS Engineering and Development, Korea Power Engineering Company, Inc; APWR, Electric Power company, Japan Atomic Power Company, Mitsubishi Heavy Industries, Westinghouse Electric; and WWER-1000 (V-392), Atomenergoproject/Gidropress Russian Federation. According to the economic competitiveness of listed compared power reactors the 14 criteria of safety have been accepted. These criteria: 1. Features of the barrier system of 'defence-in-depth'. 2. The self-security of a reactor under increase of power and reactivity of a reactor, decrease of the expense and phase transformations of the reactor core coolant (presence of negative feedbacks). 3. Presence of the reactor shutdown systems responding principles of a variety, independence and reservation. Presence of the passive means of initiation and operation of the emergency protection. 4. The emergency cooling of the core of reactor. A presence of the passive means of cooling. Presence of the water reservation for the water supply of the different safety systems. 5. The emergency electrical supply, its reliability and degree of reservation. 6. The prevention measures of the heavy accident with the melt core. The decrease of the heavy accident probability. 7. The account of the heavy accident under development of the levels of protection. 8. The protection levels of NPP, the technological criteria of efficiency of the each safety barriers and the limiting radiation criteria for the each level of protection , in particular for the design-basis and beyond-design-basis accidents. 9. The measures for reduction of the heavy accident consequences. The management by the beyond

  12. Reactor/Brayton power systems for nuclear electric spacecraft

    Science.gov (United States)

    Layton, J. P.

    1980-01-01

    Studies are currently underway to assess the technological feasibility of a nuclear-reactor-powered spacecraft propelled by electric thrusters. This vehicle would be capable of performing detailed exploration of the outer planets of the solar system during the remainder of this century. The purpose of this study was to provide comparative information on a closed cycle gas turbine power conversion system. The results have shown that the performance is very competitive and that a 400 kWe space power system is dimensionally compatible with a single Space Shuttle launch. Performance parameters of system mass and radiator area were determined for systems from 100 to 1000 kWe. A 400 kWe reference system received primary attention. The components of this system were defined and a conceptual layout was developed with encouraging results. The preliminary mass determination for the complete power system was very close to the desired goal of 20 kg/kWe. Use of more advanced technology (higher turbine inlet temperature) will substantially improve system performance characteristics.

  13. Electricity Self-Generation Costs for Industrial Companies in Cameroon

    Directory of Open Access Journals (Sweden)

    Diboma Benjamin Salomon

    2010-07-01

    Full Text Available Industrial production in developing countries (DC is frequently perturbed by electric energy supply difficulties. To overcome this problem, generators are used in self-generation of energy, but this leads to an increase of electricity-related expenses. This article assesses the impact of electricity self-generation on Cameroonian industrial companies. The model described in this article is based on data collected through a survey of a representative sample of industrial companies and from numerous previous thematic and statistical studies. The results of our analyses show that expenses related to electricity in industrial companies in Cameroon have increased five times due to electricity rationing and untimely power cuts. The article also suggests some solutions to improve the electricity self-generation capacity of industrial companies.

  14. Memorial 1997 - ENDESA (Chilean Electricity Company)

    International Nuclear Information System (INIS)

    1998-01-01

    This report provides a comprehensive survey, in depth assessment of the activities overview of ENDESA, Chilean Electricity Company, highlighting economical information and including historical and technical aspects. Economics is its focal point, but other relevant data are shown, like technical data on hydroelectric and thermoelectric power plants. Main activities developed by ENDESA are described, such in Chile as in the foreign. Data on power generation, transmission and transport are also presented and an economical balance of each colligated company are done and analysed

  15. Environmental Disclosure of Electric Power Companies Listed in the Corporate Sustainability Index (CSI

    Directory of Open Access Journals (Sweden)

    Clésia Ana Gubiani

    2012-12-01

    Full Text Available The study aimed to verify the level of disclosure of environmental information in the administration reports of the energy companies listed in the Corporate Sustainability Index (CSI. A descriptive and quantitative research was done, using the content analysis technique on the administration reports from 2006 to 2008. The sample consisted of 11 electric power companies listed in the CSI. For quantitative analysis of the disclosure index, the data collection instrument was based on the study of Rover, Murcia and Borba (2008, which proposes eight environmental categories and 36 subcategories. For the whole analysis of the data were elaborated networks of the items disclosed in each company, using the software UNICET ®. The survey results showed that there is satisfactory disclosure in the categories of environmental policies and education, training and research environment. However, it was found that there is need for greater disclosure of categories of products impacts and processes in the environment, power polices and financial environmental information. It was concluded that the information disclosed in the administration reports of the companies surveyed about the environmental information do not respect the principle of full disclosure.

  16. Compact reactor/ORC power source

    International Nuclear Information System (INIS)

    Meier, K.L.; Kirchner, W.L.; Willcutt, G.J.

    1986-01-01

    A compact power source that combines an organic Rankine Cycle (ORC) electric generator with a nuclear reactor heat source is being designed and fabricated. Incorporating existing ORC technology with proven reactor technology, the compact reactor/ORC power source offers high reliability while minimizing the need for component development. Thermal power at 125 kWt is removed from the coated particle fueled, graphite moderated reactor by heat pipes operating at 500 0 C. Outside the reactor vessel and connected to the heat pipes are vaporizers in which the toluene ORC working fluid is heated to 370 0 C. In the turbine-alternator-pump (TAP) combined-rotating unit, the thermal energy of the toluene is converted to 25 kWe of electric power. Lumped parameter systems analyses combined with a finite element thermal analysis have aided in the power source design. The analyses have provided assurance of reliable multiyear normal operation as well as full power operation with upset conditions, such as failed heat pipes and inoperative ORC vaporizers. Because of inherent high reliability, long life, and insensitivity to upset conditions, this power source is especially suited for use in remote, inaccessible locations where fuel delivery and maintenance costs are high. 10 refs

  17. An inherently safe power reactor module

    International Nuclear Information System (INIS)

    Salerno, L.N.

    1985-01-01

    General Electric's long participation in liquid metal reactor technology has led to a Power Reactor Inherently Safe Module (PRISM) concept supported by DOE contract DE-AC06-85NE37937. The reactor module is sized to maximize inherent safety features. The small size allows factory fabrication, reducing field construction and field QA/QC labor, and allows safety to be demonstrated in full scale, to support a pre-licensed standard commercial product. The module is small enough to be placed underground, and can be combined with steam and electrical generating equipment to provide a complete electrical power producing plant in the range of 400-1200 MWe. Initial assessments are that the concept has the potential to be economically competitive with existing methods of power production used by the utility industry

  18. Systems for controlling the electric power of a boiling water reactor power station

    International Nuclear Information System (INIS)

    Fukunishi, Koyu; Kiyokawa, Kazuhiro.

    1975-01-01

    Object: To achieve automatic increase and decrease of electric output in accordance with a predetermined rate of increase or decrease in output when the power output is raised or lowered. Structure: An electric output signal from an atomic power plant is led to a differentiating circuit through a smoothing circuit to produce a signal for rate of change of time, and an error signal between this signal and a preset signal produced from a circuit for a preset rate of change of output with time is supplied to an analog adjuster through a limiter. In this way, the flow rate in the reactor core is adjusted by a speed controller to obtain an output of a predetermined rate of increase. The difference signal between the electric output signal and a desired value signal is passed through an absolute circuit to a comparator circuit for comparison with a predetermined threshold value setting signal. The output signal of the comparator is used to operate a relay to open the contact so as to prevent an increase or decrease in the output beyond the required level. (Kamimura, M.)

  19. power quality study of the electrical system of the second research reactor of egypt

    International Nuclear Information System (INIS)

    Fathi, H.M.E.

    2007-01-01

    identifying problems in an electrical network which may results in an extensive damage occur is advisable for any power system. monitoring of power quality is necessary for maintaining accurate operation of sensitive equipment, it also ensures that unnecessary for maintaining accurate operation of sensitive equipment, it also ensures that unnecessary energy losses in a power system are kept at a minimum which lead to more profits. with advanced in technology growing of industrial/commercial facilities in many region. power quality problems have been a major concern among engineers; particularly in an industrial environment, where there are many large-scale type of equipment.thus, it would be useful to monitor and analyze the power quality problems.determination of power quality requires the identification of any anomalous behavior on a power system, which adversely affects the normal operation of electrical or electronic equipment. the choice of monitoring equipment in a survey is also important to ascertain a solution to these power quality problems. a power quality survey involves gathering data resources; analyzing the data (with reference to power quality standard); then , if problems exist, recommendation of mitigation techniques. the main objective of the present work is to identify power quality problems in second research reactor of egypt (ETRR-2). electrical power is supplied to the installation via tow incoming feeders from tow different substations (incoming feeder from new Abo-Zabal substation and incoming feeder from old Abo-Zabal substation ) to keep good reliability , each feeder is designed to carry the full load of ETRR-2. the monitoring investigations were performed at the second research reactor of egypt for both feeders at different operation conditions

  20. Experimental fusion power reactor conceptual design study. Final report. Volume II

    International Nuclear Information System (INIS)

    Baker, C.C.

    1976-12-01

    This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following sections: (1) reactor components, (2) auxiliary systems, (3) operations, (4) facility design, (5) program considerations, and (6) conclusions and recommendations

  1. Revision of the second basic plans of power reactor development in Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1978-01-01

    Revision of the second basic plans concerning power reactor development in PNC (Power Reactor and Nuclear Fuel Development Corporation) is presented. (1) Fast breeder reactors: As for the experimental fast breeder reactor, after reaching the criticality, the power is raised to 50 MW thermal output within fiscal 1978. The prototype fast breeder reactor is intended for the electric output of 200 MW -- 300 MW, using mixed plutonium/uranium oxide fuel. Along the above lines, research and development will be carried out on reactor physics, sodium technology, machinery and parts, nuclear fuel, etc. (2) Advanced thermal reactor: The prototype advanced thermal reactor, with initial fuel primarily of slightly enriched uranium and heavy water moderation and boiling water cooling, of 165 MW electric output, is brought to its normal operation by the end of fiscal 1978. Along the above lines, research and development will be carried out on reactor physics, machinery and parts, nuclear fuel, etc. (Mori, K

  2. Measuring efficiency and productivity change in power electric generation management companies by using data envelopment analysis: A case study

    International Nuclear Information System (INIS)

    Fallahi, Alireza; Ebrahimi, Reza; Ghaderi, S.F.

    2011-01-01

    This paper provides an empirical analysis of the determinants of energy efficiency in 32 power electric generation management companies over the period 2005–2009. The study uses non-parametric Data Envelopment Analysis (DEA) to estimate the relative technical efficiency and productivity change of these companies. In order to verify the stability of our DEA model and the importance of each input variable, a stability test is also conducted. The results of the study indicate that average technical efficiency of companies decreased during the study period. Nearly half of the companies (14) are below this average level of 88.7% for five years. Moreover, it is shown that the low increase of productivity changes is more related to low efficiency rather than technology changes. -- Highlights: ► DEA was applied on the 32 power electric generation management companies. ► A stability test is applied to verify the stability of DEA model. ► Average technical efficiency of companies decreased during the study period. ► The low increase of productivity changes is more related to low efficiency changes.

  3. Tokamak hybrid thermonuclear reactor for the production of fissionable fuel and electric power

    International Nuclear Information System (INIS)

    Velikhov, E.P.; Glukhikh, V.A.; Gur'ev, V.V.

    1978-01-01

    The results of feasibility studies of a tokamak- based hybrid reactor concept are presented. The system selected has a D-T plasma volume of 575 m 3 with additional plasma heating by injection of fast neutral particles. The method of heating makes it possible to achieve an economical two-component tokamak regime at ntau=(4-6)x10 13 sxcm -3 , i e. far below the Lawson criterion. Plasma and vacuum chamber are surrounded by a blanket where fissionable plutonium is produced and heat transformed into electric power is generated. Major plasma-neutron-physical characteristics of the 6905 MWth (2500 MWe) reactor and its electromagnetic system are presented. Evaluations show that the hybrid reactor can produce about 800 kg of Pu per 1GWth/yr as compared to 70-150 kg of Pu for fast breeder reactors. The increased Pu production rate is the major merit of the concept promising for both power generation and fuelling thermal fission reactions

  4. Electric power: the liberalization effects

    International Nuclear Information System (INIS)

    Carpentier, J.

    1999-01-01

    Nine months after the beginning of the deregulation of electric power markets in Europe, the first effects are being felt: fall of prices, amalgamation of electric power companies, development of new technologies and unemployment. (O.M.)

  5. 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

  6. Reactor power system deployment and startup

    International Nuclear Information System (INIS)

    Wetch, J.R.; Nelin, C.J.; Britt, E.J.; Klein, G.; Rasor Associates, Inc., Sunnyvale, CA; California Institute of Technology, Pasadena)

    1985-01-01

    This paper addresses issues that should receive further examination in the near-term as concept selection for development of a U.S. space reactor power system is approached. The issues include: the economics, practicality and system reliability associated with transfer of nuclear spacecraft from low earth shuttle orbits to operational orbits, via chemical propulsion versus nuclear electric propulsion; possible astronaut supervised reactor and nuclear electric propulsion startup in low altitude Shuttle orbit; potential deployment methods for nuclear powered spacecraft from Shuttle; the general public safety of low altitude startup and nuclear safe and disposal orbits; the question of preferred reactor power level; and the question of frozen versus molten alkali metal coolant during launch and deployment. These issues must be considered now because they impact the SP-100 concept selection, power level selection, weight and size limits, use of deployable radiators, reliability requirements, and economics, as well as the degree of need for and the urgency of developing space reactor power systems. 5 references

  7. Power control system in BWR type reactors

    International Nuclear Information System (INIS)

    Nishizawa, Yasuo.

    1980-01-01

    Purpose: To control the reactor power so that the power distribution can satisfy the limiting conditions, by regulating the reactor core flow rate while monitoring the power distribution in the reactor core of a BWR type reactor. Constitution: A power distribution monitor determines the power distribution for the entire reactor core based on the data for neutron flux, reactor core thermal power, reactor core flow rate and control rod pattern from the reactor and calculates the linear power density distribution. A power up ratio computing device computes the current linear power density increase ratio. An aimed power up ratio is determined by converting the electrical power up ratio transferred from a load demand input device into the reactor core thermal power up ratio. The present reactor core thermal power up ratio is subtracted from the limiting power up ratio and the difference is sent to an operation amount indicator and the reactor core flow rate is changed in a reactor core flow rate regulator, by which the reactor power is controlled. (Moriyama, K.)

  8. Low power reactor for remote applications

    International Nuclear Information System (INIS)

    Meier, K.L.; Palmer, R.G.; Kirchner, W.L.

    1985-01-01

    A compact, low power reactor is being designed to provide electric power for remote, unattended applications. Because of the high fuel and maintenance costs for conventional power sources such as diesel generators, a reactor power supply appears especially attractive for remote and inaccessible locations. Operating at a thermal power level of 135 kWt, the power supply achieves a gross electrical output of 25 kWe from an organic Rankine cycle (ORC) engine. By intentional selection of design features stressing inherent safety, operation in an unattended mode is possible with minimal risk to the environment. Reliability is achieved through the use of components representing existing, proven technology. Low enrichment uranium particle fuel, in graphite core blocks, cooled by heat pipes coupled to an ORC converter insures long-term, virtually maintenance free, operation of this reactor for remote applications. 10 refs., 7 figs., 3 tabs

  9. Forecasted electric power demands for the Delmarva Power and Light Company. Volume 1 and Volume 2. Documentation manual

    International Nuclear Information System (INIS)

    Estomin, S.L.; Beach, J.E.

    1990-10-01

    The two-volume report presents the results of an econometric forecast of peak load and electric power demands for the Delmarva Power and Light Company (DP ampersand L) through the year 2008. Separate sets of models were estimated for the three jurisdictions served by DP ampersand L: Delaware, Maryland and Virginia. For both Delaware and Maryland, econometric equations were estimated for residential, commercial, industrial, and streetlighting sales. For Virginia, equations were estimated for residential, commercial plus industrial, and streetlighting sales; separate industrial and commercial equations were not estimated for Virginia due to the relatively small size of DP ampersand L's Virginia Industrial load. Wholesale sales were econometrically estimated for the DP ampersand L system as a whole. In addition to the energy sales models, an econometric model of annual (summer) peak demand was estimated for the Company

  10. A compact reactor/ORC power source

    International Nuclear Information System (INIS)

    Meier, K.L.; Kirchner, W.L.; Willcutt, G.J.

    1986-01-01

    A compact power source that combines an organic Rankine cycle (ORC) electric generator with a nuclear reactor heat source is being designed and fabricated. Incorporating existing ORC technology with proven reactor technology, the compact reactor/ORC power source offers high reliability while minimizing the need for componenet development. Thermal power at 125 kWt is removed from the coated particle fueled, graphite moderated reactor by heat pipes operating at 500 0 C. Outside the reactor vessel and connected to the heat pipes are vaporizers in which the toluene ORC working fluid is heated to 370 0 C. In the turbine-alternator-pump (TAP) combined-rotating unit, the thermal energy of the toluene is converted to 25 kWe of electric power. Lumped parameter systems analyses combined with a finite element thermal analyses combined with a finite element thermal analysis have aided in the power source design. The analysis have provided assurance of reliable multiyear normal operation as well as full power operation with upset conditions, such as failed heat pipes and inoperative ORC vaporizers. Because of inherent high reliability, long life, and insensitivity to upset conditions, this power source is especially suited for use in remote, inaccessible locations where fuel delivery and maintenance costs are high

  11. Result of 11th regular inspection of No.1 plant in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The 11th regular inspection of No.1 plant in Shimane Nuclear Power Station was carried out from January 9 to July 2, 1986. The parallel operation was resumed on June 19, 1986, 162 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, as the result, any abnormality was not found. The works related to this regular inspection were accomplished within the range of the allowable radiation dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were as follows. Feed water spargers were replaced with those of welded type, the material of the drain pipe for No.3 feed heater was changed to STPA 23, an exhaust compressor, an exhaust gas-water separator and others, which have not been used, were removed, and the connecting pipe for a liquid nitrogen evaporator was installed. (Kako, I.)

  12. An FAHP-TOPSIS framework for analysis of the employee productivity in the Serbian electrical power companies

    Directory of Open Access Journals (Sweden)

    Snezana Pavle Knezevic

    2017-09-01

    Full Text Available The aim of this paper is to apply an integrated model, which combines methods of classical and fuzzy Multi-criteria decision making (MCDM in selected six large equity companies from the Serbian energy sector. The data considered are retrieved from the official financial statements. Four main criteria were analyzed, identified by the previous researchers and pointing to the employees productivity: Operating income/Number of employees, Equity/Number of employees, Net income/Number of employees and Total assets/Number of employees. The contribution of this paper lies in the application of a hybrid model that integrates two MCDM methods: Fuzzy Analytic Hierarchy Process (FAHP and Technique for Order Performance by Similarity to Ideal Solution (TOPSIS to analyse the employee productivity in selected D-Electrical power supply companies operating in Serbia. The FAHP is an effective method for mathematical representation of uncertain and imprecise evaluations made by humans, while the TOPSIS method is an efficient way to rank the alternatives. Results show that operating income is of highest importance for estimating employee productivity and decision making, while equity is of the weakest. Furthermore, the most productive operations in large enterprises from selected companies of the sector D-Electrical power supply are found in the company PC EPS Beograd, and the lowest are in the ED Center llc Kragujevac.

  13. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  14. Nuclear energy products except the electric power

    International Nuclear Information System (INIS)

    2004-01-01

    Technically the fission reactors, on service or under construction, can produce other products than the electric power. Meanwhile, these applications are known since the beginning of the reactors exploitation, they never have been developed industrially. This report examines the necessary technical characteristics for using the nuclear systems on non electric power applications with an economical efficiency. What are the markets for these products? What are the strategical challenges to favor the development of non electric power applications of the nuclear energy? (A.L.B.)

  15. Advanced reactor development for non-electric applications

    International Nuclear Information System (INIS)

    Chang, M.H.; Kim, S.H.

    1996-01-01

    Advance in the nuclear reactor technology achieved through nuclear power programs carried out in the world has led nuclear communities to direct its attention to a better and peaceful utilization of nuclear energy in addition to that for power generation. The efforts for non-electric application of nuclear energy has been pursued in a limited number of countries in the world for their special needs. However, those needs and the associated efforts contributed largely to the development and practical realization of advanced reactors characterized by highly improved reactor safety and reliability by deploying the most up-to-date safety technologies. Due mainly to the special purpose of utilization, economic reasons and ease in implementation of new advanced technologies, small and medium reactors have become a major stream in the reactor developments for non-electric applications. The purpose of this paper is to provide, to the interested nuclear society, the overview of the development status and design characteristics of selected advanced nuclear reactors previously developed and/or currently under development specially for non-electric applications. Major design technologies employed in those reactors to enhance the reactor safety and reliability are reviewed to present the underlying principles of the design. Along with the overview, this paper also introduces a development program and major design characteristics of an advanced integral reactor (SMART) for co-generation purpose currently under conceptual development in Korea. (author)

  16. Alteration of installation of nuclear reactors (alteration of No. 1 and No. 2 reactor facilities) in Shimane Nuclear Power Station, Chugoku Electric Power Co. , Inc. (report)

    Energy Technology Data Exchange (ETDEWEB)

    1987-07-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry after prudent deliberation on this alteration problem which had been inquired on August 28, 1986. It was recognized that the technical capability of the applicant is appropriate, as the result of deliberation. It was judged that the safety after this alteration of the installation of the reactor facilities can be ensured. As the result of examining new type 8 x 8 zirconium liner fuel, there was no problem in its mechanical design, the analysis of dynamical characteristics, and the analysis of abnormal transient change and accident in operation. As to the change of the average degree of enrichment of replacement fuel, the thermonuclear design of the reactor core was adequate. In the incineration of spent resin and filter sludge, the effect of radioactive substances to the environment was negligible. The safety after abolishing the auxiliary protection function against exhaust radioactivity is ensured with a rare gas holdup equipment. The soundness of fuel and the soundness of reactor coolant pressure boundary are maintained in abnormal transient change and accident. (Kako, I.).

  17. Alteration of installation of nuclear reactors (alteration of No.1 and No.2 reactor facilities) in Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1987-01-01

    The Nuclear Safety Commission reported to the Minister of International Trade and Industry after prudent deliberation on this alteration problem which had been inquired on August 28, 1986. It was recognized that the technical capability of the applicant is appropriate, as the result of deliberation. It was judged that the safety after this alteration of the installation of the reactor facilities can be ensured. As the result of examining new type 8 x 8 zirconium liner fuel, there was no problem in its mechanical design, the analysis of dynamical characteristics, and the analysis of abnormal transient change and accident in operation. As to the change of the average degree of enrichment of replacement fuel, the thermonuclear design of the reactor core was adequate. In the incineration of spent resin and filter sludge, the effect of radioactive substances to the environment was negligible. The safety after abolishing the auxiliary protection function against exhaust radioactivity is ensured with a rare gas holdup equipment. The soundness of fuel and the soundness of reactor coolant pressure boundary are maintained in abnormal transient change and accident. (Kako, I.)

  18. 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

  19. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  20. The Optimization of power reactor control system

    International Nuclear Information System (INIS)

    Danupoyo, S.D.

    1997-01-01

    A power reactor is an important part in nuclear powered electrical plant systems. Success in controlling the power reactor will establish safety of the whole power plant systems. Until now, the power reactor has been controlled by a classical control system that was designed based on output feedback method. To meet the safety requirements that are now more restricted, the recently used power reactor control system should be modified. this paper describes a power reactor control system that is designed based on a state feedback method optimized with LQG (Linear-quadrature-gaussian) method and equipped with a state estimator. A pressurized-water type reactor has been used as the model. by using a point kinetics method with one group delayed neutrons. the result of simulation testing shows that the optimized control system can control the power reactor more effective and efficient than the classical control system

  1. 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

  2. Technical evaluation of the proposed deletion of a reactor trip on a turbine trip below 50-percent power for the Beaver Valley nuclear power plant, Unit 1

    International Nuclear Information System (INIS)

    Reeves, W.E.

    1979-12-01

    This report documents the technical evaluation of the Duquesne Light Company's proposed license amendment for the deletion of a reactor trip on a turbine trip below 50% power for the Beaver Valley nuclear power plant, Unit 1. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  3. Power generation costs for alternate reactor fuel cycles

    International Nuclear Information System (INIS)

    Smolen, G.R.; Delene, J.G.

    1980-09-01

    The total electric generating costs at the power plant busbar are estimated for various nuclear reactor fuel cycles which may be considered for power generation in the future. The reactor systems include pressurized water reactors (PWR), heavy-water reactors (HWR), high-temperature gas cooled reactors (HTGR), liquid-metal fast breeder reactors (LMFBR), light-water pre-breeder and breeder reactors (LWPR, LWBR), and a fast mixed spectrum reactor (FMSR). Fuel cycles include once-through, uranium-only recycle, and full recycle of the uranium and plutonium in the spent fuel assemblies. The U 3 O 8 price for economic transition from once-through LWR fuel cycles to both PWR recycle and LMFBR systems is estimated. Electric power generation costs were determined both for a reference set of unit cost parameters and for a range of uncertainty in these parameters. In addition, cost sensitivity parameters are provided so that independent estimations can be made for alternate cost assumptions

  4. Reactor coolant pump type RUV for Westinghouse Electric Company LLC reactor AP1000 TM

    International Nuclear Information System (INIS)

    Baumgarten, S.; Brecht, B.; Bruhns, U.; Fehring, P.

    2010-01-01

    The RUV is a reactor coolant pump, specially designed for the Westinghouse Electric Company LLC AP1000 TM reactor. It is a hermetically sealed, wet winding motor pump. The RUV is a very compact, vertical pump/motor unit, designed to fit into the compartment next to the reactor pressure vessel. Each of the two steam generators has two pump casings welded to the channel head by the suction nozzle. The pump/motor unit consists of a pump part, where a semi-axial impeller/diffuser combination is mounted in a one-piece pump casing. Computational Fluid Dynamics methods combined with various hydraulic tests in a 1:2 scale hydraulic test assure full compliance with the specific customer requirements. A short and rigid shaft, supported by a radial bearing, connects the impeller with the high inertia flywheel. This flywheel consists of a one-piece forged stainless steel cylinder, with an option for several smaller heavy metal cylinders inside. The flywheel is located inside the thermal barrier, which forms part of the pressure boundary. A specific arrangement of cooling water circuits guarantees a homogeneous temperature distribution in and around the flywheel, minimizes the friction losses of the flywheel and protects the motor from hot coolant. The driving torque is transmitted by the motor shaft, which itself is supported by two radial bearings. A three-phase, high-voltage squirrel-cage induction motor generates the driving torque. Due to the wet winding concept it is possible to achieve positive effects regarding motor lifetime. The cooling water is forced through the stator windings and the gap between rotor and stator by an auxiliary impeller. Furthermore, this wet winding motor concept has higher efficiency as compared to a canned motor since there are no eddy current losses. As part of the design process and in addition to the hydraulic scale model, a complete half scale model pump was built. It was used to verify the calculations performed like coast

  5. Energy, electricity and nuclear power

    International Nuclear Information System (INIS)

    Reuss, P.; Naudet, G.

    2008-01-01

    After an introduction recalling what energy is, the first part of this book presents the present day energy production and consumption and details more particularly the electricity 'vector' which is an almost perfect form of energy despite the fact that it is not a primary energy source: it must be generated from another energy source and no large scale storage of this energy is possible. The second part of the book is devoted to nuclear energy principles and to the related technologies. Content: 1 - What does energy mean?: the occurrence of the energy concept, the classical notion of energy, energy notion in modern physics, energy transformations, energy conservation, irreversibility of energy transformations, data and units used in the energy domain; 2 - energy production and consumption: energy systems, energy counting, reserves and potentialities of energy resources, production of primary energies, transport and storage of primary energies, energy consumption, energy saving, energy markets and prices, energy indicators; 3 - electric power: specificity of electricity and the electric system, power networks, power generation, electricity storage, power consumption and demand, power generation economics, electricity prices and market; 4 - physical principles of nuclear energy: nuclei structure and binding energy, radioactivity and nuclear reactions, nuclear reactions used in energy generation, basics of fission reactors physics; 5 - nuclear techniques: historical overview, main reactor types used today, perspectives; 6 - fuel cycle: general considerations, uranium mining, conversion, enrichment, fuel fabrication, back-end of the cycle, plutonium recycle in water cooled reactors; 7 - health and environmental aspects of nuclear energy: effects on ionizing radiations, basics of radiation protection, environmental impacts of nuclear energy, the nuclear wastes problem, specific risks; 8 - conclusion; 9 - appendixes (units, physics constants etc..)

  6. MODERN ELECTRIC CARS OF TESLA MOTORS COMPANY

    OpenAIRE

    O. F. Vynakov; E. V. Savolova; A. I. Skrynnyk

    2016-01-01

    This overview article shows the advantages of a modern electric car as compared with internal combustion cars by the example of the electric vehicles of Tesla Motors Company. It (в смысле- статья) describes the history of this firm, provides technical and tactical characteristics of three modifications of electric vehicles produced by Tesla Motors. Modern electric cars are not less powerful than cars with combustion engines both in speed and acceleration amount. They are reliable, economical ...

  7. Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Hsien-Chuan, E-mail: linsc@iner.org.tw [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yaur, Shung-Jung; Lin, Tzung-Yi; Kuo, Weng-Sheng; Shiue, Jin-Yih; Huang, Yu-Lung [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Studsvik's core management system (CMS) was applied to Taiwan Power Company's pressurized water reactor. Black-Right-Pointing-Pointer Advanced calculation model of shutdown cooling, B-10 depletion and integrated pin exposure were introduced. Black-Right-Pointing-Pointer Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated to measurement data. Black-Right-Pointing-Pointer The uncertainty of each item was quantified. - Abstract: This paper presents the validation of Studsvik core management system (CMS) for application to the Maanshan units 1 and 2 reactor core physics analysis (Huang and Yang, 1994). The methodology was validated by demonstrating the ability to obtain accurate and reliable results for various conditions and applications. Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated. Analytical results have been compared to measured data and reliability factors of the method have been quantified.

  8. Development on power distribution technologies of four electric power companies in Japan. The Kansai Electric Power Co. , Inc

    Energy Technology Data Exchange (ETDEWEB)

    1989-07-01

    Since dependency upon electric power has been rising yearly with the development of industry and the progress of information-oriented society, various kinds of technical development are needed to supply electricity. Furthermore, amenity of people's living has been highly intended, and life style has varied. Consequently, customers' needs for energy including related services have varied remarkably, and each customer has selected energy more subjectively from the wide range of viewpoint such as reliability, handiness, cleanliness, safety, and economic efficiency. In such situation, the power distribution section of Kansai Electric Power settled four themes for major technical development and has been promoting them. Four themes are as follows; to develop a total automation system for power distribution, to promote 20kV/400V-class power distribution, to develop techniques to form facilities harmonizing with local amenity, and to make business management efficient with the advanced NC system. 3 figs., 4 tabs.

  9. Operating history of U.S. nuclear power reactors

    International Nuclear Information System (INIS)

    1974-01-01

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

  10. NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

  11. Sectoral panorama: the electric power sector in Europe

    International Nuclear Information System (INIS)

    Mons, L.

    2003-10-01

    This study takes stock on the main european markets to help the electric power companies in their decisions and investments. The first part presents the electric power sector structure in Europe. The second part is devoted to the market evolution for the different european markets (german, french, british, italian and spanish) with an analysis of the retail prices, the competition and the evolution perspectives. The third part presents the highlights in the electric power sector between 2001 and the middle of 2003. The enterprises management and strategies are presented in the fourth part. In the last part the document analyzes the financial performances of the sector and the electric power companies. (A.L.B.)

  12. Power generator in BWR type reactors

    International Nuclear Information System (INIS)

    Yoshida, Kenji.

    1984-01-01

    Purpose: To enable to perform stable and dynamic conditioning operation for nuclear fuels in BWR type reactors. Constitution: The conditioning operation for the nuclear fuels is performed by varying the reactor core thermal power in a predetermined pattern by changing the predetermined power changing pattern of generator power, the rising rate of the reactor core thermal power and the upper limit for the rising power of the reactor core thermal power are calculated and the power pattern for the generator is corrected by a power conditioning device such that the upper limit for the thermal power rising rate and the upper limit for the thermal power rising rate are at the predetermined levels. Thus, when the relation between the reactor core thermal power and the generator electrical power is fluctuated, the fluctuation is detected based on the variation in the thermal power rising rate and the limit value for the thermal power rising rate, and the correction is made to the generator power changing pattern so that these values take the predetermined values to thereby perform the stable conditioning operation for the nuclear fuels. (Moriyama, K.)

  13. Overview of electric power industry of main countries in the world

    International Nuclear Information System (INIS)

    2013-01-01

    The electric power supply system, power producer, regulation system, electricity liberalization, power demand and supply, electricity rate, development of electric power sources, nuclear power generation and renewable energy of six countries such as USA, England, German, France, Russia and China are reported. On USA, 3,754 x 10 9 kWh of total electric energy, 104 of nuclear reactors are running and giving careful consideration to safety of the plant. Shale gas production is increasing, and new technology of electric car, smart grid and demand response is developing. On England, 368 x 10 9 kWh of total electric energy, which consisted of 70.4% thermal power, 18.8% nuclear power and 10.8% renewable energy, 18 nuclear reactors are running, but almost nuclear power plants will be closed until 2023. Biomass and wind power have been developed. On German, 609 x 10 9 kWh of total electric energy, 9 nuclear reactors are running but closed till 2022, the renewable energy such as wind power and photovoltaic is introduced. On France, 542 x 10 9 kWh total electric energy, which consisted of 9% hydroelectricity, 9% thermal power, 78% nuclear power and 4% renewable energy. The renewable energy plan is formulated. On Russia, 1,052 x 10 9 kWh total electric energy consisted of 67.8% thermal power, 15.7% hydroelectricity and 16.4% nuclear power, 32 nuclear power plants are running and 9 nuclear reactors building. On China, 4,693 x 10 9 kWh power consumption, 6 nuclear power plants are running to generate 1.85% electric energy, the objects of nuclear power generation and renewable energy were announced. (S.Y.)

  14. Power Nuclear Reactors: technology and innovation for development in future

    International Nuclear Information System (INIS)

    Suarez Antola, R.

    2009-01-01

    The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view

  15. Integrated Plant Safety Assessment: Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Final report

    International Nuclear Information System (INIS)

    1983-06-01

    The Systematic Evaluation program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides: (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  16. Integrated Plant Safety Assessment, Systematic Evaluation Program. Yankee Nuclear Power Station, Yankee Atomic Electric Company, Docket No. 50-29. Draft report

    International Nuclear Information System (INIS)

    1983-02-01

    The Systematic Evaluation Program was initiated in February 1977 by the US Nuclear Regulatory Commission to review the designs of older operating nuclear reactor plants to confirm and document their safety. The review provides (1) an assessment of how these plants compare with current licensing safety requirements relating to selected issues, (2) a basis for deciding on how these differences should be resolved in an integrated plant review, and (3) a documented evaluation of plant safety. This report documents the review of Yankee Nuclear Power Station, operated by Yankee Atomic Electric Company. The Yankee plant is one of 10 plants reviewed under Phase II of this program. This report indicates how 137 topics selected for review under Phase I of the program were addressed. Equipment and procedural changes have been identified as a result of the review

  17. An approach of raising the low power reactor trip block (P-7) in Maanshan Power Plant

    International Nuclear Information System (INIS)

    Wang, L.C.

    1984-01-01

    The technical specification for the Maanshan Nuclear Power Station (FSAR Table 16.2.2-3) requires that with an increasing reactor power level above the setpoint of low power reactor trip block (P-7), a turbine trip shall initiate a reactor trip. This anticipatory reactor trip on turbine trip prevents the pressurizer PORV from openning during turbine trip event. In order to reduce unnecessary reactor trip due to turbine trip on low reactor power level during Maanshan start-up stage, Taiwan Power Company performed a transient analysis for turbine trip event by using RETRAN code. The highest reactor power level at which a turbine trip will not open the pressurizer PORV is searched. The results demonstrated that this power level can be increased from the original value-10% of the rated thermal power-to about 48% of the rated thermal power

  18. Cermet-fueled reactors for multimegawatt space power applications

    International Nuclear Information System (INIS)

    Cowan, C.L.; Armijo, J.S.; Kruger, G.B.; Palmer, R.S.; Van Hoomisson, J.E.

    1988-01-01

    The cermet-fueled reactor has evolved as a potential power source for a broad range of multimegawatt space applications. In particular, the fast spectrum reactor concept can be used to deliver 10s of megawatts of electric power for continuous, long term, unattended operation, and 100s of megawatts of electric power for times exceeding several hundred seconds. The system can also be utilized with either a gas coolant in a Brayton power conversion cycle, or a liquid metal coolant in a Rankine power conversion cycle. Extensive testing of the cermet fuel element has demonstrated that the fuel is capable of operating at very high temperatures under repeated thermal cycling conditions, including transient conditions which approach the multimegawatt burst power requirements. The cermet fuel test performance is reviewed and an advanced cermet-fueled multimegawatt nuclear reactor is described in this paper

  19. An Optimum Solution for Electric Power Theft

    Directory of Open Access Journals (Sweden)

    Aamir Hussain Memon

    2013-07-01

    Full Text Available Electric power theft is a problem that continues to plague power sector across the whole country. Every year, the electricity companies face the line losses at an average 20-30% and according to power ministry estimation WAPDA companies lose more than Rs. 125 billion. Significantly, it is enough to destroy the entire power sector of country. According to sources 20% losses means the masses would have to pay extra 20% in terms of electricity tariffs. In other words, the innocent consumers pay the bills of those who steal electricity. For all that, no any permanent solution for this major issue has ever been proposed. We propose an applicable and optimum solution for this impassable problem. In our research, we propose an Electric power theft solution based on three stages; Transmission stage, Distribution stage, and User stage. Without synchronization among all, the complete solution can not be achieved. The proposed solution is simulated on NI (National Instruments Circuit Design Suite Multisim v.10.0. Our research work is an implicit and a workable approach towards the Electric power theft, as for conditions in Pakistan, which is bearing the brunt of power crises already

  20. An Optimum Solution for Electric-Power Theft

    International Nuclear Information System (INIS)

    Memon, A.H.; Memon, F.

    2013-01-01

    Electric power theft is a problem that continues to plague power sector across the whole country. Every year, the electricity companies face the line losses at an average 20-30% and according to power ministry estimation WAPDA companies lose more than Rs. 125 billion. Significantly, it is enough to destroy the entire power sector of country. According to sources 20% losses means the masses would have to pay extra 20% in terms of electricity tariffs. In other words, the innocent consumers pay the bills of those who steal electricity. For all that, no any permanent solution for this major issue has ever been proposed. We propose an applicable and optimum solution for this impassable problem. In our research, we propose an Electric power theft solution based on three stages; Transmission stage, Distribution stage, and User stage. Without synchronization among all, the complete solution can not be achieved. The proposed solution is simulated on NI (National Instruments) Circuit Design Suite Multisim v.10.0. Our research work is an implicit and a workable approach towards the Electric power theft, as for conditions in Pakistan, which is bearing the brunt of power crises already. (author)

  1. A three-stage short-term electric power planning procedure for a generation company in a liberalized market

    International Nuclear Information System (INIS)

    Nabona, Narcis; Pages, Adela

    2007-01-01

    In liberalized electricity markets, generation companies bid their hourly generation in order to maximize their profit. The optimization of the generation bids over a short-term weekly period must take into account the action of the competing generation companies and the market-price formation rules and must be coordinated with long-term planning results. This paper presents a three stage optimization process with a data analysis and parameter calculation, a linearized unit commitment, and a nonlinear generation scheduling refinement. Although the procedure has been developed from the experience with the Spanish power market, with minor adaptations it is also applicable to any generation company participating in a competitive market system. (author)

  2. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

    1994-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

  3. Design of megawatt power level heat pipe reactors

    Energy Technology Data Exchange (ETDEWEB)

    Mcclure, Patrick Ray [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dasari, Venkateswara Rao [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reid, Robert Stowers [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-11-12

    An important niche for nuclear energy is the need for power at remote locations removed from a reliable electrical grid. Nuclear energy has potential applications at strategic defense locations, theaters of battle, remote communities, and emergency locations. With proper safeguards, a 1 to 10-MWe (megawatt electric) mobile reactor system could provide robust, self-contained, and long-term power in any environment. Heat pipe-cooled fast-spectrum nuclear reactors have been identified as a candidate for these applications. Heat pipe reactors, using alkali metal heat pipes, are perfectly suited for mobile applications because their nature is inherently simpler, smaller, and more reliable than “traditional” reactors. The goal of this project was to develop a scalable conceptual design for a compact reactor and to identify scaling issues for compact heat pipe cooled reactors in general. Toward this goal two detailed concepts were developed, the first concept with more conventional materials and a power of about 2 MWe and a the second concept with less conventional materials and a power level of about 5 MWe. A series of more qualitative advanced designs were developed (with less detail) that show power levels can be pushed to approximately 30 MWe.

  4. 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

  5. Thermionic reactors for space nuclear power

    Science.gov (United States)

    Homeyer, W. G.; Merrill, M. H.; Holland, J. W.; Fisher, C. R.; Allen, D. T.

    1985-01-01

    Thermionic reactor designs for a variety of space power applications spanning the range from 5 kWe to 3 MWe are described. In all of these reactors, nuclear heat is converted directly to electrical energy in thermionic fuel elements (TFEs). A circulating reactor coolant carries heat from the core of TFEs directly to a heat rejection radiator system. The recent design of a thermionic reactor to meet the SP-100 requirements is emphasized. Design studies of reactors at other power levels show that the same TFE can be used over a broad range in power, and that design modifications can extend the range to many megawatts. The design of the SP-100 TFE is similar to that of TFEs operated successfully in test reactors, but with design improvements to extend the operating lifetime to seven years.

  6. Centralized vs. decentralized thermal IR inspection policy: experience from a major Brazilian electric power company

    Science.gov (United States)

    dos Santos, Laerte; da Costa Bortoni, Edson; Barbosa, Luiz C.; Araujo, Reyler A.

    2005-03-01

    Furnas Centrais Elétricas S.A is one of the greatest companies of the Brazilian electric power sector and a pioneer in using infrared thermography. In the early 70s, the maintenance policy used was a centralized approach, with only one inspection team to cover all the company"s facilities. In the early 90s, FURNAS decided to decentralize the thermography inspections creating several inspection teams. This new maintenance policy presented several advantages when compared to the previous one. However the credibility of the results obtained with the thermal inspection was frequently being questioned, in part due to the lack of a detailed planning to carry out the transition from the centralized inspection to the decentralized one. In some areas of the company it was suggested the inactivation of the thermography. This paper presents the experience of FURNAS with these different maintenance policies and details the procedures which have been taken that nowadays the infrared thermal inspection has become one of the most important techniques of predictive maintenance in the company.

  7. Reactor Power Meter type SG-8

    Energy Technology Data Exchange (ETDEWEB)

    Glowacki, S W

    1981-01-01

    The report describes the principle and electronic circuits of the Reactor Power Meter type SG-8. The gamma radiation caused by the activity of the reactor first cooling circuit affectes the ionization chamber being the detector of the instrument. The output detector signal direct current is converted into the frequency of electric pulses by means of the current-to-frequency converter. The output converter frequency is measured by the digital frequency meter: the number of measured digits in time unit is proportional to the reactor power.

  8. Composite electric generator equipped with steam generator for heating reactor coolant

    International Nuclear Information System (INIS)

    Watabe, Masaharu; Soman, Yoshindo; Kawanishi, Kohei; Ota, Masato.

    1997-01-01

    The present invention concerns a composite electric generator having coolants, as a heating source, of a PWR type reactor or a thermonuclear reactor. An electric generator driving gas turbine is disposed, and a superheater using a high temperature exhaust gas of the gas turbine as a heating source is disposed, and main steams are superheated by the superheater to elevate the temperature at the inlet of the turbine. This can increase the electric generation capacity as well as increase the electric generation efficiency. In addition, since the humidity in the vicinity of the exit of the steam turbine is reduced, occurrence of loss and erosion can be suppressed. When cooling water of the thermonuclear reactor is used, the electric power generated by the electric generator driven by the gas turbine can be used upon start of the thermonuclear reactor, and it is not necessary to dispose a large scaled special power source in the vicinity, which is efficient. (N.H.)

  9. Evaluation of Electric Power Procurement Strategies by Stochastic Dynamic Programming

    Science.gov (United States)

    Saisho, Yuichi; Hayashi, Taketo; Fujii, Yasumasa; Yamaji, Kenji

    In deregulated electricity markets, the role of a distribution company is to purchase electricity from the wholesale electricity market at randomly fluctuating prices and to provide it to its customers at a given fixed price. Therefore the company has to take risk stemming from the uncertainties of electricity prices and/or demand fluctuation instead of the customers. The way to avoid the risk is to make a bilateral contact with generating companies or install its own power generation facility. This entails the necessity to develop a certain method to make an optimal strategy for electric power procurement. In such a circumstance, this research has the purpose for proposing a mathematical method based on stochastic dynamic programming and additionally considering the characteristics of the start-up cost of electric power generation facility to evaluate strategies of combination of the bilateral contract and power auto-generation with its own facility for procuring electric power in deregulated electricity market. In the beginning we proposed two approaches to solve the stochastic dynamic programming, and they are a Monte Carlo simulation method and a finite difference method to derive the solution of a partial differential equation of the total procurement cost of electric power. Finally we discussed the influences of the price uncertainty on optimal strategies of power procurement.

  10. Electric Energy Consumption of Multi Purpose Reactor GA. Siwabessy During Reactor Operation

    International Nuclear Information System (INIS)

    Koes Indrakoesoema

    2012-01-01

    Electrical power supply of Reactor Center Multi Purpose obtained from PT PLN to 3030 kVA power contracts. Distribution to existing loads in PRSG divided into 3 (three) lines, each of which is supplied through a transformer BHT01, BHT02 and BHT03, each transformer have capacity of 1600 kVA. During reactor operation, only 2 lines that serve loads, each line serve 2 primary pump motor and 2 secondary pump motor. Electrical power for 24 hours for measurement BHT01, the average is 288 kW, for BHT02 is 641 kW and BHT03 is 466 kW. The energy absorbed by each transformer for 24 hours of measurement, for BHT01 is 6.44 MWh, BHT02 absorb 14.8 MWh and BHT03 absorb 10.9 MWh. (author)

  11. Characteristics of self-powered neutron detectors used in power reactors

    International Nuclear Information System (INIS)

    Todt, W.H.

    1997-01-01

    Self-Powered Neutron Detectors have been used effectively as in-core flux monitors for over twenty-five years in nuclear power reactors world-wide. The basic properties of these radiation sensors are described including their nuclear, electrical and mechanical characteristics. Recommendations are given for the proper choice of the self-powered detector emitter to provide the proper response time and radiation sensitivity desired for use in an effective in-core radiation monitoring system. Examples are shown of specific self-powered detector designs which are being effectively used in in-core instrumentation systems for pressurised water, heavy water and graphite moderated light water reactors. Examples are also shown of the mechanical configurations of in-core assemblies of self-powered detectors combined with in-core thermocouples presently used in pressurised water and heavy water reactors worldwide. This paper is a summary of a new IEC standard to be issued in 1996 describing the characteristics and test methods of self-powered detectors used in nuclear power reactors. (author)

  12. Reactors for nuclear electric propulsion

    Energy Technology Data Exchange (ETDEWEB)

    Buden, D.; Angelo, J.A. Jr.

    1981-01-01

    Propulsion is the key to space exploitation and power is the key to propulsion. This paper examines the role of nuclear fission reactors as the primary power source for high specific impulse electric propulsion systems for space missions of the 1980s and 1990s. Particular mission applications include transfer to and a reusable orbital transfer vehicle from low-Earth orbit to geosynchronous orbit, outer planet exploration and reconnaissance missions, and as a versatile space tug supporting lunar resource development. Nuclear electric propulsion is examined as an indispensable component in space activities of the next two decades.

  13. Reactors for nuclear electric propulsion

    International Nuclear Information System (INIS)

    Buden, D.; Angelo, J.A. Jr.

    1981-01-01

    Propulsion is the key to space exploitation and power is the key to propulsion. This paper examines the role of nuclear fission reactors as the primary power source for high specific impulse electric propulsion systems for space missions of the 1980s and 1990s. Particular mission applications include transfer to and a reusable orbital transfer vehicle from low-Earth orbit to geosynchronous orbit, outer planet exploration and reconnaissance missions, and as a versatile space tug supporting lunar resource development. Nuclear electric propulsion is examined as an indispensable component in space activities of the next two decades

  14. A centennial book of Korea electric power corporation

    International Nuclear Information System (INIS)

    1989-12-01

    This book gives description of KEPC with power and life such as lighting, electric power, electric heat and communication, introduction of electric civilization, establishment and manage of Hansung electric company on opening of electric train, regulation of the train, opening of lamp business, construction of Yongsan generator, the Japanese invasion with trouble of supplying electricity, control over power business and development of water power generation, division of Korea and Korea war on damage out of Korea war and rebuild, development and growth on establishment of Korea electric power, establishment of Korea electric power by private and water power development project, stability and development, and challenge for future.

  15. Tampa Electric Company Polk Power Station IGCC project: Project status

    Energy Technology Data Exchange (ETDEWEB)

    McDaniel, J.E.; Carlson, M.R.; Hurd, R.; Pless, D.E.; Grant, M.D. [Tampa Electric Co., FL (United States)

    1997-12-31

    The Tampa Electric Company Polk Power Station is a nominal 250 MW (net) Integrated Gasification Combined Cycle (IGCC) power plant located to the southeast of Tampa, Florida in Polk County, Florida. This project is being partially funded under the Department of Energy`s Clean Coal Technology Program pursuant to a Round II award. The Polk Power Station uses oxygen-blown, entrained-flow IGCC technology licensed from Texaco Development Corporation to demonstrate significant reductions of SO{sub 2} and NO{sub x} emissions when compared to existing and future conventional coal-fired power plants. In addition, this project demonstrates the technical feasibility of commercial scale IGCC and Hot Gas Clean Up (HGCU) technology. The Polk Power Station achieved ``first fire`` of the gasification system on schedule in mid-July, 1996. Since that time, significant advances have occurred in the operation of the entire IGCC train. This paper addresses the operating experiences which occurred in the start-up and shakedown phase of the plant. Also, with the plant being declared in commercial operation as of September 30, 1996, the paper discusses the challenges encountered in the early phases of commercial operation. Finally, the future plans for improving the reliability and efficiency of the Unit in the first quarter of 1997 and beyond, as well as plans for future alternate fuel test burns, are detailed. The presentation features an up-to-the-minute update on actual performance parameters achieved by the Polk Power Station. These parameters include overall Unit capacity, heat rate, and availability. In addition, the current status of the start-up activities for the HGCU portion of the plant is discussed.

  16. Intervention in independent spent fuel storage facility license application proceedings for storage on the power plant site

    International Nuclear Information System (INIS)

    Jordan, J.

    1992-01-01

    This presentation summarizes the intervention in the Nuclear Regulatory Commission (NRC) licensing process for currently operating Independent Spent fuel Storage Installation (ISFSI) projects at Carolina Power and Light's Company's H.B. Robinson, Duke Power Company's Oconee, and Virginia Power Company's Surry. In addition, intervention at dry storage facilities that are currently under development are also described. The utilities and reactors include Baltimore Gas and Electric Company's Calvert Cliffs, Public Service Company of Colorado's Fort St. Vrain plant, Northern States Power Company's Prairie Island, Wisconsin Electric Power Company's Point Beach, and Consumers Power Company's Palisades

  17. Competitiveness of nuclear power in Japanese liberalized electricity market

    International Nuclear Information System (INIS)

    Abe, Y.

    2006-01-01

    The liberalization of Japanese electricity market expanded to customers of over 50 kV on April 1, 2005 and more than 60% of the market has been already open. The discussion about the assistance measures of nuclear power generation in Japanese liberalization of electricity market has come to grow warmer gradually. The opinions on the competitiveness of nuclear power are inconsistency among the supporters of nuclear power. Some says that nuclear power is the most competitive, others says nuclear power require some sort of financial or political assistance in the deregulation of electricity market. In this study, based on financial statements of each Japanese electric power company, the constitution of generation cost of nuclear power is illustrated and various financial and economic characteristics, including ''merit of scale'' and the impact of new nuclear power plant construction on the finance of electric power company, are discussed. In addition, the economic features of nuclear power generation are compared with those of thermal power generation through the analysis of financial statements. Finally, support policies for nuclear power required in deregulation of electric utilities are examined in terms of fairness of competition and security of electricity supply

  18. POSSIBILITIES OF APPLYING THE DEA METHOD IN THE ASSESSMENT OF EFFICIENCY OF COMPANIES IN THE ELECTRIC POWER INDUSTRY: REVIEW OF WIND ENERGY COMPANIES

    Directory of Open Access Journals (Sweden)

    Dario Maradin

    2014-07-01

    Full Text Available One of the fundamental tasks of modern power system is finding ways to produce stable and continuous electricity from scarce energy resources. One of the possible solutions is introduction, implementation and improvement of alternative forms of energy such as renewable energy sources, particularly wind energy as an increasingly important energy source which is expected to further increase its share in total electricity production. Numerous methods can be used in assessing the efficiency of wind energy companies, and in the focus of this research is the Data Envelopment Analysis method (DEA, a widely accepted methodology given its interdisciplinary approach and flexibility. This method represents a step forward in the field of renewable energy management, because it provides the possibility to compare the selected companies with the best in the industry (the most efficient and the possibility of determining sources of inefficiency and, consequently, the possibilities of their elimination.

  19. Assessment of Power Quality Problems for TRIGA PUSPATI Reactor (RTP)

    International Nuclear Information System (INIS)

    Mohd Fazli Zakaria; Ramachandaramurthy, V.K.

    2016-01-01

    The electrical power systems are exposed to different types of power quality disturbances. Investigation and monitoring of power quality is necessary to maintain accurate operation of sensitive equipment especially for nuclear installations. This paper will discuss the power quality problems observed at the electrical sources of PUSPATI TRIGA Reactor (RTP). Assessment of power quality requires the identification of any anomalous behavior on a power system, which adversely affects the normal operation of electrical or electronic equipment. A power quality assessment involves gathering data resources; analyzing the data (with reference to power quality standards) then, if problems exist, recommendation of mitigation techniques must be considered. Field power quality data is collected by power quality recorder and analyzed with reference to power quality standards. Normally the electrical power is supplied to the RTP via two sources in order to keep a good reliability where each of them is designed to carry the full load. The assessment of power quality during reactor operation was performed for both electrical sources. There were several disturbances such as voltage harmonics and flicker that exceeded the thresholds. (author)

  20. Georgia Power Company's college degree program

    International Nuclear Information System (INIS)

    Coggin, C.L.

    1988-01-01

    The purpose of this paper is to describe Georgia Power Company's on-site college degree program for nuclear power plant personnel. In February 1986, the US Nuclear Regulatory Commission issued a policy statement concerning engineering expertise on shift (Generic Letter 86-04), which appeared in Volume 50, Number 208 of the October 28, 1985 Federal Register. One of the options available to nuclear power plant personnel to meet the requirement was the combined senior reactor operator/shift technical adviser position. One of the methods for meeting the option included a bachelor's degree in engineering technology for an accredited institution, including course work in the physical, mathematical, or engineering sciences

  1. Memorial 1997 - ENDESA (Chilean Electricity Company); ENDESA - Memoria 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    This report provides a comprehensive survey, in depth assessment of the activities overview of ENDESA, Chilean Electricity Company, highlighting economical information and including historical and technical aspects. Economics is its focal point, but other relevant data are shown, like technical data on hydroelectric and thermoelectric power plants. Main activities developed by ENDESA are described, such in Chile as in the foreign. Data on power generation, transmission and transport are also presented and an economical balance of each colligated company are done and analysed 35 figs., 115 tabs.

  2. Characteristics of self-powered neutron detectors used in power reactors

    International Nuclear Information System (INIS)

    Todt, William H. Sr.

    1998-01-01

    Self-powered neutron detectors have been used effectively as in-core flux monitors for over twenty-five years in nuclear power reactors worldwide. This paper describes the basic properties of these radiation sensors including their nuclear, electrical and mechanical characteristics. Recommendations are given for the proper choice of the self-powered detector emitter to provide the proper response time and radiation sensitivity desired for use in an effective in-core radiation monitoring system. Examples are shown of specific self-powered detector designs, which are being effectively, used in in-core instrumentation systems for pressurized water, heavy water and graphite moderated light water reactors. Also examples are shown of the mechanical configurations of in-core assemblies of self-powered detectors combined with in-core thermocouples presently used in pressurized water and heavy water reactors worldwide. (author)

  3. NRC [Nuclear Regulatory Commission] staff evaluation of the General Electric Company Nuclear Reactor Study (''Reed Report'')

    International Nuclear Information System (INIS)

    1987-07-01

    In 1975, the General Electric Company (GE) published a Nuclear Reactor Study, also referred to as ''the Reed Report,'' an internal product-improvement study. GE considered the document ''proprietary'' and thus, under the regulations of the Nuclear Regulatory Commission (NRC), exempt from mandatory public disclosure. Nonetheless, members of the NRC staff reviewed the document in 1976 and determined that it did not raise any significant new safety issues. The staff also reached the same conclusion in subsequent reviews. However, in response to recent inquiries about the report, the staff reevaluated the Reed Report from a 1987 perspective. This re-evaluation, documented in this staff report, concluded that: (1) there are no issues raised in the Reed Report that support a need to curtail the operation of any GE boiling water reactor (BWR); (2) there are no new safety issues raised in the Reed Report of which the staff was unaware; and (3) although certain issues addressed by the Reed Report are still being studied by the NRC and the industry, there is no basis for suspending licensing and operation of GE BWR plants while these issues are being resolved

  4. Modular helium reactor for non-electric applications

    International Nuclear Information System (INIS)

    Shenoy, A.

    1997-01-01

    The high temperature gas-cooled Modular Helium Reactor (MHR) is an advanced, high efficiency reactor system which can play a vital role in meeting the future energy needs of the world by contributing not only to the generation of electric power, but also the non-electric energy traditionally served by fossil fuels. This paper summarizes work done over 20 years, by several people at General Atomics, how the Modular Helium Reactor can be integrated to provide different non-electric applications during Process Steam/Cogeneration for industrial application, Process Heat for transportation fuel development and Hydrogen Production for various energy applications. The MHR integrates favorably into present petrochemical and primary metal process industries, heavy oil recovery, and future shale oil recovery and synfuel processes. The technical fit of the Process Steam/Cogeneration Modular Helium Reactor (PS/C-MHR) into these processes is excellent, since it can supply the required quantity and high quality of steam without fossil superheating. 12 refs, 25 figs, 2 tabs

  5. Operating US power reactors

    International Nuclear Information System (INIS)

    Silver, E.G.

    1988-01-01

    This update, which appears regularly in each issue of Nuclear Safety, surveys the operations of those power reactors in the US which have been issued operating licenses. Table 1 shows the number of such reactors and their net capacities as of September 30, 1987, the end of the three-month period covered in this report. Table 2 lists the unit capacity and forced outage rate for each licensed reactor for each of the three months (July, August, and September 1987) covered in this report and the cumulative values of these parameters since the beginning of commercial operation. In addition to the tabular data, this article discusses other significant occurrences and developments that affected licensed US power reactors during this reporting period. Status changes at Braidwood Unit 1, Nine Mile Point 2, and Beaver Valley 2 are discussed. Other occurrences discussed are: retraining of control-room operators at Peach Bottom; a request for 25% power for Shoreham, problems at Fermi 2 which delayed the request to go to 75% power; the results of a safety study of the N Reactor at Hanford; a proposed merger of Pacific Gas and Electric with Sacramento Municipal Utility District which would result in the decommissioning of Rancho Seco; the ordered shutdown of Oyster Creek; a minor radioactivity release caused by a steam generator tube rupture at North Anna 1; and 13 fines levied by the NRC on reactor licensees

  6. Ethics on the TEPCO bankruptcy, nuclear power plants and regulatory reform in the electric power industry

    International Nuclear Information System (INIS)

    Koga, Shigeaki

    2013-01-01

    Although regulatory reform in the electric power industry had been considered as part of social system reform like in the finance and communications to liberalize the market, there still continued to exist regional monopoly, integrated system for power generation, transmission and distribution, and lack of competition. The Fukushima accident showed such electric power system was unethical as social system compared to ordinary industries, because electric power company getting profit could not be prepared for nuclear damage liability and would burden third unrelated parties with risk. Electric power company should be forced to insure nuclear power plants for nuclear accidents. Otherwise restart of nuclear power plant operation should not be allowed. Nuclear power had been justified to be entitled grant or subsidy from the government for public good, which would be unfair to people. This article presented speeding-up scheme of Fukushima accident treatment leading to TEPCO bankruptcy and discussed measures against concerns or comments about bankruptcy procedures, major part of which might be mitigation of fund-raising fear by government support. At the proceeding of bankruptcy procedure including spinning off of separate companies, regulatory reform in the electric power industry could be taken in advanced. (T. Tanaka)

  7. Report from investigation committee on the accident at the Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    Koshizuka, Seiichi

    2012-01-01

    Government's Investigation Committee on the Accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company published its final report on July 23, 2012. Results of investigation combined final report and interim report published on December 26, 2011. The author was head of accident accuse investigation team mostly in charge of site response, prior measure and plant behavior. This article reported author related technical investigation results focusing on site response and prior measures against tsunamis of units 1-3 of Fukushima Nuclear Power Stations. Misunderstanding of working state of isolation condenser of unit 1, unsuitability of alternative water injection at manual stop of high-pressure coolant injection (HPCI) system of unit 3 and improper prior measure against tsunami and severe accident were pointed out in interim report. Improper monitoring of suppression chamber of unit 2 and again unsuitable work for HPCI system of unit 3 were reported in final report. Thorough technical investigation was more encouraged to update safety measures of nuclear power stations. (T. Tanaka)

  8. Limiting factor analysis of high availability nuclear plants (boiling water reactors). Final report

    International Nuclear Information System (INIS)

    Frederick, L.G.; Brady, R.M.; Shor, S.W.W.; McCusker, J.T.; Alden, W.M.; Kovacs, S.

    1979-08-01

    The pertinent results are presented of a 16-month study conducted for Electric Power Research Institute by General Electric Company, Bechtel Power Corporation, and Philadelphia Electric Company. The study centered around the Peach Bottom 2 Atomic Power Station, but also included limited study of operations at 20 additional operating boiling water reactors. The purpose of the study was to identify and evaluate key factors limiting plant availability, and to identify potential improvements for eliminating or alleviating those limitations. The key limiting factors were found to be refueling activities; activities related to the reactor fuel; reactor scrams; activities related to 20 operating systems or major components; delays due to radiation, turbid water during refueling operations, facilities/working conditions, and dirt/foreign material; and general maintenance/repair of valves and piping. Existing programs to reduce the effect on plant unavailability are identified, and suggestions for further action are made

  9. 75 FR 75704 - Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of...

    Science.gov (United States)

    2010-12-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-275-LR; 50-323-LR] Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 And 2); Notice of Appointment of Adjudicatory Employee... Seismologist, Office of Nuclear Material Safety and Safeguards, has been appointed as a Commission adjudicatory...

  10. Nitrogen oxide control at power plants of the ENEL company (Italy)

    Energy Technology Data Exchange (ETDEWEB)

    Kotler, V.R. (Vserossiiskii Teplotekhnicheskii Institut (Russian Federation))

    1993-03-01

    Analyzes experiences of the ENEL electricity company in Italy in controlling pollutant emission from fossil-fuel power plants. In 1990, the company produced 87% of the country's electricity. Until the year 2000, ENEL plans to increase coal use for power generation by 23.5% and install 9,300 MW of new coal-fired power plant capacity. New European and Italian emission standards require ENEL to reduce NO[sub x] emissions by 30% from 1986 to 1998. NO[sub x] emission values from various fuel-oil and pulverized-coal fired steam generators operated by the company are given. Modifications to existing combustion technologies and equipment installed to lower NO[sub x] content in flue gases at various ENEL power plants are considered. The most promising coal combustion technologies and ongoing research programs are pointed out. 4 refs.

  11. An agent-based simulation of power generation company behavior in electricity markets under different market-clearing mechanisms

    International Nuclear Information System (INIS)

    Aliabadi, Danial Esmaeili; Kaya, Murat; Şahin, Güvenç

    2017-01-01

    Deregulated electricity markets are expected to provide affordable electricity for consumers through promoting competition. Yet, the results do not always fulfill the expectations. The regulator's market-clearing mechanism is a strategic choice that may affect the level of competition in the market. We conceive of the market-clearing mechanism as composed of two components: pricing rules and rationing policies. We investigate the strategic behavior of power generation companies under different market-clearing mechanisms using an agent-based simulation model which integrates a game-theoretical understanding of the auction mechanism in the electricity market and generation companies' learning mechanism. Results of our simulation experiments are presented using various case studies representing different market settings. The market in simulations is observed to converge to a Nash equilibrium of the stage game or to a similar state under most parameter combinations. Compared to pay-as-bid pricing, bid prices are closer to marginal costs on average under uniform pricing while GenCos' total profit is also higher. The random rationing policy of the ISO turns out to be more successful in achieving lower bid prices and lower GenCo profits. In minimizing GenCos' total profit, a combination of pay-as-bid pricing rule and random rationing policy is observed to be the most promising. - Highlights: • An agent-based simulation of generation company behavior in electricity markets is developed. • Learning dynamics of companies is modeled with an extended Q-learning algorithm. • Different market clearing mechanisms of the regulator are compared. • Convergence to Nash equilibria is analyzed under different cases. • The level of competition in the market is studied.

  12. Potential minimum cost of electricity of superconducting coil tokamak power reactors

    International Nuclear Information System (INIS)

    Reid, R.L.; Peng, Y-K. M.

    1989-01-01

    The potential minimum cost of electricity (COE) for superconducting tokamak power reactors is estimated by increasing the physics (confinement, beta limit, bootstrap current fraction) and technology [neutral beam energy, toroidal field (TF) coil allowable stresses, divertor heat flux, superconducting coil critical field, critical temperature, and quench temperature rise] constraints far beyond those assumed for ITER until the point of diminishing returns is reached. A version of the TETRA systems code, calibrated with the ITER design and modified for power reactors, is used for this analysis, limiting this study to reactors with the same basic device configuration and costing algorithms as ITER. A minimum COE is reduced from >200 to about 80 mill/kWh when the allowable design constraints are raised to 2 times those of ITER. At 4 times the ITER allowables, a minimum COE of about 60 mill/kWh is obtained. The corresponding tokamak has a major radius of approximately 4 m, a plasma current close to 10 MA, an aspect ratio of 4, a confinement H- factor ≤3, a beta limit of approximately 2 times the first stability regime, a divertor heat flux of about 20 MW/m 2 , a Β max ≤ 18 T, and a TF coil average current density about 3 times that of ITER. The design constraints that bound the minimum COE are the allowable stresses in the TF coil, the neutral beam energy, and the 99% bootstrap current (essentially free current drive). 14 refs., 4 figs., 2 tabs

  13. Fire safety requirements for electrical cables towards nuclear reactor safety

    International Nuclear Information System (INIS)

    Raju, M.R.

    2002-01-01

    Full text: Electrical power supply forms a very important part of any nuclear reactor. Power supplies have been categorized in to class I, II, III and IV from reliability point. The safety related equipment are provided with highly reliable power supply to achieve the safety of very high order. Vast network of cables in a nuclear reactor are grouped and segregated to ensure availability of power to at least one group under all anticipated occurrences. Since fire can result in failures leading to unavailability of power caused by common cause, both passive and active fire protection methods are adopted in addition to fire detection system. The paper describes the requirement for passive fire protection to electrical cables viz. fire barrier and fire breaks. The paper gives an account of the tests required to standardize the products. Fire safety implementation for cables in research reactors is described

  14. Operating Experience in Nuclear Power Plants with Boiling-Water Reactors; Experience acquise dans l'exploitation des reacteurs a eau bouillante; Opyt ehkspluatatsii kipyashchago reaktora; Experiencia adquirida con la explotacion de reactores de agua hirviente

    Energy Technology Data Exchange (ETDEWEB)

    Ascherl, R. J. [General Electric Company, San Jose, CA (United States)

    1963-10-15

    Asignificant amount of operating experience has now been accumulated by boiling-water-reactor power plants. By the end of 1962, over 2200 million kWh of electricity have been generated by three plants operating on utility.system - Dresden Nuclear Power Station, Commonwealth Edison Company, Morris, Illinois; Vallecitos Atomic Power Plant, Pacific Gas and Electric Company and General Electric Company, Pleasanton, California; and Kahl Nuclear Power Station, Rheinisch Westfaelisches Elektrizitaetswerk and Bayernwerk, Kahl-am-Main, West Germany. Boiling-water-reactor power-plant performance, under routine electric-utility operating conditions, has been excellent. Reactor and plant availability and capacity factor provide a sound basis for anticipation of continuing reliable performance from boiling-water-reactor power stations. During 1963, four additional boiling-water-reactor plants will begin power operation: Big Rock Point Nuclear Plant, Consumers Power Company, Charlevoix, Michigan; Humboldt Bay Plant Nuclear Unit, Pacific Gas and Electric Company, Eureka, California; Garigliano Nuclear Power Station, Societa Elettronucleare Nazionale, Scauri, Italy; and Japan Power Demonstration Reactor, Japan Atomic Energy Research Institute, Tokai Mura, Japan. The start-up and initial operation of these plants confirms the expectation of reliable performance established by Dresden, Kahl, and Vallecitos. Performance records of Dresden, Kahl and Vallecitos have clearly proved the stability and safety of boiling-water reactors. Additionally, radiation levels within the plant and in the environs have been significantly below limits established by operating licences. Simplicity and ease of operation of boiling-water reactors has been confirmed. Load following characteristics of the Dresden dual-cycle boiling-water reactor have been excellent. Major and minor maintenance and repair work can be accomplished by ordinary craft unions, and without undue hardship or time limits caused by

  15. Nuclear Power and Ghana's Future Electricity Generation

    International Nuclear Information System (INIS)

    Ennison, I.; Dzobo, M.

    2011-01-01

    One of the major challenges facing Ghana in her developmental efforts is the generation of adequate and affordable electricity to meet increasing demand. Problems with the dependency on hydro power has brought insecurity in electricity supply due to periodic droughts. Thermal power systems have been introduced into the electricity generation mix to complement the hydro power supply but there are problems associated with their use. The high price of crude oil on the international market has made them expensive to run and the supply of less expensive gas from Steps are being taken to run the thermal plants on less expensive gas from Nigeria has delayed due to conflicts in the Niger Delta region and other factors. The existing situation has therefore called for the diversification of the electricity generation mix so as to ensure energy security and affordable power supply. This paper presents the nuclear option as a suitable alternative energy source which can be used to address the energy supply problems facing the nation as well the steps being taken towards its introduction in the national energy mix. In addition, electricity demand projections using the MAED model as well as other studies are presented. The expected electricity demand of 350000 GWh (4000MWyr) in 2030, exceeds the total electricity supply capability of the existing hydropower system, untapped hydro resources and the maximum amount of gas that can be imported from Nigeria through the West Africa pipeline. Also presented is a technological assessment on the type of nuclear reactor to be used. The technological assessment which was done based on economics, grid size, technological maturity, passive safety and standardization of reactor design, indicate that a medium sized pressurized water reactor (i.e. a PWR with capacity 300MW to 700MW) is the most favourable type of reactor. In addition the challenges facing the implementation of the nuclear power programme in Ghana are presented. (author)

  16. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Brunswick Steam Electric Plant, Units 1 and 2

    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 Brunswick Steam Electric Plant, Units 1 and 2. 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 with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources

  17. ATMEA and medium power reactors. The ATMEA joint venture and the ATMEA1 medium power reactor

    International Nuclear Information System (INIS)

    Mathet, Eric; Castello, Gerard

    2012-01-01

    This Power Point presentation presents the ATMEA company (a joint venture of Areva and Mitsubishi), the main features of its medium power reactor (ATMEA1) and its building arrangement, indicates the general safety objectives. It outlines the features of its robust design which aim at protecting, cooling down and containing. It indicates the regulatory and safety frameworks, comments the review of the safety options by the ASN and the results of this assessment

  18. Low power unattended defense reactor

    International Nuclear Information System (INIS)

    Kirchner, W.L.; Meier, K.L.

    1984-01-01

    A small, low power, passive, nuclear reactor electric power supply has been designed for unattended defense applications. Through innovative utilization of existing proven technologies and components, a highly reliable, ''walk-away safe'' design has been obtained. Operating at a thermal power level of 200 kWt, the reactor uses low enrichment uranium fuel in a graphite block core to generate heat that is transferred through heat pipes to a thermoelectric (TE) converter. Waste heat is removed from the TEs by circulation of ambient air. Because such a power supply offers the promise of minimal operation and maintenance (OandM) costs as well as no fuel logistics, it is particularly attractive for remote, unattended applications such as the North Warning System

  19. Low power unattended defense reactor

    International Nuclear Information System (INIS)

    Kirchner, W.L.; Meier, K.L.

    1984-01-01

    A small, low power, passive, nuclear reactor electric power supply has been designed for unattended defense applications. Through innovative utilization of existing proven technologies and components, a highly reliable, walk-away safe design has been obtained. Operating at a thermal power level of 200 kWt, the reactor uses low enrichment uranium fuel in a graphite block core to generate heat that is transferred through heat pipes to a thermoelectric (TE) converter. Waste heat is removed from the TEs by circulation of ambient air. Because such a power supply offers the promise of minimal operation and maintenance (O and M) costs as well as no fuel logistics, it is particularly attractive for remote, unattended applications such as the North Warning System

  20. Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2. Docket Nos. 50-387 and 50-388, Pennsylvania Power and Light Company, Allegheny Electric Cooperative, Inc

    International Nuclear Information System (INIS)

    1982-07-01

    Information is presented concerning site characteristics; design criteria for systems and components; reactor thermal and hydraulic characteristics; reactor coolant pressure boundary; engineered safety features; instrumentation and control; electrical power systems; auxiliary systems; conduct of operations; quality assurance; and TMI-2 requirements

  1. Performance of the Electric power companies of Burkina Faso, the Ivory Coast, Mali and Senegal, and their organizational models

    International Nuclear Information System (INIS)

    Girod, J.

    1993-01-01

    The history of the technical, economic, and financial performances of these four countries' power companies over the past two decades is recounted, and then interpreted as the result of the existing organizational models. The changes that have occurred can be understood in long-term perspective by comparing the performance of these companies to the characteristics, rules, and objectives used to define the models, which also helps explain the history of performance indicator variations. Two models are defined: one for the physical plant and one for the management. These correspond to two successive phases in the organization and operation of the electrical sector. Rural electrification and regional interconnection will be important factors in any new model or models developed for the future, because the forms they take is likely to modify the characteristics of these national power companies. 26 refs., 1 fig., 3 tabs

  2. Progress of innovation of electrical power technology in 2013

    International Nuclear Information System (INIS)

    Nakaiwa, Masaru; Inumaru, Jun; Hamada, Takashi

    2014-01-01

    The following is the description of technical innovations at five companies including Central Research Institute of Electric Power Industry, Japan Atomic Energy Agency, and Japan Nuclear Fuel Ltd. Central Research Institute of Electric Power Industry presented their efforts in (1) advancement of the safety of light water reactors (2) clarification of radiological risks and improvement of radiation protection matters (3) support of backend projects and (4) countermeasures against natural disasters for electric power distribution facilities aiming at the establishment of the optimum risk management. Japan Atomic Energy Agency presented the research and development related to (1) measures taken for the Fukushima Daiichi nuclear power plant accident (2) practical use of FBR cycle (3) disposal technology of high-level radioactive wastes (4) technical system to extract fusion energy (5) particle beam technology (6) research based on the formation of the foundation and social needs of atomic study (7) nuclear hydrogen/heat application (8) atomic safety (9) backend measures; and (10) nuclear proliferation. Japan Nuclear Fuel Ltd. presented the record of 5 and half years from the start to the completion of vitrification test. In the course of the development, the active test started from March 2003 was suspended due to the Great East Japan Earthquake on March 11th, 2011 but resumed thereafter and completed. (S.Y.)

  3. Westinghouse Electric Company experiences in chemistry on-line monitoring in Eastern European nuclear power plants

    International Nuclear Information System (INIS)

    Balavage, J.

    2001-01-01

    Westinghouse Electric Company has provided a number of Chemistry On-Line Monitoring (OLM) Systems to Nuclear Power Plants in Eastern Europe. Eleven systems were provided to the Temelin Nuclear Power Plant in the south of the Czech Republic. Four systems were provided to the Russian NPP at Novovoronezh. In addition, a system design was developed for primary side chemistry monitoring for units 5 and 6 of another eastern European VVER. The status of the Temelin OLM systems is discussed including updates to the Temelin designs, and the other Eastern European installations and designs are also described briefly. Some of the problems encountered and lessons learned from these projects are also discussed. (R.P.)

  4. How power is generated in a nuclear reactor

    International Nuclear Information System (INIS)

    Swaminathan, V.

    1978-01-01

    Power generation by nuclear fission as a result of chain reaction caused by neutrons interacting with fissile material such as 235 U, 233 U and 239 Pu is explained. Electric power production by reactor is schematically illustrated. Materials used in thermal reactor and breeder reactor are compared. Fuel reprocessing and disposal of radioactive waste coming from reprocessing plant is briefly described. Nuclear activities in India are reviewed. Four heavy water plants and two power reactors are under construction and will be operative in the near future. Two power reactors are already in operation. Nuclear Fuel Complex at Hyderabad supplies fuel element to the reactors. Fuel reprocessing and waste management facility has been set up at Tarapur. Bhabha Atomic Research Centre at Bombay and Reactor Research Centre at Kalpakkam near Madras are engaged in applied and basic research in nuclear science and engineering. (B.G.W.)

  5. 76 FR 69713 - Application To Export Electric Energy; BP Energy Company

    Science.gov (United States)

    2011-11-09

    ... DEPARTMENT OF ENERGY [OE Docket No. EA-314-A] Application To Export Electric Energy; BP Energy.... SUMMARY: BP Energy Company (BP Energy) has applied to renew its authority to transmit electric energy from... electric energy from the United States to Mexico as a power marketer for a five-year term using existing...

  6. 76 FR 69712 - Application To Export Electric Energy; BP Energy Company

    Science.gov (United States)

    2011-11-09

    ... DEPARTMENT OF ENERGY [OE Docket No. EA-315-A] Application To Export Electric Energy; BP Energy.... SUMMARY: BP Energy Company (BP Energy) has applied to renew its authority to transmit electric energy from... BP Energy to transmit electric energy from the United States to Canada as a power marketer for a five...

  7. The fast breeder reactor

    International Nuclear Information System (INIS)

    Davis, D.A.; Baker, M.A.W.; Hall, R.S.

    1990-01-01

    Following submission of written evidence, the Energy Committee members asked questions of three witnesses from the Central Electricity Generating Board and Nuclear Electric (which will be the government owned company running nuclear power stations after privatisation). Both questions and answers are reported verbatim. The points raised include where the responsibility for the future fast reactor programme should lie, with government only or with private enterprise or both and the viability of fast breeder reactors in the future. The case for the fast reactor was stated as essentially strategic not economic. This raised the issue of nuclear cost which has both a construction and a decommissioning element. There was considerable discussion as to the cost of building a European Fast reactor and the cost of the electricity it would generate compared with PWR type reactors. The likely demand for fast reactors will not arrive for 20-30 years and the need to build a fast reactor now is questioned. (UK)

  8. New advanced small and medium nuclear power reactors: possible nuclear power plants for Australia

    International Nuclear Information System (INIS)

    Dussol, R.J.

    2003-01-01

    In recent years interest has increased in small and medium sized nuclear power reactors for generating electricity and process heat. This interest has been driven by a desire to reduce capital costs, construction times and interest during construction, service remote sites and ease integration into small grids. The IAEA has recommended that the term 'small' be applied to reactors with a net electrical output less than 300 MWe and the term 'medium' to 300-700 MWe. A large amount of experience has been gained over 50 years in the design, construction and operation of small and medium nuclear power reactors. Historically, 100% of commercial reactors were in these categories in 1951-1960, reducing to 21% in 1991-2000. The technologies involved include pressurised water reactors, boiling water reactors, high temperature gas-cooled reactors, liquid metal reactors and molten salt reactors. Details will be provided of two of the most promising new designs, the South African Pebble Bed Modular Reactor (PBMR) of about 110 MWe, and the IRIS (International Reactor Innovative and Secure) reactor of about 335 MWe. Their construction costs are estimated to be about US$l,000/kWe with a generating cost for the PBMR of about US1.6c/kWh. These costs are lower than estimated for the latest designs of large reactors such as the European Pressurised Reactor (EPR) designed for 1,600 MWe for use in Europe in the next decade. It is concluded that a small or medium nuclear power reactor system built in modules to follow an increasing demand could be attractive for generating low cost electricity in many Australian states and reduce problems arising from air pollution and greenhouse gas emissions from burning fossil fuels

  9. Experimental fusion power reactor conceptual design study. Final report. Volume III

    International Nuclear Information System (INIS)

    Baker, C.C.

    1976-12-01

    This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following appendices: (1) tradeoff code analysis, (2) residual mode transport, (3) blanket/first wall design evaluations, (4) shielding design evaluation, (5) toroidal coil design evaluation, (6) E-coil design evaluation, (7) F-coil design evaluation, (8) plasma recycle system design evaluation, (9) primary coolant purification design evaluation, (10) power supply system design evaluation, (11) number of coolant loops, (12) power conversion system design evaluation, and (13) maintenance methods evaluation

  10. Study on Stochastic Optimal Electric Power Procurement Strategies with Uncertain Market Prices

    Science.gov (United States)

    Sakchai, Siripatanakulkhajorn; Saisho, Yuichi; Fujii, Yasumasa; Yamaji, Kenji

    The player in deregulated electricity markets can be categorized into three groups of GENCO (Generator Companies), TRNASCO (Transmission Companies), DISCO (Distribution Companies). This research focuses on the role of Distribution Companies, which purchase electricity from market at randomly fluctuating prices, and provide it to their customers at given fixed prices. Therefore Distribution companies have to take the risk stemming from price fluctuation of electricity instead of the customers. This entails the necessity to develop a certain method to make an optimal strategy for electricity procurement. In such a circumstance, this research has the purpose for proposing the mathematical method based on stochastic dynamic programming to evaluate the value of a long-term bilateral contract of electricity trade, and also a project of combination of the bilateral contract and power generation with their own generators for procuring electric power in deregulated market.

  11. Nuclear power within liberalised electricity markets

    International Nuclear Information System (INIS)

    Kidd, Stephen W.

    2002-01-01

    Competition between various methods of generating electricity in liberalised markets means that all power plants must be cost-effective. The price of electricity from nuclear power includes all waste disposal and decommissioning costs, unlike other electricity generating technologies. Most existing nuclear power plants are likely to prosper under electricity liberalization. Many will receive operating life extensions and be able to compete in the electricity market for many years to come. Investment costs are particularly heavy for nuclear plants. Capital expenditure appraisal methodologies mean that such plants suffer financial disadvantages in times of high interest rates. Low and stable fuel costs are the prime advantage of nuclear plants against other sources of generating electricity. There will be significant demand for new generating capacity, both incremental and replacement, in the next 20 years. Under present conditions, where there is access to a stable and cheap supply of piped gas, nuclear and coal plants find it difficult to compete against gas-fired plants. The nuclear industry is addressing the need for new reactor designs, offering significant capital and operating cost reductions from the previous generation of reactors. This development and the need for carbon abatement on a worldwide basis offers nuclear plants a further economic advantage against alternative technologies. (author)

  12. 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.

  13. Electric power monthly

    Energy Technology Data Exchange (ETDEWEB)

    Smith, Sandra R.; Johnson, Melvin; McClevey, Kenneth; Calopedis, Stephen; Bolden, Deborah

    1992-05-01

    The Electric Power Monthly is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), Department of Energy. This publication provides monthly statistics at the national, Census division, and State levels for net generation, fuel consumption, fuel stocks, quantity and quality of fuel, cost of fuel, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fuel are also displayed for the North American Electric Reliability Council (NERC) regions. Additionally, statistics by company and plant are published in the EPM on capability of new plants, new generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fuel.

  14. 78 FR 13097 - Electric Power Research Institute; Seismic Evaluation Guidance

    Science.gov (United States)

    2013-02-26

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0038] Electric Power Research Institute; Seismic... Electric Power Research Institute (EPRI)-1025287, ``Seismic Evaluation Guidance: Screening, Prioritization... guidance and clarification of an acceptable approach to assist nuclear power reactor licensees when...

  15. The power of British Energy

    International Nuclear Information System (INIS)

    Hawley, R.

    1997-01-01

    When the power industry in Britain was privatized, British Energy plc (BE), whose head office is in Edingburgh, Scotland, was founded in July 1996. It is the only power utility in the world exclusively operating nuclear power stations. Operative business has remained the responsibility of the two regional supply companies, Nuclear Electric (NE) and Scottish Nuclear (SN) which, in addition to the modern PWR nuclear generating unit of Sizewell B, have included in the new holding company their advanced gas-cooled and gas-moderated reactor (AGR) units. The older gas-graphite reactor (GGR) plants were combined in the new Magnox Electric plc, Berkeley; at some later date, this company is to be merged with another nuclear power plant operator, British Nuclear Fuels plc (BNFL). Sizewell B, which was commissioned in 1995, is the last nuclear generating unit to be started up in the United Kingdom, for the time being. In times of low raw material prices and the need for a quick return on invested capital, BE is reluctant to run the risk associated with tying up capital for a long time. Instead, the company has backfitted its plants so that the production of electricity from nuclear power in Britain in 1996 of 92,476 GWh was increased by almost 10% over the 1995 level of 84,174 GWh. In addition to modernization and rationalization at home, BE together with Sizewell B vendor Westinghouse is engaged worldwide in the development and commercialization of future advanced reactors. This ensures that the know-how accumulated will be preserved and will be available for new nuclear power plants to be built in Britain in the next century. (orig.)

  16. Remerschen nuclear power station with BBR pressurized water reactor

    International Nuclear Information System (INIS)

    Hoffmann, J.P.

    1975-01-01

    On the basis of many decades of successful cooperation in the electricity supply sector with the German RWE utility, the Grand Duchy of Luxemburg and RWE jointly founded Societe Luxembourgeoise d'Energie Nucleaire S.A. (SENU) in 1974 in which each of the partners holds a fifty percent interest. SENU is responsible for planning, building and operating this nuclear power station. Following an international invitation for bids on the delivery and turnkey construction of a nuclear power station, the consortium of the German companies of Brown, Boveri and Cie. AG (BBC), Babcock - Brown Boveri Reaktor GmbH (BBR) and Hochtief AG (HT) received a letter of intent for the purchase of a 1,300 MW nuclear power station equipped with a pressurized water reactor. The 1,300 MW station of Remerschen will be largely identical with the Muelheim-Kaerlich plant under construction by the same consortium near Coblence on the River Rhine since early 1975. According to present scheduling, the Remerschen nuclear power station could start operation in 1981. (orig.) [de

  17. Biomass utilization at Northern States Power Company

    International Nuclear Information System (INIS)

    Ellis, R.P.

    1994-01-01

    Northern States Power Company (open-quotes NSPclose quotes) generates, transmits and distributes electricity and distributes natural gas to customers in Minnesota, Wisconsin, North Dakota, South Dakota and Michigan. An important and growing component of the fuel needed to generate steam for electrical production is biomass. This paper describes NSP's historical use of biomass, current biomass resources and an overview of how NSP plans to expand its use of biomass in the future

  18. Safety Evaluation Report related to the operation of Wm. H. Zimmer Nuclear Power Station, Unit No. 1. Docket No. 50-358. Cincinnati Gas and Electric Company

    International Nuclear Information System (INIS)

    1982-08-01

    Information is presented concerning site characteristics; design criteria for structures, systems, and components; reactor; reactor coolant system and connected systems; engineered safety features; instrumentation and controls; electric power; auxiliary systems; conduct of operations; and TMI-2 requirements

  19. Nuclear power reactor safety

    International Nuclear Information System (INIS)

    Pon, G.A.

    1976-10-01

    This report is based on the Atomic Energy of Canada Limited submission to the Royal Commission on Electric Power Planning on the safety of CANDU reactors. It discusses normal operating conditions, postulated accident conditions, and safety systems. The release of radioactivity under normal and accident conditions is compared to the limits set by the Atomic Energy Control Regulations. (author)

  20. Fuel cells and electricity companies - new risk management opportunities

    International Nuclear Information System (INIS)

    Whale, M.

    2004-01-01

    'Full text:' Deregulation, distributed generation, combined heat and power, renewables, fuel cells, hydrogen. Power companies are facing a rapidly evolving environment that is testing their ability to effectively deploy capital and earn profits. While recent deregulation trends have shifted the structure of power markets into separating generators from distributors, the improving economic value proposition offered by smaller scale distributed generation technologies - such as fuel cells - would seem to be a conflicting development. In this complex and changing environment, decisions based on the economic reality of the capital markets are likely to prevail. By examining the opportunity to enhance risk management offered by stationary fuel cells, particularly in CHP applications, we provide a context for the issues being discussed in today's sessions focusing on power companies and electric utilities. Our risk management perspective suggests a pathway for implementing fuel cells in combined heat and power applications that large power generators can introduce in increasingly smaller sizes. With capital costs of fuel cells high and risk tolerance of power companies low, the challenge for smaller technology developers will be to reduce the apparently long time horizon that persists for substantial deployment. (author)

  1. Simulation of power plant construction in competitive Korean electricity market

    International Nuclear Information System (INIS)

    Ahn, Nam Sung; Huh, Sung Chul

    2001-01-01

    This paper describes the forecast of power plant construction in competitive Korean electricity market. In Korea, KEPCO (Korean Electric Power Corporation, fully controlled by government) was responsible for from the production of the electricity to the sale of electricity to customer. However, the generation part is separated from KEPCO and six generation companies were established for whole sale competition from April 1st, 2001. The generation companies consist of five fossil power companies and one nuclear power company. Fossil power companies are schedule to be sold to private companies including foreign investors. Nuclear power company is owned by government. The competition in generation market will start from 2003. ISO (Independence System Operator) will purchase the electricity from the power exchange market. The market price is determined by the SMP (System Marginal Price) which is decided by the balance between demand and supply of electricity in power exchange market. Under this uncertain circumstance, the energy policy planners are interested to the construction of the power plant in the future. These interests are accelerated due to the recent shortage of electricity supply in California. In the competitive market, investors are no longer interested in the investment for the capital intensive, long lead time generating technologies. Large nuclear and coal plants were no longer the top choices. Instead, investors in the competitive market are interested in smaller, more efficient, cheaper, cleaner technologies such as CCGT (Combined Cycle Gas Turbine). Electricity is treated as commodity in the competitive market. The investor's behavior in the commodity market shows that the new investment decision is made when the market price exceeds the sum of capital cost and variable cost of the new facility and the existing facility utilization depends on the marginal cost of the facility. This investor's behavior can be applied to the new investments for the

  2. Issues behind Radiation management of workers at Fukushima Nuclear Power Plant of Tokyo Electric Power Company. From the viewpoint of radiation exposure of the ocular lens and the biological effects to the lens

    International Nuclear Information System (INIS)

    Hayashida, Toshiyuki; Sasaki, Hiroshi; Hatsusaka, Natsuko; Hamada, Nobuyuki; Tatsuzaki, Hideo; Akahane, Keiichi; Yokoyama, Sumi

    2017-01-01

    In March 2011, the accident occurred at the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company. During recovery from critical situations, the radiation dose for some emergency workers exceeded the effective dose limit recommended for an emergency situation. A month after the accident, the International Commission on Radiological Protection issued a statement on tissue reactions recommending significant reduction of the equivalent dose limit to the lens of the eye. Many radiation workers will need to be involved in treatment of water contaminated with radionuclides, fuel debris retrieval, and decommissioning of reactors for a long period of time. Thus, the optimized radiation control in the fields, exposure reduction, prevention of tissue reactions, and reduction of stochastic risks for workers becomes necessary. This paper discusses issues in relation to radiation protection of the ocular lens in such recovery workers, from the viewpoint of radiation exposure of workers, its management, manifestations and mechanisms of the lens effects. (author)

  3. Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production

    Energy Technology Data Exchange (ETDEWEB)

    Mac Donald, Philip Elsworth; Buongiorno, Jacopo; Davis, Cliff Bybee; Weaver, Kevan Dean

    2002-01-01

    The use of supercritical temperature and pressure light water as the coolant in a direct-cycle nuclear reactor offers potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to 46%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type recirculation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If a tight fuel rod lattice is adopted, it is possible to significantly reduce the neutron moderation and attain fast neutron energy spectrum conditions. In this project a supercritical water reactor concept with a simple, blanket-free, pancake-shaped core will be developed. This type of core can make use of either fertile or fertile-free fuel and retain the hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity.

  4. Estimates of power requirements for a Manned Mars Rover powered by a nuclear reactor

    Science.gov (United States)

    Morley, Nicholas J.; El-Genk, Mohamed S.; Cataldo, Robert; Bloomfield, Harvey

    1991-01-01

    This paper assesses the power requirement for a Manned Mars Rover vehicle. Auxiliary power needs are fulfilled using a hybrid solar photovoltaic/regenerative fuel cell system, while the primary power needs are meet using an SP-100 type reactor. The primary electric power needs, which include 30-kW(e) net user power, depend on the reactor thermal power and the efficiency of the power conversion system. Results show that an SP-100 type reactor coupled to a Free Piston Stirling Engine yields the lowest total vehicle mass and lowest specific mass for the power system. The second lowest mass was for a SP-100 reactor coupled to a Closed Brayton Cycle using He/Xe as the working fluid. The specific mass of the nuclear reactor power system, including a man-rated radiation shield, ranged from 150-kg/kW(e) to 190-kg/KW(e) and the total mass of the Rover vehicle varied depend upon the cruising speed.

  5. Medium-Power Lead-Alloy Reactors: Missions for This Reactor Technology

    International Nuclear Information System (INIS)

    Todreas, Neil E.; MacDonald, Philip E.; Hejzlar, Pavel; Buongiorno, Jacopo; Loewen, Eric P.

    2004-01-01

    A multiyear project at the Idaho National Engineering and Environmental Laboratory and the Massachusetts Institute of Technology investigated the potential of medium-power lead-alloy-cooled technology to perform two missions: (1) the production of low-cost electricity and (2) the burning of actinides from light water reactor (LWR) spent fuel. The goal of achieving a high power level to enhance economic performance simultaneously with adoption of passive decay heat removal and modularity capabilities resulted in designs in the range of 600-800 MW(thermal), which we classify as a medium power level compared to the lower [∼100 MW(thermal)] and higher [2800 MW(thermal)] power ratings of other lead-alloy-cooled designs. The plant design that was developed shows promise of achieving all the Generation-IV goals for future nuclear energy systems: sustainable energy generation, low overnight capital cost, a very low likelihood and degree of core damage during any conceivable accident, and a proliferation-resistant fuel cycle. The reactor and fuel cycle designs that evolved to achieve these missions and goals resulted from study of the following key trade-offs: waste reduction versus reactor safety, waste reduction versus cost, and cost versus proliferation resistance. Secondary trade-offs that were also considered were monolithic versus modular design, active versus passive safety systems, forced versus natural circulation, alternative power conversion cycles, and lead versus lead-bismuth coolant.These studies led to a selection of a common modular design with forced convection cooling, passive decay heat removal, and a supercritical CO 2 power cycle for all our reactor concepts. However, the concepts adopt different core designs to optimize the achievement of the two missions. For the low-cost electricity production mission, a design approach based on fueling with low enriched uranium operating without costly reprocessing in a once-through cycle was pursued to achieve a

  6. Improving the taxation regime for electric power

    International Nuclear Information System (INIS)

    Fjermeros, Morten; Ilstad, Kristine

    2003-01-01

    In Norway, the present taxation regime for electric power is very complex. The power companies are currently charged with ordinary tax on profits, tax on economic rent, tax on natural resources and land tax. In addition there are the rules about licence fees, yield of power due to concession conditions, and reversion. The Norwegian Electricity Industry Association (EBL), assisted by a firm of lawyers, has proposed an improvement over the current taxation regime

  7. Preparing Canada's power systems for transition to the year 2000: the Y2K programs of Canada's electric utility companies: province-by-province report

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1999-09-01

    The province-by-province report covers BC Hydro; TransAlta, ATCO Ltd., EPCOR, and Enmax, SaskPower, Manitoba Hydro, Winnipeg Hydro, Ontario Power Generation, Ontario Hydro Services Company, Toronto Hydro, Hydro-Quebec and Energie Maclaren, Newfoundland and Labrador Hydro, Newfoundland Power, Nova Scotia Power, Maritime Electric,Yukon and Northwest Territories,Yukon Electrical Company Ltd., Northland Utilities (Yellowknife) Ltd. and Northland Utilities (NWT) Ltd. A report typically deals with inventory, testing and remediation of business systems, inventory, testing and remediation of operational control devices, business partner reviews, and preparation and exercising of contingency plans, as well as Y2K status and readiness reports, and dateline preparations.

  8. Procedure of determination of the nuclear reactor start-up power

    International Nuclear Information System (INIS)

    Brandt, K.D.; Griese, K.; Guehne, F.

    1985-01-01

    The invention has been aimed at a determination of the thermal reactor power during the start-up period and the commissioning resp. preferably under an extremely low thermal power in a range from 0.001 to 1%. In addition to it also the power range up to 100% shall be covered. The external gamma-ray flux density as a function of the thermal reactor power is measured in several overlapping partial measuring ranges. A suitable measuring device transforms the input signals into an electrically measured quantity proportional to the reactor power

  9. Pellet bed reactor for multi-modal space power

    International Nuclear Information System (INIS)

    Buden, D.; Williams, K.; Mast, P.; Mims, J.

    1987-01-01

    A review of forthcoming space power needs for both civil and military missions indicates that power requirements will be in the tens of megawatts. The electrical power requirements are envisioned to be twofold: long-duration lower power levels will be needed for station keeping, communications, and/or surveillance; short-duration higher power levels will be required for pulsed power devices. These power characteristics led to the proposal of a multi-modal space power reactor using a pellet bed design. Characteristics desired for such a multimegawatt reactor power source are standby, alert, and pulsed power modes; high-thermal output heat source (approximately 1000 MWt peak power); long lifetime station keeping power (10 to 30 years); high temperature output (1500 K to 1800 K); rapid-burst power transition; high reliability (above 95 percent); and stringent safety standards compliance. The proposed pellet bed reactor is designed to satisfy these characteristics

  10. Design of reactor protection systems for HTR plants generating electric power and process heat problems and solutions

    International Nuclear Information System (INIS)

    Craemer, B.; Dahm, H.; Spillekothen, H.G.

    1982-06-01

    The design basis of the reactor protection system (RPS) for HTR plants generating process heat and electric power is briefly described and some particularities of process heat plants are indicated. Some particularly important or exacting technical measuring positions for the RPS of a process heat HTR with 500 MWsub(th) power (PNP 500) are described and current R + D work explained. It is demonstrated that a particularly simple RPS can be realized in an HTR with modular design. (author)

  11. Characteristics and economy of the European reactor of pressurized water (EPR); Caracteristicas y economia del reactor europeo de agua a presion (EPR)

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz V, J.; Ramirez S, J.R.; Palacios H, J.C. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: jov@nuclear.inin.mx

    2005-07-01

    The high current costs of the fossil fuels, have propitiated that the industries of electric power generation in the world reconsider the nuclear option as medium of generation. In Europe, the more recently contracted nuclear power plant is that of Olkiluoto-III in Finland that waits it enters in operation at the end of 2009. The reactor that will be installed in this power plant will be a prototype of pressurized water reactor of the companies AREVA and EDF. In this work they are described the reactor EPR and the major components of the nuclear power plant as well as the main characteristics of safety and the flexibility of the operation of the EPR. The supposed costs reported in different sources of information are also described and calculated with information provided by the manufacturer company. (Author)

  12. The business for power : hydro-electricity in southeastern British Columbia 1897-1997

    International Nuclear Information System (INIS)

    Mouat, J.

    1997-01-01

    The evolution and development of the hydroelectric power industry in southeastern British Columbia was chronicled by recounting the first hundred years of the West Kootenay Power and Light Electrical Utility. The utility's first generator produced electricity in the summer of 1898 when hydro-electric companies were a new phenomenon. The factors behind the success of the company, the personalities of the promoters and entrepreneurs that launched the company, the complex interplay of unique events and the social and political context that illustrate a fascinating process in which electricity became an integral part of everyday life, are described. Refs., tabs., figs

  13. Preparing Canada`s power systems for transition to the Year 2000: Y2K readiness assessment results for Canadian electric utility companies: second quarter 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-08-25

    The report describes the state of readiness of Canadian electric utility companies with respect to the Year 2000 computer challenge. It complements the North American Electric Reliability Council Report entitled `Preparing the Electric Power Systems of North America for Transition to the Year 2000: A Status and Work Plan.` Two surveys were employed to gather information for this report. The first, a detailed survey prepared by NERC, was forwarded to all major electric utilities that comprise the Bulk Electricity System in North America. CEA has removed the Canadian findings from the overall North American results, and has presented those findings in this report. The second was a shorter, more simplified study, conducted by CEA and Natural Resources Canada. Whereas small companies involved only in the distribution aspect of the electricity business were not asked to complete the NERC assessment, all Canadian electric utility companies were part of the shorter survey. Chapter 2 covers specifically the readiness status and project management for non-nuclear generation, nuclear generation, energy management systems, telecommunications systems, substation controls, system protection and distribution systems, business information systems, and small distribution companies.

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

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  15. Plant maintenance and advanced reactors, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-09-15

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Advanced plants to meet rising expectations, by John Cleveland, International Atomic Energy Agency, Vienna; A flexible and economic small reactor, by Mario D. Carelli and Bojan Petrovic, Westinghouse Electric Company; A simple and passively safe reactor, by Yury N. Kuznetsov, Research and Development Institute of Power Engineering (NIKIET), Russia; Gas-cooled reactors, by Jeffrey S. Merrifield, U.S. Nuclear Regulatory Commission; ISI project managment in the PRC, by Chen Chanbing, RINPO, China; and, Fort Calhoun refurbishment, by Sudesh Cambhir, Omaha Public Power District.

  16. Space reactor electric systems: system integration studies, Phase 1 report

    International Nuclear Information System (INIS)

    Anderson, R.V.; Bost, D.; Determan, W.R.; Harty, R.B.; Katz, B.; Keshishian, V.; Lillie, A.F.; Thomson, W.B.

    1983-01-01

    This report presents the results of preliminary space reactor electric system integration studies performed by Rockwell International's Energy Systems Group (ESG). The preliminary studies investigated a broad range of reactor electric system concepts for powers of 25 and 100 KWe. The purpose of the studies was to provide timely system information of suitable accuracy to support ongoing mission planning activities. The preliminary system studies were performed by assembling the five different subsystems that are used in a system: the reactor, the shielding, the primary heat transport, the power conversion-processing, and the heat rejection subsystems. The subsystem data in this report were largely based on Rockwell's recently prepared Subsystem Technology Assessment Report. Nine generic types of reactor subsystems were used in these system studies. Several levels of technology were used for each type of reactor subsystem. Seven generic types of power conversion-processing subsystems were used, and several levels of technology were again used for each type. In addition, various types and levels of technology were used for the shielding, primary heat transport, and heat rejection subsystems. A total of 60 systems were studied

  17. Safe nuclear power for the Third World

    International Nuclear Information System (INIS)

    Johnson, W.R.; Lyon, C.F.; Redick, J.R.

    1989-01-01

    It is clear that using nuclear power for the generation of electricity is one way of reducing the emissions of CO 2 and other gases that contribute to the greenhouse effect. Equally clear is the fact that the reduction can be magnified by converting domestic, commercial, and industrial power-consuming activities from the direct use of fossil fuel sources to electrical energy. A major area for future progress in limiting CO 2 emissions is in the Third World, where population growth and expectations for a higher social and economic standard of living portend vast increases in future energy use. A number of problems come to mind as one contemplates the widespread expansion of nuclear energy use into the Third World. The authors propose a method involving the marriage of two currently evolving concepts by which nuclear electrical generation can be expanded throughout the world in a manner that will address these problems. The idea is to form multinational independent electric generating companies, or nuclear electric companies (NECs), that would design, build, operate, and service a standardized fleet of nuclear power plants. The plants would be of the Integral Fast Reactor (IFR) design, now under development at Argonne National Laboratory, and, in particular, a commercial conceptualization of the IFR sponsored by General Electric Company, the Power Reactor Inherently Safe Module (PRISM)

  18. Electrical power systems for Mars

    Science.gov (United States)

    Giudici, Robert J.

    1986-01-01

    Electrical power system options for Mars Manned Modules and Mars Surface Bases were evaluated for both near-term and advanced performance potential. The power system options investigated for the Mission Modules include photovoltaics, solar thermal, nuclear reactor, and isotope power systems. Options discussed for Mars Bases include the above options with the addition of a brief discussion of open loop energy conversion of Mars resources, including utilization of wind, subsurface thermal gradients, and super oxides. Electrical power requirements for Mission Modules were estimated for three basic approaches: as a function of crew size; as a function of electric propulsion; and as a function of transmission of power from an orbiter to the surface of Mars via laser or radio frequency. Mars Base power requirements were assumed to be determined by production facilities that make resources available for follow-on missions leading to the establishment of a permanently manned Base. Requirements include the production of buffer gas and propellant production plants.

  19. Power Reactor Embrittlement Data Base

    International Nuclear Information System (INIS)

    Kam, F.B.K.; Stallmann, F.W.; Wang, J.A.

    1990-01-01

    Regulatory and research evaluations of embrittlement predication models and of pressure vessel integrity can be greatly expedited by the use of a well-designed, computerized data base. The Power Reactor Embrittlement Data Base (PR-EDB) is such a comprehensive collection of data for US commercial nuclear reactors. The Nuclear Regulatory Commission (NRC) has provided financial support, and the Electric Power Research Institute (EPRI) has provided technical assistance in the quality assurance (QA) of the data to establish an industry-wide data base that will be maintained and updated on a long-term basis. Successful applications of the data base to several of NRC's evaluations have received favorable response and support for its continuation. The future direction of the data base has been designed to include the test reactor and other types of data of interest to the regulators and the researchers. 1 ref

  20. Mirror reactor studies

    International Nuclear Information System (INIS)

    Moir, R.W.; Barr, W.L.; Bender, D.J.

    1977-01-01

    Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80%. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59% and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high re-circulating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)]. By contrast, the fusion-fission reactor design is not penalized by re-circulating power and uses relatively near-term fusion technology being developed for the fusion power program. New results are presented on the Th- 233 U and the U- 239 Pu fuel cycles. The purpose of this hybrid is fuel production, with projected costs at $55/g of Pu or $127/g of 233 U. Blanket and cooling system designs, including an emergency cooling system, by General Atomic Company, lead us to the opinion that the reactor can meet expected safety standards for licensing. The smallest mirror reactor having only a shield between the plasma and the coil is the 4.2-m long fusion engineering research facility (FERF) designed for material irradiation. The smallest mirror reactor having both a blanket and shield is the 7.5-m long experimental power reactor (EPR), which has both a fusion and a fusion-fission version. (author)

  1. Wireless power transfer for electric vehicle

    OpenAIRE

    Mude, Kishore Naik

    2015-01-01

    Wireless Power Transfer (WPT) systems transfer electric energy from a source to a load without any wired connection. WPTs are attractive for many industrial applications because of their advantages compared to the wired counterpart, such as no exposed wires, ease of charging, and fearless transmission of power in adverse environmental conditions. Adoption of WPTs to charge the on-board batteries of an electric vehicle (EV) has got attention from some companies, and efforts are being made for ...

  2. Estimation, comparison, and evaluation of advanced fission power reactor generation costs

    International Nuclear Information System (INIS)

    Waddell, J.D.

    1977-01-01

    The study compares the high-temperature gas-cooled reactor (HTGR), the gas-cooled fast reactor (GCFR), the molten-salt breeder reactor (MSBR), the light water breeder reactor (LWBR), and the heavy water reactor (HWR) with proposed light water reactors (LWR) and liquid-metal fast breeder reactors (LMFBR). The relative electrical generation costs, including the effects of the introduction of advanced reactor fuel cycles into the U.S. nuclear power economy, were projected through the year 2030. The study utilized the NEEDS computer code which is a simulation of the U.S. nuclear power economy. The future potential electrical generation costs and cumulative consumption of uranium ore were developed using characterizations of the advanced systems. The reactor-fuel cycle characterizations were developed from literature reviews and personal discussions with the proponents of the various systems. The study developed a ranking of the concepts based on generation costs and uranium consumption

  3. Design criteria for the electrical system in advanced passive reactors. Special features of the AP-600 Reactor

    International Nuclear Information System (INIS)

    Moraleda Lopez, A.

    1997-01-01

    The design of the electrical system of an Passive Advanced Reactor is determined by the concept of passive actuation of safety systems, simplification of process systems and optimisation of equipment performance. The system that results from these criteria is very different to those designed for present plants. The main differences are: No class 1E alternating current systems No emergency diesel generators Fewer safety and non-safety class electricity consumers System for continuous monitoring of battery status Use of electronic speed regulators for reactor feedwater pump motors Outsite battery backup safety power supply Motor-operated valves are the only safety electrical actuators Portable power supply for post 72 hour equipment This paper develops these concepts and applies them to the AP-600 project and describes the electrical system of this type of plant. (Author)

  4. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    2010-03-01

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  5. MODERN ELECTRIC CARS OF TESLA MOTORS COMPANY

    Directory of Open Access Journals (Sweden)

    O. F. Vynakov

    2016-08-01

    Full Text Available This overview article shows the advantages of a modern electric car as compared with internal combustion cars by the example of the electric vehicles of Tesla Motors Company. It (в смысле- статья describes the history of this firm, provides technical and tactical characteristics of three modifications of electric vehicles produced by Tesla Motors. Modern electric cars are not less powerful than cars with combustion engines both in speed and acceleration amount. They are reliable, economical and safe in operation. With every year the maximum range of an electric car is increasing and its battery charging time is decreasing.Solving the problem of environmental safety, the governments of most countries are trying to encourage people to switch to electric cars by creating subsidy programs, lending and abolition of taxation. Therefore, the advent of an electric vehicle in all major cities of the world is inevitable.

  6. Framatome advanced nuclear power-benefits for our clients from the new company

    International Nuclear Information System (INIS)

    Weber, P.

    2001-01-01

    Framatome ANP (Advanced Nuclear Power) merges the complementary strengths of two global nuclear industry leaders Framatome and Siemens - offering clients the best technological solutions for safe, reliable and economical plant performance. With a combined workforce of 13,300 skilled individuals, Framatome ANP is now the nuclear industry's leading supplier. Serving as Original Equipment Manufacturer (OEM) for more than 90 reactors that provide about 30% of the world's total installed nuclear power capacity, our experienced resources remain focused on the local needs of individual clients, wherever in the world they may be. The Company main business used to be turnkey construction of complete Nuclear Power plants, BWR and PWR capabilities, heavy equipment manufacturing, comprehensive I and C capabilities, and also expertise and knowledge of VVER. Framatome ANP will benefit in all of its fields of activity of the experience gained through Framatome and Siemens' collaboration on the next generation reactor, the EPR, as well as on steam generators replacements and or modernization of VVER. Framatome ANP nuclear fuel designs for both PWR and BWR plants provide innovative features and world-leading performance. Framatome ANP is organized according a matrix organization with: - 4 Business Groups (Project and Engineering, Service, Nuclear Fuel, Mechanical Equipment) - 3 Regional Divisions (Framatome Advanced Nuclear Power S.A.S., France; Framatome Advanced Nuclear Power GmbH, Germany; Framatome Advanced Nuclear Power Inc., USA). By 30th January 2001 Siemens Nuclear Power GmbH, founded in 2000 as successor of the Nuclear Division of Siemens Power Generation Group (KWU), was renamed to Framatome Advanced Nuclear Power GmbH forming the German part of the world wide acting company. Over the past 40 years 23 nuclear power plants all around the world - not only pressurized and boiling water reactors, but also two heavy-watermoderated reactors have been designed, constructed and

  7. A gas-cooled reactor surface power system

    International Nuclear Information System (INIS)

    Lipinski, R.J.; Wright, S.A.; Lenard, R.X.; Harms, G.A.

    1999-01-01

    A human outpost on Mars requires plentiful power to assure survival of the astronauts. Anywhere from 50 to 500 kW of electric power (kWe) will be needed, depending on the number of astronauts, level of scientific activity, and life-cycle closure desired. This paper describes a 250-kWe power system based on a gas-cooled nuclear reactor with a recuperated closed Brayton cycle conversion system. The design draws upon the extensive data and engineering experience developed under the various high-temperature gas cooled reactor programs and under the SP-100 program. The reactor core is similar in power and size to the research reactors found on numerous university campuses. The fuel is uranium nitride clad in Nb1%Zr, which has been extensively tested under the SP-100 program. The fuel rods are arranged in a hexagonal array within a BeO block. The BeO softens the spectrum, allowing better use of the fuel and stabilizing the geometry against deformation during impact or other loadings. The system has a negative temperature feedback coefficient so that the power level will automatically follow a variable load without the need for continuous adjustment of control elements. Waste heat is removed by an air-cooled heat exchanger using cold Martian air. The amount of radioactivity in the reactor at launch is very small (less than a Curie, and about equal to a truckload of uranium ore). The system will need to be engineered so that criticality can not occur for any launch accident. This system is also adaptable for electric propulsion or life-support during transit to and from Mars. copyright 1999 American Institute of Physics

  8. A gas-cooled reactor surface power system

    International Nuclear Information System (INIS)

    Lipinski, Ronald J.; Wright, Steven A.; Lenard, Roger X.; Harms, Gary A.

    1999-01-01

    A human outpost on Mars requires plentiful power to assure survival of the astronauts. Anywhere from 50 to 500 kW of electric power (kWe) will be needed, depending on the number of astronauts, level of scientific activity, and life-cycle closure desired. This paper describes a 250-kWe power system based on a gas-cooled nuclear reactor with a recuperated closed Brayton cycle conversion system. The design draws upon the extensive data and engineering experience developed under the various high-temperature gas cooled reactor programs and under the SP-100 program. The reactor core is similar in power and size to the research reactors found on numerous university campuses. The fuel is uranium nitride clad in Nb1%Zr, which has been extensively tested under the SP-100 program. The fuel rods are arranged in a hexagonal array within a BeO block. The BeO softens the spectrum, allowing better use of the fuel and stabilizing the geometry against deformation during impact or other loadings. The system has a negative temperature feedback coefficient so that the power level will automatically follow a variable load without the need for continuous adjustment of control elements. Waste heat is removed by an air-cooled heat exchanger using cold Martian air. The amount of radioactivity in the reactor at launch is very small (less than a Curie, and about equal to a truckload of uranium ore). The system will need to be engineered so that criticality can not occur for any launch accident. This system is also adaptable for electric propulsion or life-support during transit to and from Mars

  9. A Gas-Cooled Reactor Surface Power System

    Energy Technology Data Exchange (ETDEWEB)

    Harms, G.A.; Lenard, R.X.; Lipinski, R.J.; Wright, S.A.

    1998-11-09

    A human outpost on Mars requires plentiful power to assure survival of the astronauts. Anywhere from 50 to 500 kW of electric power (kWe) will be needed, depending on the number of astronauts, level of scientific activity, and life- cycle closure desired. This paper describes a 250-kWe power system based on a gas-cooled nuclear reactor with a recuperated closed Brayton cycle conversion system. The design draws upon the extensive data and engineering experience developed under the various high-temperature gas cooled reactor programs and under the SP-100 program. The reactor core is similar in power and size to the research reactors found on numerous university campuses. The fuel is uranium nitide clad in Nb 1 %Zr, which has been extensively tested under the SP-I 00 program The fiel rods are arranged in a hexagonal array within a BeO block. The BeO softens the spectrum, allowing better use of the fbel and stabilizing the geometty against deformation during impact or other loadings. The system has a negative temperature feedback coefficient so that the power level will automatically follow a variable load without the need for continuous adjustment of control elements. Waste heat is removed by an air-cooled heat exchanger using cold Martian air. The amount of radioactivity in the reactor at launch is very small (less than a Curie, and about equal to a truckload of uranium ore). The system will need to be engineered so that criticality cannot occur for any launch accident. This system is also adaptable for electric propulsion or life-support during transit to and from Mars.

  10. The Relationship Between Electricity Price and Wind Power Generation in Danish Electricity Markets

    DEFF Research Database (Denmark)

    Hu, Weihao; Chen, Zhe; Bak-Jensen, Birgitte

    2010-01-01

    of competitive electricity markets in some ways, is chosen as the studied power system. The relationship between the electricity price (both the spot price and the regulation price) and the wind power generation in an electricity market is investigated in this paper. The spot price, the down regulation price...... and the up regulation price generally decreases when the wind power penetration in the power system increases. The statistical characteristics of the spot price for different wind power penetration are analyzed. The findings of this paper may be useful for wind power generation companies to make the optimal...... bidding strategy and may be also useful for the optimal operation of modern power systems with high wind power penetrations....

  11. Power programmes review: Nuclear power in Italy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    Several concrete measures have been initiated in Italy for the generation of nuclear power on a substantial scale. Two plants are already under construction and work will start soon on a third. Plans have also been announced for more stations. If the work already initiated is completed on schedule the installed capacity of nuclear power in Italy is likely to exceed 500 mw (electric) in the course of the next four years. This will constitute a sizeable proportion of the total electrical capacity in the country. After the Italian National Committee for Nuclear Research (Comitato Nazionale per le Ricerche Nucleari) was reorganized late in 1956, it prepared what can be described as a nuclear five-year plan for Italy. The plan, designed to cover the period 1957-1962, includes detailed schemes for a comprehensive development of the peaceful uses of nuclear energy, including a programme for the generation of power. The Comitato Nazionale per le Ricerche Nucleari (CNRN) promotes and co-ordinates the various activities in the field, and within the framework of its general programme certain industrial groups in Italy have formulated specific projects for nuclear power. At a Geneva conference (1958) it was disclosed that several companies were planning to build nuclear power stations in Italy. (1) SELNI (Societa Elettronucleare Italiana), pertaining to the Edison-Volta group, which plans to build a pressurized water reactor. (2) So.R.I.N. (Societa Ricerche Impianti Nucleari), a company founded by the Fiat and Montecatini groups, which is constructing a research centre, with a swimming pool reactor, and various laboratories for chemistry, physics and metallurgy. This centre will also be used for the training of specialized personnel, in view of the company's programme which envisages two 150 mw (e) plants: one operating with enriched uranium, the other with natural uranium. Such a programme will become effective only when the cost of power produced by these plants may actually

  12. Advances in ICF power reactor design

    International Nuclear Information System (INIS)

    Hogan, W.J.; Kulcinski, G.L.

    1985-01-01

    Fifteen ICF power reactor design studies published since 1980 are reviewed to illuminate the design trends they represent. There is a clear, continuing trend toward making ICF reactors inherently safer and environmentally benign. Since this trend accentuates inherent advantages of ICF reactors, we expect it to be further emphasized in the future. An emphasis on economic competitiveness appears to be a somewhat newer trend. Lower cost of electricity, smaller initial size (and capital cost), and more affordable development paths are three of the issues being addressed with new studies

  13. Tokamak experimental power reactor

    International Nuclear Information System (INIS)

    Stacey, W.M. Jr.; Abdou, M.A.; Brooks, J.N.

    1978-01-01

    A tokamak experimental power reactor has been designed that is capable of producing net electric power over a wide range of possible operating conditions. A net production of 81 MW of electricity is expected from the design reference conditions that assume a value of 0.07 for beta-toroidal, a maximum toroidal magnetic field of 9 T and a thermal conversion efficiency of 30%. Impurity control is achieved through the use of a low-Z first wall coating. This approach allows a burn time of 60 seconds without the incorporation of a divertor. The system is cooled by a dual pressurized water/steam system that could potentially provide thermal efficiencies as high as 39%. The first surface facing the plasma is a low-Z coated water cooled panel that is attached to a 20 cm thick blanket module. The vacuum boundary is removed a total of 22 cm from the plasma, thereby minimizing the amount of radiation damage in this vital component. Consideration is given in the design to the possible use of the EPR as a materials test reactor. It is estimated that the total system could be built for less than 550 million dollars

  14. Safety of power transformers, power supplies, reactors and similar products - Part 1: General requirements and tests

    CERN Document Server

    International Electrotechnical Commission. Geneva

    1998-01-01

    This International Standard deals with safety aspects of power transformers, power supplies, reactors and similar products such as electrical, thermal and mechanical safety. This standard covers the following types of dry-type transformers, power supplies, including switch mode power supplies, and reactors, the windings of which may be encapsulated or non-encapsulated. It has the status of a group safety publication in accordance with IEC Guide 104.

  15. Total quality control: the deming management philosophy applied to nuclear power plants

    International Nuclear Information System (INIS)

    Heising, C.D.; Wetherell, D.L.; Melhem, S.A.; Sato, M.

    1987-01-01

    In recent years, a call has come for the development of inherently safe nuclear reactor systems that cannot have large-scale accidents. In the search for the perfect inherently safe reactor system, some are calling for the institution of computerized automated control of reactors eliminating most human operators from the control room. A different approach to the problem of the control of inherently safe reactors is that both future and present nuclear power plants need to institute total quality control (TQC) to plant operations and management. The Deming management philosophy of TQC has been implemented in a wide range of industries - particularly in Japan and the US. Specific attention is given, however, to TQC implementation in the electric power industry as applied to nuclear plants. The Kansai Electric Power Company and Florida Power and Light Company have recently implemented TQC. Statistical quality control methods have been applied to monitor and control reactor variables (for example, to the steam generator water level important to start-up operations of pressurized water reactors)

  16. The control of emissions from nuclear power reactors in Canada

    International Nuclear Information System (INIS)

    Gorman, D.J.; Neil, B.C.J.; Chatterjee, R.M.

    1988-01-01

    Nuclear power reactors in Canada are of the CANDU pressurised heavy water design. These are located in the provinces of Ontario, Quebec, and New Brunswick. Most of the nuclear generating capacity is in the province of Ontario which has 16 commissioned reactors with a total capacity of 11,500 MWe. There are four reactors under construction with an additional capacity of 3400 MWe. Nuclear power currently accounts for approximately 50% of the electrical power generation of Ontario. Regulation of the reactors is a Federal Government responsibility administered by the Atomic Energy Control Board (AECB) which licenses the reactors and sets occupational and public dose limits

  17. Electric power monthly

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    The Energy Information Administration (EIA) prepares the Electric Power Monthly (EPM) for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. This publication provides monthly statistics for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. The EIA publishes statistics in the EPM on net generation by energy source, consumption, stocks, quantity, quality, and cost of fossil fuels; and capability of new generating units by company and plant. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead.

  18. The roles played by the Canadian General Electric Company's Atomic Power Department in Canada's nuclear power program: work, organization and success in APD, 1955-1995

    International Nuclear Information System (INIS)

    Cantello, G.W.

    2003-01-01

    This thesis explores the roles played by the Canadian General Electric Company's Atomic Power Department (APD) in Canada's distinctive nuclear power program. From the establishment of APD in 1955 until the completion of the KANUPP project in Pakistan in 1972, the company's strategy encompassed the design, manufacture, and commissioning of entire nuclear power projects in Canada and abroad. APD then developed a specialized role in the design and supply of complete nuclear fuel handling systems, nuclear fuel bundles, and service work, that sustained a thriving workplace. Five key factors are identified as the reasons behind the long and successful history of the department: (1) Strong, capable and efficient management from the start, (2) Flexible organizational structure, (3) Extremely competent design group, (4) Excellent manufacturing, test, commissioning and service capabilities, (5) Correctly identifying, at the right time, the best fields in which to specialize. (author)

  19. Medium-size high-temperature gas-cooled reactor

    International Nuclear Information System (INIS)

    Peinado, C.O.; Koutz, S.L.

    1980-08-01

    This report summarizes high-temperature gas-cooled reactor (HTGR) experience for the 40-MW(e) Peach Bottom Nuclear Generating Station of Philadelphia Electric Company and the 330-MW(e) Fort St. Vrain Nuclear Generating Station of the Public Service Company of Colorado. Both reactors are graphite moderated and helium cooled, operating at approx. 760 0 C (1400 0 F) and using the uranium/thorium fuel cycle. The plants have demonstrated the inherent safety characteristics, the low activation of components, and the high efficiency associated with the HTGR concept. This experience has been translated into the conceptual design of a medium-sized 1170-MW(t) HTGR for generation of 450 MW of electric power. The concept incorporates inherent HTGR safety characteristics [a multiply redundant prestressed concrete reactor vessel (PCRV), a graphite core, and an inert single-phase coolant] and engineered safety features

  20. How is Electricity Generated from Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lajnef, D.

    2015-01-01

    Nuclear power is a proven, safe and clean source of power generation. A nuclear power plant is a thermal power station in which the heat source is a nuclear reactor. As is typical in all conventional thermal power stations the heat is used to generate steam which drives a steam turbine: the energy released from continuous fission of the atoms of the fuel is harnessed as heat in either a gas or water, and is used to produce steam. Nuclear Reactors are classified by several methods. It can be classified by type of nuclear reaction, by the moderator material, by coolant or by generation. There are several components common to most types of reactors: fuel, moderator, control rods, coolant, and containment. Nuclear reactor technology has been under continuous development since the first commercial exploitation of civil nuclear power in the 1950s. We can mention seven key reactor attributes that illuminate the essential differences between the various generations of reactors: cost effectiveness, safety, security and non-proliferation, fuel cycle, grid appropriateness and Economics. Today there are about 437 nuclear power reactors that are used to generate electricity in about 30 countries around the world. (author)

  1. The recent activities of nuclear power globalization. Our provision against global warming by global deployment of our own technologies as integrated nuclear power plant supply company'

    International Nuclear Information System (INIS)

    Yamauchi, Kiyoshi; Suzuki, Shigemitsu

    2008-01-01

    Mitsubishi Heavy Industries, Ltd. (MHI) is striving to expand and spread nuclear power plants as an 'Integrated Nuclear Power Plant Supply Company' based on its engineering, manufacturing, and technological support capabilities. The company also has ample experience in the export of major components. MHI is accelerating its global deployment through the market introduction of large-sized strategic reactor US-APWR, the joint development of a mid-sized strategic reactor ATMEA1 with AREVA, and a small strategic reactor PBMR. The company also plans to internationally deploy technologies for the nuclear fuel cycle. We present here the leading-edge trends in the global deployment of these nuclear businesses, all of which help to solve the energy and environmental issues in the world. (author)

  2. Electric failure on the reactor n.3 of the nuclear power plant of Dampierre

    International Nuclear Information System (INIS)

    2007-05-01

    This note of information resumes the progress of the electric failure on the reactor n.3 of the nuclear power plant of Dampierre, the organization during the incident, it establishes then a comparison with the incident arisen to Forsmark in 2006 and reminds that it lead in an inspection on behalf of the Asn which noticed that all the procedures had been respected by the operators and did not noticed any abnormality in the maintenance. This event was classified at the level 1 of the international nuclear event scale (INES). (N.C.)

  3. Electric power annual 1995. Volume I

    International Nuclear Information System (INIS)

    1996-07-01

    The Electric Power Annual presents a summary of electric power industry statistics at national, regional, and State levels. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts, and the general public with data that may be used in understanding U.S. electricity markets. The Electric Power Annual is prepared by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy. In the private sector, the majority of the users of the Electric Power Annual are researchers and analysts and, ultimately, individuals with policy- and decisionmaking responsibilities in electric utility companies. Financial and investment institutions, economic development organizations interested in new power plant construction, special interest groups, lobbyists, electric power associations, and the news media will find data in the Electric Power Annual useful. In the public sector, users include analysts, researchers, statisticians, and other professionals with regulatory, policy, and program responsibilities for Federal, State, and local governments. The Congress and other legislative bodies may also be interested in general trends related to electricity at State and national levels. Much of the data in these reports can be used in analytic studies to evaluate new legislation. Public service commissions and other special government groups share an interest in State-level statistics. These groups can also compare the statistics for their States with those of other jurisdictions

  4. Design requirement for electrical system of an advanced research reactor

    International Nuclear Information System (INIS)

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

    2004-12-01

    An advanced research reactor is being designed since 2002 and the conceptual design has been completed this year for the several types of core. Also the fuel was designed for the potential cores. But the process system, the I and C system, and the electrical system design are under pre-conceptual stage. The conceptual design for those systems will be developed in the next year. Design requirements for the electrical system set up to develop conceptual design. The same goals as reactor design - enhance safety, reliability, economy, were applied for the development of the requirements. Also the experience of HANARO design and operation was based on. The design requirements for the power distribution, standby power supply, and raceway system will be used for the conceptual design of electrical system

  5. Design requirement for electrical system of an advanced research reactor

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-12-01

    An advanced research reactor is being designed since 2002 and the conceptual design has been completed this year for the several types of core. Also the fuel was designed for the potential cores. But the process system, the I and C system, and the electrical system design are under pre-conceptual stage. The conceptual design for those systems will be developed in the next year. Design requirements for the electrical system set up to develop conceptual design. The same goals as reactor design - enhance safety, reliability, economy, were applied for the development of the requirements. Also the experience of HANARO design and operation was based on. The design requirements for the power distribution, standby power supply, and raceway system will be used for the conceptual design of electrical system.

  6. Control of operational transients in power reactors - Methodology

    International Nuclear Information System (INIS)

    Vukovic, D.

    1983-01-01

    By introducing the nuclear power stations in the electric power system, questions of their possibilities to satisfy system's demand arise. Control of operational transients (temperature and Xe 135 ) in power reactors by determining the optimal control rod strategy is given. Ti optimize the Xe 135 transients, the Pantryagin theorem of optimal processes is applied. For solving three dimensional, two-group diffusion equations the heterogeneous Feinberg-Galanin method with axial flux harmonics is adopted. An application of this formalism to three-dimensional, finite cylindrical pressurised water reactor radially reflected is presented. (author)

  7. Broadband internet connection utilizing electric power cables, v. 16(61)

    International Nuclear Information System (INIS)

    Plastinovski, Jovche

    2008-01-01

    Considering the introduction of wide spread communication, once again, pay our attention to the oldest network in Macedonia(and world wide)- the electrical network. Being widespread, it can make the broadband communication available from any place that has an electrical connection. This includes the rural areas, which the commercial companies are not interested in. Since the early 80-ties the big power companies have realized the potential of the use electric network for communication. its beginning had faced with difficulties, since in order to send data via the noisy interferes with other units such as the radio and military equipment. But nowadays these obstacles are more or lass overcame. Some of the companies are using BPL (broadband power lines) communication for their daily operations, while in the same time this relatively new technology for data transfer over power lines is under heavy developing. (Author)

  8. Broadband internet connection utilizing electric power cables, v. 16(62)

    International Nuclear Information System (INIS)

    Plastinovski, Jovche

    2008-01-01

    Considering the introduction of wide spread communication, once again, pay our attention to the oldest network in Macedonia(and world wide)- the electrical network. Being widespread, it can make the broadband communication available from any place that has an electrical connection. This includes the rural areas, which the commercial companies are not interested in. Since the early 80-ties the big power companies have realized the potential of the use electric network for communication. its beginning had faced with difficulties, since in order to send data via the noisy interferes with other units such as the radio and military equipment. But nowadays these obstacles are more or lass overcame. Some of the companies are using BPL (broadband power lines) communication for their daily operations, while in the same time this relatively new technology for data transfer over power lines is under heavy developing. (Author)

  9. Study on regimes of nuclear power plants with WWER-type reactors

    International Nuclear Information System (INIS)

    Akkerman, G.; Khampel', R.; Khentshel', G.; Kertsher, F.; Lyuttsov, K.

    1976-01-01

    The problems are considered of optimization of nuclear fuel loading, the peculiarities of the NPP operation at decreased power, and also the problem of stability operation of NPP with WWER type reactors taking into account specific features of these reactors (partial fuel overloads, change in reactor reactivity with power changes). The two particular interconnected problems discussed are: choice of such a sequence of partial rechargings which ensures the minimum cost of the electric power generated, and increasing the reactor operating time by reducing its power output. Besides the technical and economic estimates, much attention is given to analysing the stability of NPP operation

  10. Electrical supervisory control and data acquisition system for Power Reactor Fuel Reprocessing Facility (PREFRE-II) at Tarapur

    International Nuclear Information System (INIS)

    Singh, V.K.; Kaushik, S.; Haneef, K.K.M.

    2014-01-01

    Power Reactor Fuel Reprocessing Facility (PREFRE II) is a radio-chemical plant located at Tarapur. The electric power supply to PREFRE-II plant has been provided from a 33 KV Sub-station located in PREFRE-II complex to meet the O and M requirement of plant. The major equipment of the substation includes HT switch board, dry type transformer, LT switch board, Diesel Generator (DG) set and Un-interrupted Power Supply (UPS) System. The power supply to the plant is provided at 415 V voltage level with the help of Power Distribution Boards (PDBs) and Motor Control Centres (MCCs) located at different floors of the plant. The parameters of the electrical equipment of substation and plant are recorded in each shift in the log-book, manually by the operator. To maintain the log-book, the operator needs to go closer to the individual equipment in radioactive area of the plant to read the parameters. The log-book method of monitoring is a cumbersome method and does not include fault event records, trends and diagnostic behavior of the equipment. Electrical Supervisory Control and Data Acquisition (E-SCADA) system has been increasingly used in Nuclear Power Plants (NPPs) for control and monitoring of electrical parameters of plant and switchyard equipment. E-SCADA system has been designed, developed and implemented for PREFRE-II plant for remote monitoring of parameters of electrical equipment. E-SCADA system provides monitoring of electrical equipment and renders complete guidance and information with the help of Graphical User Interface (GUI) to the operator to take necessary action during normal and abnormal conditions. E-SCADA with intelligent communication features helps in reducing cabling from field equipment which enhances the fire safety of plant. As a result engineering, operation and maintenance efforts for monitoring are reduced considerably in terms of requirement of skilled man power and accurate data logging of electrical parameters. This system also helps to

  11. Electric power distribution: in the direction of a competitive market?

    International Nuclear Information System (INIS)

    Souza, J.R.A. de.

    1993-01-01

    This paper discusses the process of electric power sector deregulation, occurred in several countries, frequently followed of privatization, which the aim is activate the competition and, consequently, the efficiency between the companies of the electric power sector. The competition in the supply market of electric power, by the Great Britain, France, Spain and United States are shown as an example of this energy policy. (C.G.C.)

  12. 78 FR 50409 - Kansas Municipal Energy Agency v. Sunflower Electric Power Corporation, Mid-Kansas Electric...

    Science.gov (United States)

    2013-08-19

    ... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket Nos. EL13-84-000] Kansas Municipal Energy Agency v. Sunflower Electric Power Corporation, Mid-Kansas Electric Company, LLC, Southwest... 306 of the Federal Power Act, 16 U.S.C. 824e and 825e and Rule 206 of the Federal Energy Regulatory...

  13. 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)

  14. Trend of collective dose and dose reduction measures of Mitsubishi Electric Corporation workers in nuclear power plants

    International Nuclear Information System (INIS)

    Yamato, I.; Nakayama, T.; Shimokawa, F.; Yamamoto, T.

    1996-01-01

    MELCO has supplied the reactor instrumentation control system, reactor coolant pump motors, turbine generator and central control system for the pressurized water type nuclear power plant. For the legal periodical inspection and repair work, MELCO has also received orders for the periodical inspection for 23 power plants (including 4 plants under construction) of 5 electric power companies, and executed the inspection work from the view point of preventive maintenance. The annual dose for MELCO's workers is liable to be decreased in spite of increased number of plants. The dose for new plant in particular is 50, or less as compared with that for conventional plant. This is because the measures taken for the conventional plant against the dose reduction is reflected upon the new plant. The dose reduction measures are taken for each system for which order was received. Such measures are mainly intended to improve the work procedures and equipment for reduction of work time in the radioactive area and to arrange the working process, so as to perform the work in such period when the dose level at the working environment is low. To enhance the workers' consciousness for reduction of dose, MELCO provided the workers with dose predictive training, and let them aware of such items known at the tool box briefing (TBX), which could realize the dose reduction for workers. MELCO has been positively promoting the activity to arrange the desirable work environment for extermination of 3Ks (giken, gitsui, titanai) or 3Ds (dangerous, difficult, dirty) including protection against radiation in corporation with electric power companies. (author)

  15. The next generation of power reactors - safety characteristics

    International Nuclear Information System (INIS)

    Modro, S.M.

    1995-01-01

    The next generation of commercial nuclear power reactors is characterized by a new approach to achieving reliability of their safety systems. In contrast to current generation reactors, these designs apply passive safety features that rely on gravity-driven transfer processes or stored energy, such as gas-pressurized accumulators or electric batteries. This paper discusses the passive safety system of the AP600 and Simplified Boiling Water Reactor (SBWR) designs

  16. Assessment and Improving Methods of Reliability Indices in Bakhtar Regional Electricity Company

    Directory of Open Access Journals (Sweden)

    Saeed Shahrezaei

    2013-04-01

    Full Text Available Reliability of a system is the ability of a system to do prospected duties in future and the probability of desirable operation for doing predetermined duties. Power system elements failures data are the main data of reliability assessment in the network. Determining antiseptic parameters is the goal of reliability assessment by using system history data. These parameters help to recognize week points of the system. In other words, the goal of reliability assessment is operation improving and decreasing of the failures and power outages. This paper is developed to assess reliability indices of Bakhtar Regional Electricity Company up to 1393 and the improving methods and their effects on the reliability indices in this network. DIgSILENT Power Factory software is employed for simulation. Simulation results show the positive effect of improving methods in reliability indices of Bakhtar Regional Electricity Company.

  17. The effects of electric power industry restructuring on the safety of nuclear power plants in the United States

    Science.gov (United States)

    Butler, Thomas S.

    Throughout the United States the electric utility industry is restructuring in response to federal legislation mandating deregulation. The electric utility industry has embarked upon an extraordinary experiment by restructuring in response to deregulation that has been advocated on the premise of improving economic efficiency by encouraging competition in as many sectors of the industry as possible. However, unlike the telephone, trucking, and airline industries, the potential effects of electric deregulation reach far beyond simple energy economics. This dissertation presents the potential safety risks involved with the deregulation of the electric power industry in the United States and abroad. The pressures of a competitive environment on utilities with nuclear power plants in their portfolio to lower operation and maintenance costs could squeeze them to resort to some risky cost-cutting measures. These include deferring maintenance, reducing training, downsizing staff, excessive reductions in refueling down time, and increasing the use of on-line maintenance. The results of this study indicate statistically significant differences at the .01 level between the safety of pressurized water reactor nuclear power plants and boiling water reactor nuclear power plants. Boiling water reactors exhibited significantly more problems than did pressurized water reactors.

  18. Physical characteristics of GE [General Electric] BWR [boiling-water reactor] fuel assemblies

    International Nuclear Information System (INIS)

    Moore, R.S.; Notz, K.J.

    1989-06-01

    The physical characteristics of fuel assemblies manufactured by the General Electric Company for boiling-water reactors are classified and described. The classification into assembly types is based on the GE reactor product line, the Characteristics Data Base (CDB) assembly class, and the GE fuel design. Thirty production assembly types are identified. Detailed physical data are presented for each assembly type in an appendix. Descriptions of special (nonstandard) fuels are also reported. 52 refs., 1 fig., 6 tabs

  19. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    International Nuclear Information System (INIS)

    Hampel, V.E.

    1989-01-01

    The author presents a nuclear reactor for generating electricity disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor

  20. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    Science.gov (United States)

    Hampel, Viktor E.

    1989-01-01

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

  1. 76 FR 24465 - Pacific Gas and Electric Company

    Science.gov (United States)

    2011-05-02

    ... Electric Company Notice of Application Tendered for Filing With the Commission and Establishing Procedural... Gas and Electric Company. e. Name of Project: Drum-Spaulding Project. f. Location: The west slope of..., Pacific Gas and Electric Company, P.O. Box 770000, San Francisco, CA 94177-0001, (415) 973-4481, or e-mail...

  2. Characteristics and economy of the European reactor of pressurized water (EPR)

    International Nuclear Information System (INIS)

    Ortiz V, J.; Ramirez S, J.R.; Palacios H, J.C.

    2005-01-01

    The high current costs of the fossil fuels, have propitiated that the industries of electric power generation in the world reconsider the nuclear option as medium of generation. In Europe, the more recently contracted nuclear power plant is that of Olkiluoto-III in Finland that waits it enters in operation at the end of 2009. The reactor that will be installed in this power plant will be a prototype of pressurized water reactor of the companies AREVA and EDF. In this work they are described the reactor EPR and the major components of the nuclear power plant as well as the main characteristics of safety and the flexibility of the operation of the EPR. The supposed costs reported in different sources of information are also described and calculated with information provided by the manufacturer company. (Author)

  3. Subchannel analysis in nuclear reactors

    International Nuclear Information System (INIS)

    Ninokata, H.; Aritomi, M.

    1992-01-01

    This book contains 10 informative papers, presented at the International Seminar on Subchannel Analysis 1992 (ISSCA '92), organized by the Institute of Applied Energy, in collaboration with Atomic Energy Society of Japan, Tokyo Electric Power Company, Kansai Electric Power Company, Nuclear Power Engineering Corporation and the Japan Atomic Energy Research Institute, and held at the TIS-Green Forum, Tokyo, Japan, 30 October 1992. The seminar ISSCA '92 was intended to review the current state-of-the-arts of the method being applied to advanced nuclear reactors including Advanced BWRs, Advanced PWRs and LMRs, and to identify the problems to be solved, improvements to be made, and the needs of R and Ds that were required from the new fuel bundles design. The critical review was to focus on the performances of currently available subchannel analysis codes with regard to heat transfer and fluid flows in various types of nuclear reactor bundles under both steady-state and transient operating conditions, CHF, boiling transition (BT) or dryout behaviors and post BT. The behaviors of physical modeling and numerical methods in these extreme conditions were discussed and the methods critically evaluated in comparison with experiments. (author) (J.P.N.)

  4. The independent power production and the reorganization of the electric power sector

    International Nuclear Information System (INIS)

    1998-12-01

    The transformation of the electric power production and distribution sector is in progress thanks to the progressive opening of markets and to the emergence of a new kind of actor: the independent producer. After the USA, the UK, and most of the emerging countries, the continental Europe is actively preparing its mutation. The historical actors try to protect their positions on their own national markets and at the same time to develop their international position. The newcomers (oil companies, independent power producers, collective service companies) have adopted a radically offensive strategy based on an international development and a skimming of the market. This study takes stock of the degree of liberalization of the different markets and analyzes their structuring elements and dynamism. An analytical presentation of the main actors of the electric power market is performed in order to evaluate their forces and feeblenesses in front of this mutation. Finally, it tries to answer the following questions: which are the most promising zones for the newcomers, and which companies will win this new deal? (J.S.)

  5. Assessment of Smart Reactor Utilization for Barelang

    International Nuclear Information System (INIS)

    Sahala-M-Lumbanraja; Yuliastuti

    2007-01-01

    This paper assesses the feasibility of SMART reactor utilization in BARELANG region. BARELANG region is an industrial area located in Riau Islands Province. The need of electricity and fresh water, whether for industry growth or people, are the main problem of this region. Until now, the National Electricity Company (PLN) has not able to supply the electricity needed by industrial sector. The use of oil as a main electricity generation resource of the entire power plant has caused a tremendous generation cost. On dry seasons, the fresh water supplied by PDAM is reducing drastically. This situation occurs because water source of PDAM extremely depends on the water storage during rainy seasons. SMART reactor is a modular light reactor developed by KAERI for dual purposes, producing electricity and fresh water at the same time. The total thermal power generated by this type of reactor is about 330 M Wth with 33 % efficiency, as 90 M We connected to the electricity grid and rest is used in producing potable water with capacity 40,000 m 3 /day. Compare to the conventional reactor, SMART reactor is based on simple operation and maintenance principles, enhanced safety, easy to inspect, a relatively short construction time, small investment cost, competitive generation cost, and a flexible design to fit with the existing infrastructure. The main characteristic of SMART reactor is an integral design concept where the entire main cooling system components are located in the pressurize vessel. (author)

  6. Integrated operation and management system for a 700MW combined cycle power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shiroumaru, I. (Yanai Power Plant Construction Office, Chugoku Electric Power Co., Inc., 1575-5 Yanai-Miyamoto-Shiohama, Yanai-shi, Yamaguchi-ken (JP)); Iwamiya, T. (Omika Works, Hitachi, Ltd., 5-2-1 Omika-cho, Hitachi-shi, Ibaraki-ken (JP)); Fukai, M. (Hitachi Works, Hitachi, Ltd., 3-1-1 Saiwai-cho, Hitachi-shi, Ibaraki-ken (JP))

    1992-03-01

    Yanai Power Plant of the Chugoku Electric Power Co., Inc. (Yamaguchi Pref., Japan) is in the process of constructing a 1400MW state-of-the-art combined cycle power plant. The first phase, a 350MW power plant, started operation on a commercial basis in November, 1990. This power plant has achieved high efficiency and high operability, major features of a combined cycle power plant. The integrated operation and management system of the power plant takes care of operation, maintenance, control of general business, etc., and was built using the latest computer and digital control and communication technologies. This paper reports that it is expected that this system will enhance efficient operation and management for the power plant.

  7. Space-reactor electric systems: subsystem technology assessment

    International Nuclear Information System (INIS)

    Anderson, R.V.; Bost, D.; Determan, W.R.

    1983-01-01

    This report documents the subsystem technology assessment. For the purpose of this report, five subsystems were defined for a space reactor electric system, and the report is organized around these subsystems: reactor; shielding; primary heat transport; power conversion and processing; and heat rejection. The purpose of the assessment was to determine the current technology status and the technology potentials for different types of the five subsystems. The cost and schedule needed to develop these potentials were estimated, and sets of development-compatible subsystems were identified

  8. Interim report on the accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    2011-12-01

    The Investigation Committee on the Accident at the Fukushima Nuclear Power Stations (the Investigation Committee) of Tokyo Electric Power Company (TEPCO) was established by the Cabinet decision on May 24, 2011. Its objectives are: to conduct investigation for finding out the causes of accidents at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi NPS) and Fukushima Dai-ni Nuclear Power Station (Fukushima Dai-ni NPS) of TEPCO as well as the causes of accident damage; and to make policy recommendations for limiting the expansion of damage and preventing reoccurrence of similar accidents. The Investigation Committee has conducted its investigation and evaluation since its first meeting on June 7, 2011. Its activities included: site visits to the Fukushima Dai-ichi and Dai-ni NPSs, as well as to other facilities; hearing of heads of local governments around the Fukushima Dai-ichi NPS; and hearing of people concerned through interviews mainly arranged by the Secretariat. As of December 16, 2011, the number of interviewees reached 456. The investigation and evaluation by the Investigation Committee are still ongoing and the Interim Report does not cover every item that the Committee aims at investigating and evaluating. Fact-finding of even some of those items discussed in the Interim Report are not yet completed. The Investigation Committee continues to conduct its investigation and evaluation and will issue its Final Report in the summer of 2012. This brief executive summary covers mainly considerations and evaluation of the issues in Chapter VII of the Interim Report, with brief reference to Chapters I to VI. The Investigation Committee recommendations are printed in bold. (author)

  9. Reactor pressure vessel life cycle management at the Calvert Cliffs Nuclear Power Plant

    International Nuclear Information System (INIS)

    Doroshuk, B.W.; Bowman, M.E.; Henry, S.A.; Pavinich, W.A.; Lapides, M.E.

    1993-01-01

    Life Cycle Management (LCM) seeks to manage the aging process of important systems, structures, and components during licensed operation. The goal of Baltimore Gas and Electric Company's (BG and E) Life Cycle Management Program is to assure attainment of 40 years of operation and to preserve the option of an additional 20 years of operation for the Calvert Cliffs Nuclear Power Plant (CCNPP). Since the reactor pressure vessel (RPV) has been identified as one of the most critical components with regard to long-term operation of a nuclear power plant, BG and E initiated actions to manage life limiting or aging issues for the CCNPP RPVs. To achieve long-term operation, technical RPV issues must be effectively managed. This paper describes methods BG and E uses for managing RPV age-related degradation. (author)

  10. Monitoring for shaft cracks on reactor recirculation pumps

    International Nuclear Information System (INIS)

    Kowal, M.G.; O'Brien, J.T. Jr.

    1989-01-01

    The article discusses the vibration characteristics associated with a boiling water reactor (BWR) recirculation pump. It also describes the application of diagnostic techniques and shaft crack theory to an on-line diagnostic monitoring system for reactor recirculation pumps employed at Philadelphia Electric Company's Peach Bottom Atomic Power Station. Specific emphasis is placed on the unique monitoring techniques associated with these variable speed vertical pumps

  11. Assessment and mitigation of power quality problems for PUSPATI TRIGA Reactor (RTP)

    Science.gov (United States)

    Zakaria, Mohd Fazli; Ramachandaramurthy, Vigna K.

    2017-01-01

    An electrical power systems are exposed to different types of power quality disturbances. Investigation and monitoring of power quality are necessary to maintain accurate operation of sensitive equipment especially for nuclear installations. This paper will discuss the power quality problems observed at the electrical sources of PUSPATI TRIGA Reactor (RTP). Assessment of power quality requires the identification of any anomalous behavior on a power system, which adversely affects the normal operation of electrical or electronic equipment. A power quality assessment involves gathering data resources; analyzing the data (with reference to power quality standards) then, if problems exist, recommendation of mitigation techniques must be considered. Field power quality data is collected by power quality recorder and analyzed with reference to power quality standards. Normally the electrical power is supplied to the RTP via two sources in order to keep a good reliability where each of them is designed to carry the full load. The assessment of power quality during reactor operation was performed for both electrical sources. There were several disturbances such as voltage harmonics and flicker that exceeded the thresholds. To reduce these disturbances, mitigation techniques have been proposed, such as to install passive harmonic filters to reduce harmonic distortion, dynamic voltage restorer (DVR) to reduce voltage disturbances and isolate all sensitive and critical loads.

  12. Nuclear-electric power in space

    International Nuclear Information System (INIS)

    Truscello, V.C.; Davis, H.S.

    1984-01-01

    Because direct-broadcast satellites, air-traffic-control radar satellites, industrial processing on subsequent versions of the space station, and long range excursions to other planets using nuclear-electric propulsion systems, all space missions for which current power-supply systems are not sufficient. NASA and the DOE therefore have formed a joint program to develop the technology required for nuclear-reactor space power plants. After investigating potential space missions in the given range, the project will develop the technology to build such systems. High temperatures pose problems, ''hot shoes'' and ''cold shoes'', a Stirling engine dynamic system, and critical heat-transfer problems are all discussed. The nuclear reactor system for space as now envisioned is schematicized

  13. ANALYSIS OF GROSS REGIONAL PRODUCT FLUCTUATIONS AND ELECTRIC POWER CONSUMPTION IN 2005- 2014. RESERVES FOR DECREASING ELECTRIC POWER PRICES

    Directory of Open Access Journals (Sweden)

    Suslov N. I.

    2016-09-01

    Full Text Available In this work we considered the trajectories of change in indicators characterizing the status of economics and power industry: gross regional product, electric power consumption, industrial production, energy prices and costs of delivering electric power to consumers in Russian regions for the last 10 years. Low global commodity prices and sanctions led to a sharp decrease of equipment import, which resulted in an acute problem of import substitution. The level of tariffs of natural monopolies is of great importance for industrial development. The goal of this work was to analyze possibilities for reducing electric power prices by changing the institutional and economic conditions of management. We analyzed not only the official information from Rosstat, but also government regulations, figures given in the official government publication «The Rossiyskaya Gazeta» as well as articles and interviews on economic problems of the electric power industry over the recent years published in «The Kommersant» newspaper. High tariffs of network marketing companies for electric energy transmission, state regulation of heating prices, financing the construction of new capacities by charging the payment in power provision contracts, high price of electric power of nuclear power plants lead to an annual increase in electric power prices for end users. In this work we considered possible solutions to limit the growth of electric power prices.

  14. Nuclear power reactors and hydrogen storage systems

    International Nuclear Information System (INIS)

    Ibrahim Aly Mahmoud El Osery.

    1980-01-01

    Among conclusions and results come by, a nuclear-electric-hydrogen integrated power system was suggested as a way to prevent the energy crisis. It was shown that the hydrogen power system using nuclear power as a leading energy resource would hold an advantage in the current international situation as well as for the long-term future. Results reported provide designers of integrated nuclear-electric-hydrogen systems with computation models and routines which will allow them to explore the optimal solution in coupling power reactors to hydrogen producing systems, taking into account the specific characters of hydrogen storage systems. The models were meant for average computers of a type easily available in developing countries. (author)

  15. Development of creep damage assessment system for aged thermal power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nonaka, Isamu [IshikawaJima-Harima Heavy Industries Co., Ltd., Tokyo (Japan); Umaki, Hideo [Ishikawajima-Harima Heavy Industries Co., Ltd., Tokyo (Japan); Nishida, Hidetalca [The Chugoku Electric Power Co., Inc., Hiroshima (Japan); Yamaguchi, Hiroshi [The Chugoku Electric Power Co., Inc., Hiroshima (Japan)

    1999-12-31

    IHI has developed the Creep Damage Assessment System to identify voids by processing an image observed by a small laser microscope with an advanced image processing technique jointly with Chugoku Electric Power Co., Inc. The result can be obtained immediately on the spot. Application tests of the system at the Unit No.3 boiler of the Kudamatsu Power Station showed good operability, adaptability to the environment, and accuracy. The new system can easily indicate damage conditions in parts during the periodical inspection, allowing rapid maintenance. Time reduction required for assessment and increased reliability of equipment can be also achieved. (orig.)

  16. Development of creep damage assessment system for aged thermal power plant

    Energy Technology Data Exchange (ETDEWEB)

    Nonaka, Isamu [IshikawaJima-Harima Heavy Industries Co., Ltd., Tokyo (Japan); Umaki, Hideo [Ishikawajima-Harima Heavy Industries Co., Ltd., Tokyo (Japan); Nishida, Hidetalca [The Chugoku Electric Power Co., Inc., Hiroshima (Japan); Yamaguchi, Hiroshi [The Chugoku Electric Power Co., Inc., Hiroshima (Japan)

    1998-12-31

    IHI has developed the Creep Damage Assessment System to identify voids by processing an image observed by a small laser microscope with an advanced image processing technique jointly with Chugoku Electric Power Co., Inc. The result can be obtained immediately on the spot. Application tests of the system at the Unit No.3 boiler of the Kudamatsu Power Station showed good operability, adaptability to the environment, and accuracy. The new system can easily indicate damage conditions in parts during the periodical inspection, allowing rapid maintenance. Time reduction required for assessment and increased reliability of equipment can be also achieved. (orig.)

  17. IRIS: A global approach to nuclear power renaissance

    International Nuclear Information System (INIS)

    Carelli, M.D.

    2004-01-01

    Improved international reactor IRIS (International Reactor Innovative and Secure) is discussed. IRIS is defined as a modular reactor with integral arrangement and water coolant. Industrial companies, research, scientific groups and electric power producers of different countries (USA, Great Britain, Italy, Spain, Brazil, Russia, Mexico, Japan, Croatia) take part in the realization of IRIS. Basic parameters of the reactor, construction characteristics, arrangement are presented [ru

  18. Electric Power Monthly, July 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-10-12

    The Electric Power Monthly (EPM) is prepared by the Electric Power Division; Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), Department of Energy. This publication provides monthly statistics at the national, Census division, and State levels for net generation, fuel consumption, fuel stocks, quantity and quality of fuel, cost of fuel, electricity sales, and average revenue per kilowatthour of electricity sold. Data on net generation are also displayed at the North American Electric Reliability Council (NERC) region level. Additionally, company and plant level information are published in the EPM on capability of new plants, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost in fuel. Quantity, quality, and cost of fuel data lag the net generation, fuel consumption, fuel stocks, electricity sales, and average revenue per kilowatthour data by 1 month. This difference in reporting appears in the national, Census division, and State level tables. However, at the plant level, all statistics presented are for the earlier month for the purpose of comparison. 12 refs., 4 figs., 48 tabs.

  19. Upgrading the electrical system of the IEA-R1 reactor to avoid triggering event of accidents

    International Nuclear Information System (INIS)

    Mello, Jose Roberto de; Madi Filho, Tufic

    2015-01-01

    The IEA-R1 research reactor at the Institute of Energy and Nuclear Research (IPEN) is a research reactor open pool type, built and designed by the American firm 'Babcox and Wilcox', having as coolant and moderator demineralized light water and Beryllium and graphite, as reflectors. The power supply system is designed to meet the electricity demand required by the loads of the reactor (Security systems and systems not related to security) in different situations the plant can meet, such as during startup, normal operation at power, shutdown, maintenance, exchange of fuel elements and accident situations. Studies have been done on possible accident initiating events and deterministic techniques were applied to assess the consequences of such incidents. Thus, the methods used to identify and select the accident initiating events, the methods of analysis of accidents, including sequence of events, transient analysis and radiological consequences, have been described. Finally, acceptance criteria of radiological doses are described. Only a brief summary of the item concerning loss of electrical power will be presented. The loss of normal electrical power at the IEA-R1 reactor is very common. In the case of Electric External Power Loss, at the IEA-R1 reactor building, there may be different sequences of events, as described below. When the supply of external energy in the IEA-R1 facility fails, the Electrical Distribution Vital System, consisting of 4 (four) generators type 'UPS', starts operation, immediately and it will continue supplying power to the reactor control table, core cooling system and other security systems. To contribute to security, in the electric power failure, starts to operate the Emergency Cooling System (SRE). SRE has the function of removing residual heat from the core to prevent the melting of fuel elements in the event of loss of refrigerant to the core. Adding to the generators with batteries group system, new auxiliary

  20. An overview of future sustainable nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Poullikkas, Andreas [Electricity Authority of Cyprus, P.O. Box 24506, 1399 Nicosia (Cyprus)

    2013-07-01

    In this paper an overview of the current and future nuclear power reactor technologies is carried out. In particular, the nuclear technology is described and the classification of the current and future nuclear reactors according to their generation is provided. The analysis has shown that generation II reactors currently in operation all around the world lack significantly in safety precautions and are prone to loss of coolant accident (LOCA). In contrast, generation III reactors, which are an evolution of generation II reactors, incorporate passive or inherent safety features that require no active controls or operational intervention to avoid accidents in the event of malfunction, and may rely on gravity, natural convection or resistance to high temperatures. Today, partly due to the high capital cost of large power reactors generating electricity and partly due to the consideration of public perception, there is a shift towards the development of smaller units. These may be built independently or as modules in a larger complex, with capacity added incrementally as required. Small reactors most importantly benefit from reduced capital costs, simpler units and the ability to produce power away from main grid systems. These factors combined with the ability of a nuclear power plant to use process heat for co-generation, make the small reactors an attractive option. Generally, modern small reactors for power generation are expected to have greater simplicity of design, economy of mass production and reduced installation costs. Many are also designed for a high level of passive or inherent safety in the event of malfunction. Generation III+ designs are generally extensions of the generation III concept, which include advanced passive safety features. These designs can maintain the safe state without the use of any active control components. Generation IV reactors, which are future designs that are currently under research and development, will tend to have closed

  1. Study on the power control system for NPP power unit with the WWER-440 reactor

    International Nuclear Information System (INIS)

    Aleksandrova, N.D.; Naumov, A.V.

    1981-01-01

    Results of model investigations into basic version of the power control systems (PCS) conformably to the WWER-440 NPP power unit are stated. Transient processes in the power unit system when being two PCS versions during perturbations of different parameters: unit power, vapour pressure or position of control rods have been simulated. Investigations into the different PCS versions show that quality of operation of a traditional scheme with a turbine power controller and reactor pressure controller can be significantly improved with the introduction of a high-speed signal of pressure into the reactor controller. The PCS version with the compensation of interrelations between the turbine and reactor controllers constructed according to the same principles as the standard schemes of power units of thermal electric power plant is perspective as well [ru

  2. Introduction of construction management system for preparation work of Shimane Nuclear Power Station Unit-3

    International Nuclear Information System (INIS)

    Sasaki, Yutaka; Tsumura, Isamu; Hayashi, Minoru; Nakamoto, Kenji

    2005-01-01

    The construction management system aims to have information on the construction management between the Chugoku Electric Power Co. Inc. and each contractor, and to work efficiently. The system has been operating during about half year. The system manages the manufacturing process, safety and quality. The aims, development process, characteristics, network construction of the system are reported. As outline of the construction management system, functions and construction management of each process, safety and quality and ITV camera are explained. The system will be used at construction of Shimane nuclear power station unit-3. (S.Y.)

  3. Additional costs for Norwegian power companies from the OED-proposed implementation of the Electricity Directive II; Merkostnader for norske kraftselskaper ved OEDs forslag til implementering av Eldirektiv II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The cost-related consequences for Norwegian vertically integrated power companies caused by the proposed implementation of Electricity Directive II by OED (Norwegian Oil and Energy Department) are considered. Electricity Directive II demands a company and functional division between the network activities and the activities exposed to competition. The OED proposition aims at lowering the limit for which network companies are included by the new demands, from 100.000 to either 20.000 or 10.000 network clients. Moreover, they propose measures that ensure the network companies' independence, and these exceed by far the minimum requirements of Electricity Directive II. The additional costs may be significant in some aspects. Especially the requirement of an independent management in parent- and subsidiary company will lead to added costs of about Nok 320 million for the Norwegian power business. Further, a split-up management structure may be poorly compatible with the mind set behind the corporate model, something which potentially can lead to bad investments or a weaker utilization of potential cost synergies. The motive for proposing stricter demands on Norwegian power business is among other to limit cross-subsidies so that the competition in the market is reinforced. In light of substantial, quantified additional costs and other negative effects, the proposition's effect on the competition should be investigated further, including alternative measures that may be more cost-effective and/or more accurate (ml)

  4. The decision making of an electric power producer

    International Nuclear Information System (INIS)

    Giger, F.

    2002-01-01

    How can choose an electric power producer when he has to decide an investment of a supplementary power plant? Which were the criteria to choose a small or a medium power reactor? In this framework, the economical profitability, the technical feasibility and the associated risks are discussed. (A.L.B.)

  5. Risk management of power supply in open electricity market

    International Nuclear Information System (INIS)

    Rinta-Runsala, E.; Kiviniemi, J.

    1999-12-01

    The open electricity market has increased the need of risk management in electric utilities. In this publication the concepts of risk assessment and measures mostly concentrating on market risks for power supply companies are reported. An essential past of the risk management includes the electricity derivates and trade

  6. Ground testing of an SP-100 prototypic reactor

    International Nuclear Information System (INIS)

    Motwani, K.; Pflasterer, G.R.; Upton, H.; Lazarus, J.D.; Gluck, R.

    1988-01-01

    SP-100 is a space power system which is being developed by GE to meet future space electrical power requirements. The ground testing of an SP-100 prototypic reactor system will be conducted at the Westinghouse Hanford Company site located at Richland, Washington. The objective of this test is to demonstrate the performance of a full scale prototypic reactor system, including the reactor, control system and flight shield. The ground test system is designed to simulate the flight operating conditions while meeting all the necessary nuclear safety requirements in a gravity environment. The goal of the reactor ground test system is to establish confidence in the design maturity of the SP-100 space reactor power system and resolve the technical issues necessary for the development of a flight mission design

  7. Design and performance of General Electric boiling water reactor main steam line isolation valves

    International Nuclear Information System (INIS)

    Rockwell, D.A.; van Zylstra, E.H.

    1976-08-01

    An extensive test program has been completed by the General Electric Company in cooperation with the Commonwealth Edison Company on the basic design type of large main steam line isolation valves used on General Electric Boiling Water Reactors. Based on a total of 40 tests under simulated accident conditions covering a wide range of mass flows, mixture qualities, and closing times, it was concluded that the commercially available valves of this basic type will close completely and reliably as required. Analytical methods to predict transient effects in the steam line and valve after postulated breaks were refined and confirmed by the test program

  8. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  9. Electric power monthly, May 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    The Electric Power Monthly (EPM) presents monthly electricity statistics. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data in this report are presented for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. This publication provides monthly statistics for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Statistics by company and plant are published on the capability of new generating units, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fossil fuels.

  10. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  11. Conversion of a reactor to partial power output

    International Nuclear Information System (INIS)

    Iljunin, W.G.; Kusnezow, I.A.; Murogow, W.M.; Schmelew, A.N.

    1975-01-01

    The method, among other things, involves an increase in the rate of secondary fissile material production in a fast breeder reactor if the flow of the working fluid through a turbine is reduced as a function of a given amount of reduction of the electric load. This objective will be served by a circuit and circuit variants, respectively, which include a high temperature cooling circuit with, for instance, a sodium cooled HTR, a low temperature cooling circuit with, for instance, a fast or thermal breeder reactor, a working fluid circuit with the turbine, and a heat consumption circuit. In the scheme suggested for operation in the partial power production mode it is envisaged that, as the electric load of the plant decreases the flow of the working fluid upstream of the turbine is kept constant by means of a control system in the working fluid circuit. Additional control systems are used to reduce the amount of heat transmitted by the breeder reactor to the working fluid. The excess amount of heat is distributed to the load connected. This again reduces the temperatures at the inlet and the outlet of the breeder reactor, thus raising its thermal power output. However, the flow through the breeder reactor remains constant all the time. (DG/RF) [de

  12. Power exchange game in the electricity market

    International Nuclear Information System (INIS)

    Pyykko, S.; Partanen, J.; Viljainen, S.; Lassila, J.; Honkapuro, S.; Tahvanainen, K.

    2006-01-01

    Since it is not economically reasonable to build parallel electricity networks, in Finland, Sweden, Norway and Denmark, electricity distribution is protected by monopoly. However, electricity production and selling have been opened up to competition by connecting the transmission networks of these countries together, and it is possible to produce electricity where it is cheapest. A common electricity power market, called Nord Pool, has been created where electricity can be bought, sold or used as an exchange product. In order to help students understand the operation of electricity markets and the use of different electricity exchange products, the Department of Electrical Engineering at Lappeenranta University developed a scheme in which the theory can be used in practice. In the scheme, students are given the responsibility to manage the electricity markets of power companies in order analyze, plan and make decisions, which are skills required on the open power markets. The paper provided an introduction to the electricity markets in Nordic countries and discussed Nord Pool and its products. Information about education at the Department of Electrical Engineering at Lappeenranta University of Technology was also presented. The paper also provided details of the power exchange scheme on the electricity markets. 6 refs., 17 figs

  13. New technologies deployment for advanced power plants

    International Nuclear Information System (INIS)

    Kiyoshi, Yamauchi

    2007-01-01

    Mitsubishi Heavy Industries, Ltd. (MHI) has been the total engineering and manufacturing company of pressurized water reactors (PWRs) in Japan since the commencement of commercial operations of Mihama Unit 1 of the Kansai Electric Power Company in 1970. Over these decades, MHI has endeavored to develop a broad spread of nuclear technology, from design, manufacturing, and construction, to plant maintenance services. More recently, with the ever rising need for nuclear power generation around the world to prevent global warming and to cope with surging oil prices, MHI is striving to expand its nuclear power business in the world market, such as US-APWR (Advanced Pressurized Water Reactor) in the U.S., as well as to develop technology for advanced reactors and nuclear fuel cycles to ensure energy security in the future. This paper introduces these approaches, especially focused on new technologies deployment for the global needs, and clarifies the current status and future prospects of MHI as the world's leading nuclear company. (author)

  14. Nuclear Power as a Basis for Future Electricity Generation

    Science.gov (United States)

    Pioro, Igor; Buruchenko, Sergey

    2017-12-01

    It is well known that electrical-power generation is the key factor for advances in industry, agriculture, technology and the level of living. Also, strong power industry with diverse energy sources is very important for country independence. In general, electrical energy can be generated from: 1) burning mined and refined energy sources such as coal, natural gas, oil, and nuclear; and 2) harnessing energy sources such as hydro, biomass, wind, geothermal, solar, and wave power. Today, the main sources for electrical-energy generation are: 1) thermal power - primarily using coal and secondarily - natural gas; 2) “large” hydro power from dams and rivers and 3) nuclear power from various reactor designs. The balance of the energy sources is from using oil, biomass, wind, geothermal and solar, and have visible impact just in some countries. In spite of significant emphasis in the world on using renewables sources of energy, in particular, wind and solar, they have quite significant disadvantages compared to “traditional” sources for electricity generation such as thermal, hydro, and nuclear. These disadvantages include low density of energy, which requires large areas to be covered with wind turbines or photovoltaic panels or heliostats, and dependence of these sources on Mother Nature, i.e., to be unreliable ones and to have low (20 - 40%) or very low (5 - 15%) capacity factors. Fossil-fueled power plants represent concentrated and reliable source of energy. Also, they operate usually as “fast-response” plants to follow rapidly changing electrical-energy consumption during a day. However, due to combustion process they emit a lot of carbon dioxide, which contribute to the climate change in the world. Moreover, coal-fired power plants, as the most popular ones, create huge amount of slag and ash, and, eventually, emit other dangerous and harmful gases. Therefore, Nuclear Power Plants (NPPs), which are also concentrated and reliable source of energy

  15. Proposal of space reactor for nuclear electric propulsion system

    International Nuclear Information System (INIS)

    Nishiyama, Takaaki; Nagata, Hidetaka; Nakashima, Hideki

    2009-01-01

    A nuclear reactor installed in spacecrafts is considered here. The nuclear reactor could stably provide an enough amount of electric power in deep space missions. Most of the nuclear reactors that have been developed up to now in the United States and the former Soviet Union have used uranium with 90% enrichment of 235 U as a fuel. On the other hand, in Japan, because the uranium that can be used is enriched to below 20%, the miniaturization of the reactor core is difficult. A Light-water nuclear reactor is an exception that could make the reactor core small. Then, the reactor core composition and characteristic are evaluated for the cases with the enrichment of the uranium fuel as 20%. We take up here Graphite reactor, Light-water reactor, and Sodium-cooled one. (author)

  16. Conceptual design of a demonstration reactor for electric power generation

    International Nuclear Information System (INIS)

    Asaoka, Y.; Hiwatari, R.; Okano, K.; Ogawa, Y.; Ise, H.; Nomoto, Y.; Kuroda, T.; Mori, S.; Shinya, K.

    2005-01-01

    Conceptual study on a demonstration plant for electric power generation, named Demo-CREST, was conducted based on the consideration that a demo-plant should have capacities both (1) to demonstrate electric power generation in a plant scale with moderate plasma performance, which will be achieved in the early stage of the ITER operation, and foreseeable technologies and materials and (2) to have a possibility to show an economical competitiveness with advanced plasma performance and high performance blanket systems. The plasma core was optimized to be a minimum size for both net electric power generation with the ITER basic plasma parameters and commercial-scale generation with advance plasma parameters, which would be attained by the end of ITER operation. The engineering concept, especially the breeding blanket structure and its maintenance scheme, is also optimized to demonstrate the tritium self-sustainability and maintainability of in-vessel components. Within the plasma performance as planned in the present ITER program, the net electric power from 0 MW to 500 MW is possible with the basic blanket system under the engineering conditions of maximum magnetic field 16 T, NBI system efficiency 50%, and NBI current drive power restricted to 200 MW. Capacities of stabilization of reversed shear plasma and the high thermal efficiency are additional factors for optimization of the advanced blanket. By replacing the blanket system with the advanced one of higher thermal efficiency, the net electric power of about 1000 MW is also possible so that the economic performance toward the commercial plant can be also examined with Demo-CREST. (author)

  17. Electric power plant international. 1976--1977 edition

    Energy Technology Data Exchange (ETDEWEB)

    1975-01-01

    ''Electric Power Plant International'' is intended to provide a comprehensive commercial and technical information source for use by suppliers, operators, and potential purchasers of power plant, and also by suppliers of materials and services to such organizations. It contains information that will help those considering the purchase of power plant to gain a reasonable understanding of the factors that should be taken into account when making a purchasing decision. Consideration is given to the operation, maintenance, and modification of power systems that will be of relevance to those currently operating plant. The publication is designed to act as an interface between suppliers and users of power plant. As part of this function, reference sections contain listings of all the companies that have been located throughout the world, supplying prime movers, generators, generator sets, and fixed-frequency inverter systems. Details of products currently available from these companies are included wherever possible and this is being continuously up-dated and extended to give increased coverage in future editions. The Electrical Research Association Ltd. does not manufacture or supply power plant (apart from some special-purpose static inverter systems), but would be pleased to receive requirement details from any company wishing to inquire about plant purchase. These will be forwarded to appropriate suppliers throughout the world who will be able to submit tenders for suitable products. Inquiry forms are included in Chapter 6 for this purpose.

  18. Electric-power economy of Japan

    International Nuclear Information System (INIS)

    Dobrochotov, V.I.; Wolfberg, D.B.

    1975-01-01

    This is a survey on a) development and present capacity of electricity-supply companies in Japan, b) the structural shift in the capacity of power plants which took place from 1966 until 1974, arranged according to thermal, nuclear and hydraulic power stations, c) the structural shift in the use of fossile fuels, also from 1966 until 1974, d) the major thermal and nuclear power stations and pump storage plants under construction and in operation, e) interconnected operation. The survey ends with the development study of the Japanese Government being outlined. (GG/LN) [de

  19. Galena Electric Power A Situational Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Robert E. Chaney; Stephen G. Colt; Ronald A. Johnson; Richard W. Wiles; Gregory J. White

    2008-12-31

    The purpose of the investigation is to compare the economics of various electrical power generation options for the City of Galena. Options were assessed over a 30-year project period, beginning in 2010, and the final results were compared on the basis of residential customer electric rates ($/kWh). Galena's electric utility currently generates power using internal combustion diesel engines and generator sets. Nearby, there is an exposed coal seam, which might provide fuel for a power plant. Contributions to the energy mix might come from solar, municipal solid waste, or wood. The City has also been approached by Toshiba, Inc., as a demonstration site for a small (Model 4S) nuclear reactor power plant. The Yukon River is possibly a site for in-river turbines for hydroelectric power. This report summarizes the comparative economics of various energy supply options. This report covers: (1) thermal and electric load profiles for Galena; (2) technologies and resources available to meet or exceed those loads; (3) uses for any extra power produced by these options; (4) environmental and permitting issues and then; and (5) the overall economics of each of the primary energy options.

  20. UF6 breeder reactor power plants for electric power generation

    International Nuclear Information System (INIS)

    Rust, J.H.; Clement, J.D.; Hohl, F.

    1976-01-01

    The reactor concept analyzed is a 233 UF 6 core surrounded by a molten salt (Li 7 F, BeF 2 , ThF 4 ) blanket. Nuclear survey calculations were carried out for both spherical and cylindrical geometries. A maximum breeding ratio of 1.22 was found. Thermodynamic cycle calculations were performed for a variety of Rankine cycles. Optimization of a Rankine cycle for a gas core breeder reactor employing an intermediate heat exchanger gave a maximum efficiency of 37 percent. A conceptual design is presented along with a system layout for a 1000 MW stationary power plant. The advantages of the GCBR are as follows: (1) high efficiency, (2) simplified on-line reprocessing, (3) inherent safety considerations, (4) high breeding ratio, (5) possibility of burning all or most of the long-lived nuclear waste actinides, and (6) possibility of extrapolating the technology to higher temperatures and MHD direct conversion

  1. Guide to power reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-07-15

    The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

  2. An underground nuclear power station using self-regulating heat-pipe controlled reactors

    Science.gov (United States)

    Hampel, V.E.

    1988-05-17

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

  3. Dynamic Response Testing in an Electrically Heated Reactor Test Facility

    Science.gov (United States)

    Bragg-Sitton, Shannon M.; Morton, T. J.

    2006-01-01

    Non-nuclear testing can be a valuable tool in development of a space nuclear power or propulsion system. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Standard testing allows one to fully assess thermal, heat transfer, and stress related attributes of a given system, but fails to demonstrate the dynamic response that would be present in an integrated, fueled reactor system. The integration of thermal hydraulic hardware tests with simulated neutronic response provides a bridge between electrically heated testing and full nuclear testing. By implementing a neutronic response model to simulate the dynamic response that would be expected in a fueled reactor system, one can better understand system integration issues, characterize integrated system response times and response characteristics, and assess potential design improvements at a relatively small fiscal investment. Initial system dynamic response testing was demonstrated on the integrated SAFE-100a heat pipe cooled, electrically heated reactor and heat exchanger hardware, utilizing a one-group solution to the point kinetics equations to simulate the expected neutronic response of the system (Bragg-Sitton, 2005). The current paper applies the same testing methodology to a direct drive gas cooled reactor system, demonstrating the applicability of the testing methodology to any reactor type and demonstrating the variation in system response characteristics in different reactor concepts. In each testing application, core power transients were controlled by a point kinetics model with reactivity feedback based on core average temperature; the neutron generation time and the temperature feedback coefficient are provided as model inputs. Although both system designs utilize a fast spectrum reactor, the method of cooling the reactor differs significantly, leading to a variable system response that can be demonstrated and assessed in a non-nuclear test facility.

  4. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

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

  5. Brayton rotating units for space reactor power systems

    Energy Technology Data Exchange (ETDEWEB)

    Gallo, Bruno M.; El-Genk, Mohamed S. [Institute for Space and Nuclear Power Studies and Chemical and Nuclear Engineering Dept., The Univ. of New Mexico, Albuquerque, NM 87131 (United States)

    2009-09-15

    Designs and analyses models of centrifugal-flow compressor and radial-inflow turbine of 40.8kW{sub e} Brayton Rotating Units (BRUs) are developed for 15 and 40 g/mole He-Xe working fluids. Also presented are the performance results of a space power system with segmented, gas cooled fission reactor heat source and three Closed Brayton Cycle loops, each with a separate BRU. The calculated performance parameters of the BRUs and the reactor power system are for shaft rotational speed of 30-55 krpm, reactor thermal power of 120-471kW{sub th}, and turbine inlet temperature of 900-1149 K. With 40 g/mole He-Xe, a power system peak thermal efficiency of 26% is achieved at rotation speed of 45 krpm, compressor and turbine inlet temperatures of 400 and 1149 K and 0.93 MPa at exit of the compressor. The corresponding system electric power is 122.4kW{sub e}, working fluid flow rate is 1.85 kg/s and the pressure ratio and polytropic efficiency are 1.5% and 86.3% for the compressor and 1.42% and 94.1% for the turbine. For the same nominal electrical power of 122.4kW{sub e}, decreasing the molecular weight of the working fluid (15 g/mole) decreases its flow rate to 1.03 kg/s and increases the system pressure to 1.2 MPa. (author)

  6. Outline of advanced boiling water reactor

    International Nuclear Information System (INIS)

    Yoshio Matsuo

    1987-01-01

    The ABWR (Advanced Boiling Water Reactor) is based on construction and operational experience in Japan, USA and Europe. It was developed jointly by the BWR supplieres, General Electric, Hitachi, and Toshiba, as the next generation BWR for Japan. The Tokyo Electric Power Co. provided leadership and guidance in developing the ABWR, and in combination with five other Japanese electric power companies. The major objectives in developing the ABWR are: 1. Enhanced plant operability, maneuverability and daily load-following capability; 2. Increased plant safety and operating margins; 3. Improved plant availability and capacity factor; 4. Reduced occupational radiation exposure; 5. Reduced radwaste volume, and 6. Reduced plant capital and operating costs. (Liu)

  7. Closed Brayton cycle power conversion systems for nuclear reactors :

    Energy Technology Data Exchange (ETDEWEB)

    Wright, Steven A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lipinski, Ronald J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Vernon, Milton E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sanchez, Travis [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2006-04-01

    This report describes the results of a Sandia National Laboratories internally funded research program to study the coupling of nuclear reactors to gas dynamic Brayton power conversion systems. The research focused on developing integrated dynamic system models, fabricating a 10-30 kWe closed loop Brayton cycle, and validating these models by operating the Brayton test-loop. The work tasks were performed in three major areas. First, the system equations and dynamic models for reactors and Closed Brayton Cycle (CBC) systems were developed and implemented in SIMULINKTM. Within this effort, both steady state and dynamic system models for all the components (turbines, compressors, reactors, ducting, alternators, heat exchangers, and space based radiators) were developed and assembled into complete systems for gas cooled reactors, liquid metal reactors, and electrically heated simulators. Various control modules that use proportional-integral-differential (PID) feedback loops for the reactor and the power-conversion shaft speed were also developed and implemented. The simulation code is called RPCSIM (Reactor Power and Control Simulator). In the second task an open cycle commercially available Capstone C30 micro-turbine power generator was modified to provide a small inexpensive closed Brayton cycle test loop called the Sandia Brayton test-Loop (SBL-30). The Capstone gas-turbine unit housing was modified to permit the attachment of an electrical heater and a water cooled chiller to form a closed loop. The Capstone turbine, compressor, and alternator were used without modification. The Capstone systems nominal operating point is 1150 K turbine inlet temperature at 96,000 rpm. The annular recuperator and portions of the Capstone control system (inverter) and starter system also were reused. The rotational speed of the turbo-machinery is controlled by adjusting the alternator load by using the electrical grid as the load bank. The SBL-30 test loop was operated at

  8. Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-10-15

    At the beginning of 1963 nuclear power plants produced some 3 500 000kW of electrical power to different distribution grids around the world. Much significant operating experience has been gained with these power reactors, but this experience is often not collected in such a way as to make it easily available. The International Atomic Energy Agency convened a Conference on Operating Experience with Power Reactors in Vienna from 4-8 June 1963 which was attended by 240 participants representing 27 of the Agency's Member States and six international organizations. At the Conference, 42 papers giving detailed experience with more than 20 nuclear power stations were discussed. Although similar meetings on a national or regional scale have been held earlier in various countries, this is the first arranged by the Agency on a world-wide basis. Some of the detailed material may have been given earlier but for the most part it represents new and recently acquired experience, and for the first time it has been possible to compile in one place such extensive material on the operating experience with power reactors. The Conference discussed the experience gained both generally in the context of national and international nuclear power development programmes, and more specifically in the detailed operating experience with different power reactor stations. In addition, various plant components, fuel cycles, staffing of nuclear plants and licensing of such staff were treated. It is hoped that these Proceedings will be of interest not only to nuclear plant designers and operators who daily encounter problems similar to those discussed by the Conference, but also to those guiding the planning and implementation of power development programmes.

  9. Operating Experience with Power Reactors. Proceedings of the Conference on Operating Experience with Power Reactors. Vol. II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1963-10-15

    At the beginning of 1963 nuclear power plants produced some 3 500 000 kW of electrical power to different distribution grids around the world. Much significant operating experience has been gained with these power reactors, but this experience is often not collected in such a way as to make it easily available. The International Atomic Energy Agency convened a Conference on Operating Experience with Power Reactors in Vienna from 4 -8 June 1963 which was attended by 240 participants representing 27 of the Agency's Member States and six international organizations. At the Conference, 42 papers giving detailed experience with more than 20 nuclear power stations were discussed. Although similar meetings on a national or regional scale have been held earlier in various countries, this is the first arranged by the Agency on a world-wide basis. Some of the detailed material may have been given earlier but for the most part it represents new and recently acquired experience, and for the first time it has been possible to compile in one place such extensive material on the operating experience with power reactors. The Conference discussed the experience gained both generally in the context of national and international nuclear power development programmes, and more specifically in the detailed operating experience with different power reactor stations. In addition, various plant components, fuel cycles, staffing of nuclear plants and licensing of such staff were treated. It is hoped that these Proceedings will be of interest not only to nuclear , plant designers and operators who daily encounter problems similar to those discussed by the Conference, but also to those guiding the planning and implementation of power development programmes.

  10. Space nuclear reactor electric power. January 1972-May 1990 (A Bibliography from the International Aerospace Abstracts data base). Report for January 1972-May 1990

    International Nuclear Information System (INIS)

    1990-05-01

    This bibliography contains citations concerning studies and conceptual designs of nuclear space power reactors to generate electric power for space missions. The citations cover the technology, safety aspects, and policy considerations. (This updated bibliography contains 280 citations, 172 of which are new entries to the previous edition.)

  11. Reactor design for nuclear electric propulsion

    International Nuclear Information System (INIS)

    Koenig, D.R.; Ranken, W.A.

    1979-01-01

    Conceptual design studies of a nuclear power plant for electric propulsion of spacecrafts have been on going for several years. An attractive concept which has evolved from these studies and which has been described in previous publications, is a heat-pipe cooled, fast spectrum nuclear reactor that provides 3 MW of thermal energy to out-of-core thermionic converters. The primary motivation for using heat pipes is to provide redundancy in the core cooling system that is not available in gas or liquid-metal cooled reactors. Detailed investigation of the consequences of heat pipe failures has resulted in modifications to the basic reactor design and has led to consideration of an entirely different core design. The new design features an integral laminated core configuration consisting of alternating layers of UO 2 and molybdenum sheets that span the entire diameter of the core. Design characteristics are presented and compared for the two reactors

  12. Design approaches for enhancing the engineering feasibility of tokamak power reactors

    International Nuclear Information System (INIS)

    Shannon, T.E.; Steiner, D.

    1977-01-01

    The design approach developed in the ORNL Fusion Power Demonstration Study is reviewed. The design concepts having greatest impact on reactor feasibility by the application of current or near term technology are described briefly. These are: blanket structural material, blanket coolant, power conversion system, and pulsed electrical system. Concepts relative to the approach taken to simplify the overall reactor design are listed

  13. Electric power monthly, April 1991

    International Nuclear Information System (INIS)

    1991-01-01

    The Electric Power Monthly (EPM) presents monthly summaries of electric utility statistics at the national Census division, and State level. The purpose of this publication is to provide energy decision makers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data are given for net generation, fuel consumption, fuel stocks, quantity and quality of fuel, cost of fuel, electricity sales, revenue, and average revenue per kilowatt hour of electricity sold. Data on net generation are also displayed at the North American Electric Reliability Council (NERC) region level. Additionally, statistics at the company and plant level are published in the EPM on capability of new plants, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fuel. 6 figs., 57 tabs

  14. Summary of the electric power supply program for fiscal 1981

    International Nuclear Information System (INIS)

    Shimada, Minoru

    1981-01-01

    The plans of electric power supply for fiscal 1981 (from April, 1981, to March, 1982) by the power companies were formulated and submitted to the Ministry of International Trade and Industry. Along with the current up trend of economic activities, the demands of electric power will be on the increase. A summer peak of power consumption may rise all the more due to the increase in room-cooling units. On the other hand, the problem of petroleum is unsettled. Under the situation, the principal considerations behind the formulation of the plans are the effective utilization of other energy resources than oil and the suppression of oil-burning power generation, the economical usage of all power generation facilities and stabilized demand and supply, and the promotion of wide-area operation. The situation in fiscal 1981, power demands, power source facilities demand and supply balance, and the interchange of power among power companies are described. (J.P.N.)

  15. Tariffs on power supply and prices of electricity per 1st January 1994

    International Nuclear Information System (INIS)

    1994-04-01

    The document gives a survey of the most usual types of tariffs connected with the Danish electric-power distribution companies and the prices, valid per January 1st, 1994, set by individual companies and also the cost to consumers of connection to the supply network. A survey of prices set by power plant administrators with regard to the distribution companies is also included in addition to a summary of the modes of calculation in connection with wind turbines not owned by the electricity companies and descriptions of models for calculations related to decentral and industrial plants. Local conditions such as structure, economy etc. must be taken into consideration when comparing prices set by companies in several different areas. (AB)

  16. 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)

  17. NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

    International Nuclear Information System (INIS)

    1994-08-01

    The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  18. SBWR: A simplified boiling water reactor

    International Nuclear Information System (INIS)

    Duncan, J.D.; Sawyer, C.D.; Lagache, M.P.

    1987-01-01

    An advanced light water reactor concept is being developed for possible application in the 1990's. The concept, known as SBWR is a boiling water reactor which uses natural circulation to provide flow to the reactor core. In an emergency, a gravity driven core cooling system is used. The reactor is depressurized and water from an elevated suppression pool flows by gravity to the reactor vessel to keep the reactor core covered. The concept also features a passive containment cooling system in which water flows by gravity to cool the suppression pool wall. No operator action is required for a period of at least three days. Use of these and other passive systems allows the elimination of emergency diesel generators, core cooling pumps and heat removal pumps which is expected to simplify the plant design, reduce costs and simplify licensing. The concept is being developed by General Electric, Bechtel and the Massachusetts Institute of Technology supported by the Electric Power Research Institute and the United States Department of Energy in the United States. In Japan, The Japan Atomic Power Company has a great interest in this concept

  19. Small space reactor power systems for unmanned solar system exploration missions

    International Nuclear Information System (INIS)

    Bloomfield, H.S.

    1987-12-01

    A preliminary feasibility study of the application of small nuclear reactor space power systems to the Mariner Mark II Cassini spacecraft/mission was conducted. The purpose of the study was to identify and assess the technology and performance issues associated with the reactor power system/spacecraft/mission integration. The Cassini mission was selected because study of the Saturn system was identified as a high priority outer planet exploration objective. Reactor power systems applied to this mission were evaluated for two different uses. First, a very small 1 kWe reactor power system was used as an RTG replacement for the nominal spacecraft mission science payload power requirements while still retaining the spacecraft's usual bipropellant chemical propulsion system. The second use of reactor power involved the additional replacement of the chemical propulsion system with a small reactor power system and an electric propulsion system. The study also provides an examination of potential applications for the additional power available for scientific data collection. The reactor power system characteristics utilized in the study were based on a parametric mass model that was developed specifically for these low power applications. The model was generated following a neutronic safety and operational feasibility assessment of six small reactor concepts solicited from U.S. industry. This assessment provided the validation of reactor safety for all mission phases and generatad the reactor mass and dimensional data needed for the system mass model

  20. Concerning installation of reactor at Noto nuclear power plant of Hokuriku Electric Power Co., Inc. (reply to inquiry)

    International Nuclear Information System (INIS)

    1988-01-01

    In response to an inquiry on the conformity of the title issue to the applicable law concerning nuclear material, nuclear fuel and nuclear reactor, the Nuclear Safety Commission ordered the Nuclear Reactor Safety Expert Group to make a study, made an examination after receiving a report from the Group, and submit the findings to the Minister of International Trade and Industry. The study on the site conditions covered the site location, geology, effects or earthquakes, meteorology, hydrology and social environment. The study on the safety design of the reactor covered the design of the facilities as a whole, anti-earthquake design, reactor, instrumentation, reactor shutdown system, reactivity control, protection, cooling system, reactor vessel, fuel handling, fuel storage, and radiation control. The study also included exposure evaluation, abnormal transient state analysis and accident analysis. It is concluded that the relevant company has a technical capability required for the installation and proper operation of the reactor in question, and that the reactor will have adequate safety with no possibility of causing a disaster. (Nogami, K.)

  1. Electric power transmission system: A new expansion scheme

    International Nuclear Information System (INIS)

    Unidad de Planeacion Minero Energetica, UPME

    2000-01-01

    With the purpose of responding to the interconnection requirements among the main cities of the country, a company of public character was created, in charge of the planning and of the development of the national interconnected system (NIS), in such form that their work optimized the use of the available energy resources for the electricity supply and it improved the accounting levels and quality of the service. Starting from 1967, interconnection electric Corp., ISA, a very important task began in the development of methodologies and strategies of expansion of the INS that it allowed, in very short term, to connect the areas of Bogota the Atlantic Cost, Antioquia and the Cauca Valley and to develop important generation projects for the supply of electric power of the country. Then, the electric sector was reformed through the laws 142 and 143 of 1994, in search of the specialization of the business and in that sense, ISA is divided in two companies: ISAGEN that the activities degeneration and electric power commercialization, and ISA, company electric power transport, that it takes charge of the interconnection of the national system assumes. In connection with the execution of the transmission works and in the face of the possibility of lingering courts of energy, the law establishes that ISA will carry out the works that are needed and that the particular initiative doesn't develop. For that same time, it is considered that the planning should be carried out in an integral way, taking into account the requirements of the population's energy and its possibilities of supply and through programs and actions of appropriate use of the available energy resources. The UPME (Unit of Planning Miner Energetic) was created for assumes this work, so with their analyses they already offer signs to the state the investors, about the population's necessities and of the business opportunities, respectively

  2. Power generation versus fuel production in light water hybrid reactors

    International Nuclear Information System (INIS)

    Greenspan, E.

    1977-06-01

    The economic potentials of fissile-fuel-producing light-water hybrid reactors (FFP-LWHR) and of fuel-self-sufficient (FSS) LWHR's are compared. A simple economic model is constructed that gives the capital investment allowed for the hybrid reactor so that the cost of electricity generated in the hybrid based energy system equals the cost of electricity generated in LWR's. The power systems considered are LWR, FSS-LWHR, and FFP-LWHR plus LWR, both with and without plutonium recycling. The economic potential of FFP-LWHR's is found superior to that of FSS-LWHR's. Moreover, LWHR's may compete, economically, with LWR's. Criteria for determining the more economical approach to hybrid fuel or power production are derived for blankets having a linear dependence between F and M. The examples considered favor the power generation rather than fuel production

  3. A small-scale modular reactor for electric source for remote places

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    Use of a small-scale modular reactor (SMR) as an electric source for remote places is one of scenarios for actual use of SMR parallel to alternative source of present nuclear power stations and co-generation source at urban suburbs, there is not only an actual experience to construct and operate for power source for military use in U.S.A. on 1950s to 1960s, but also four nuclear reactors (LWGR, 12 MW) in Vilyvino Nuclear Power Station in far northern district in Russia are under operation. Recently, Department of Energy in U.S.A. prepared the 'Report to Congress on Small Modular Nuclear Reactors' evaluating on feasibility of SMR as a power source for remote places according to requirement of the Congress. This report evaluated a feasibility study on nine SMRs in the world with 10 to 50 MW of output as electric source for remote places on economical efficiency and so on, together with analysis of their design concepts, to conclude that 'they could perform beginning of operations on 2000s because of no large technical problems and keeping a level capable of competing with power generation cost at remote place on its present economical efficiency'. Here was introduced on outlines of this report. (G.K.)

  4. THE PHASE REACTOR INDUCTANCE SELECTION TECHNIQUE FOR POWER ACTIVE FILTER

    Directory of Open Access Journals (Sweden)

    D. V. Tugay

    2016-12-01

    Full Text Available Purpose. The goal is to develop technique of the phase inductance power reactors selection for parallel active filter based on the account both low-frequency and high-frequency components of the electromagnetic processes in a power circuit. Methodology. We have applied concepts of the electrical circuits theory, vector analysis, mathematical simulation in Matlab package. Results. We have developed a new technique of the phase reactors inductance selection for parallel power active filter. It allows us to obtain the smallest possible value of THD network current. Originality. We have increased accuracy of methods of the phase reactor inductance selection for power active filter. Practical value. The proposed technique can be used in the design and manufacture of the active power filter for real objects of energy supply.

  5. Operational power reactor health physics

    International Nuclear Information System (INIS)

    Watson, B.A.

    1987-01-01

    Operational Health Physics can be comprised of a multitude of organizations, both corporate and at the plant sites. The following discussion centers around Baltimore Gas and Electric's (BG and E) Calvert Cliffs Nuclear Power Plant, located in Lusby, Maryland. Calvert Cliffs is a twin Combustion Engineering 825 MWe pressurized water reactor site with Unit I having a General electric turbine-generator and Unit II having a Westinghouse turbine-generator. Having just completed each Unit's ten-year Inservice Inspection and Refueling Outge, a total of 20 reactor years operating health physics experience have been accumulated at Calvert Cliffs. Because BG and E has only one nuclear site most health physics functions are performed at the plant site. This is also true for the other BG and E nuclear related organizations, such as Engineering and Quality Assurance. Utilities with multiple plant sites have corporate health physics entity usually providing oversight to the various plant programs

  6. Directions in advanced reactor technology

    International Nuclear Information System (INIS)

    Golay, M.W.

    1990-01-01

    Successful nuclear power plant concepts must simultaneously performance in terms of both safety and economics. To be attractive to both electric utility companies and the public, such plants must produce economical electric energy consistent with a level of safety which is acceptable to both the public and the plant owner. Programs for reactor development worldwide can be classified according to whether the reactor concept pursues improved safety or improved economic performance as the primary objective. When improved safety is the primary goal, safety enters the solution of the design problem as a constraint which restricts the set of allowed solutions. Conversely, when improved economic performance is the primary goal, it is allowed to be pursued only to an extent which is compatible with stringent safety requirements. The three major reactor coolants under consideration for future advanced reactor use are water, helium and sodium. Reactor development programs focuses upon safety and upon economics using each coolant are being pursued worldwide. These programs are discussed

  7. Study of the Utilization BWR Type Nuclear Power Reactor for Desalination Process

    International Nuclear Information System (INIS)

    Itjeu Karliana; Sumijanto; Dhandhang Purwadi, M.

    2008-01-01

    The needs of fresh water increased by rapid population growth and industrials expansion, but these demands can not be prepared naturally. Following this case, seawater desalination becomes the primer option which can fulfill the need through the nuclear desalination technology. The coupled nuclear power reactor enables to supply thermal energy for auxiliary equipment and pumps operation. The utilization study of power reactor type BWR coupled with desalination process has been performed. The goal of study is to obtain characteristic data of desalted water specification which desalination system coupling with nuclear power plant produced energy for desalination process. The study is carried out by browsing data and information, and comprehensive review of thermal energy correlation between NPP with desalination process installation. According to reviewing are found that the thermal energy and electric power utilization from the nuclear power reactor are enable to remove the seawater to produce desalted water and also to operate auxiliary equipments. The assessment results is VK-300 reactor prototype, BWR type 250 MW(e) power are cogeneration unit can supplied hot steam temperature 285 °C to the extraction turbine to empower 150 MW electric power, and a part of hot steam 130 °C is use to operate desalination process and remind heat is distribute to the municipal and offices at that region. The coupled of VK-300 reactor power type BWR with desalination installation of MED type enable to produce desalted water with high quality distillate. Based on the economic calculation that the VK-300 reactor power of BWR type produced water distillate capacity is 300.000 m 3 /hour with cost US$ 0.58/m 3 . The coupling VK-300 reactor power type BWR with MED desalination plant is competitive economically. (author)

  8. Change in plan for installation of nuclear reactor in Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in plan for No.3 and No.4 nuclear reactor facilities) (report)

    International Nuclear Information System (INIS)

    1987-01-01

    This report, compiled by the Nuclear Safety Commission to be submitted to the Minister of International Trade and Industry, deals with studies on a proposed change in the plan for the installation of nuclear reactors in the Genkai Nuclear Power Plant of Kyushu Electric Power Co., Inc. (change in the plan for the No.3 and No.4 nuclear reactor facilities). The conclusions of and principles for the examination and evaluation are described first. The studies carried out are focused on the safety of the facilities, and it is concluded that part of the proposed change is appropriate with respect to the required technical capability and that part of the change will not have adverse effects on the safety design of the facilities. The examination of the safety design of the reactor facilities cover the reactivity control, new material for the steam generator, design of chemical and volume control systems, design of liquid waste treatment facilities, integration of all confinement vessel spray rings, and design of the diesel power generator. It is confirmed that all of them can meet the safety requirements. Studies and analyses are also made of the emission of radiations to the surrounding environment, abnormal transient changes during operations, and possible accidents. (Nogami, K.)

  9. Results of photovoltaic power generation system operation in Tokyo Electric Power Company; Tokyo Denryoku ni okeru taiyoko hatsuden setsubi no unten jisseki ni tsuite

    Energy Technology Data Exchange (ETDEWEB)

    Fukuda, H; Itokawa, K [Tokyo Electric Power Co. Inc., Tokyo (Japan)

    1996-10-27

    A report was made on the measurement of data and the results of the analysis at 14 sites of photovoltaic power generation facilities operated under system interconnection by Tokyo Electric Power Company. This type of system is provided in 40 sites as of the end of fiscal 1995, generating 479kw. The items measured were the generated electric energy at all 14 sites, and the quantity of solar radiation, outside air temperature, panel temperature, etc., at limited sites; and the capacity of each equipment, azimuth and inclination of the panel were also recorded simultaneously. Hourly values were used for the analysis. Five minute values were utilized, however, in the examination of the cause of lowered output and in the situation recognition of the influence of the shade or the change of weather. The utilization factor of the facilities was in the average 10.8% in fiscal 1994 and 10.7% in fiscal 1995. The factor decreased slightly unless the panel azimuth faced due south. The utilization factor at the panel inclination of 35 degrees and 45 degrees showed both 10.4% through the year making no difference. The system seemed to show no overwhelming possibilities in coping with electric power demand. The reason was that deviation existed for 2 hours or so in the peak and that reliability was low as basic power facilities. However, it was determined that the system be continuously examined in future. 9 figs., 1 tab.

  10. Preliminary conceptual design of the blanket and power conversion system for the Mirror Hybrid Reactor

    International Nuclear Information System (INIS)

    Schultz, K.R.; Culver, D.W.; Rao, S.B.; Rao, S.R.

    1978-01-01

    A conceptual design of a commercial Mirror Hybrid Reactor, optimized for 239 Pu production, has been completed. This design is the product of a joint effort by Lawrence Livermore Laboratory and General Atomic Company, and follows directly from earlier work on the Mirror Hybrid. This paper describes the blanket and power conversion system of the reactor design. Included are descriptions of the prestressed concrete reactor vessel that supports the magnets and contains the blanket and power conversion system components, the blanket module design, the blanket fuel design, and the power conversion system

  11. Values in the electric power industry

    Energy Technology Data Exchange (ETDEWEB)

    Sayre, K. (ed.)

    1977-01-01

    A basic conclusion established by the seven essays presented is that nowhere within the complex decision-making process of the electric power industry is there any provision for systematically considering the curtailment of consumption as a serious alternative to continued expansion of power production. Six recommendations are summarized for concrete steps toward remedying this deficiency as a result of examining the essays. Continued expansion of power generation could result in desirable consequences of economic growth, jobs, ready transportation, and many consumer conveniences; undesirable consequences are: increasing air and water pollution, further depletion of nonrenewable resources, and increased dependence on foreign sources of energy. The papers are: A Cybernetic Analysis of Certain Energy Consumption Patterns, by Kenneth Sayre; Social and Environmental Value in Power Plant Licensing: A Study in the Regulation of Nuclear Power by Vaughn McKim; Legal and Economic Aspects of the Electric Utility's ''Mandate to Serve'', by Charles Murdock; Economies of Scale in the Electric Power Industry, by Kenneth Jameson; Dynamics of Growth in the U.S. Electric Power Industry, by Ellen Maher; Utilitarianism and Cost-Benefit Analysis: An Essay on the Relevance of Moral Philosophy to Bureaucratic Theory, by Alasdair MacIntyre; and An Ethical Analysis of Power Company Decision-Making, by Kenneth Goodpaster and Kenneth Sayre. (MCW)

  12. Small Modular Reactors for Countries with Small to Medium Electric Grids - An Economically Sensible Solution

    International Nuclear Information System (INIS)

    Young, P.

    2012-01-01

    There has recently been a renewed interest throughout the world in small nuclear units for generating electricity and for other applications. A report by the World Nuclear Association discussing the advantages of small modular nuclear reactors (SMRs) over traditional nuclear reactor designs, states that ''modern small reactors for power generation are expected to have greater simplicity of design, economy of mass production, and reduced siting costs. Many are also designed for a high level of passive or inherent safety in the event of malfunction.'' Since the inception of nuclear power, the size of reactor units has grown from under 100 MWe to more than 1600 MWe. Today, due partly to the high capital cost of large power reactors and partly to the need to service small electricity grids, there is a move to develop smaller units. These may be built individually or as modules in a larger plant. SMRs are a good fit in markets where anticipated electricity demand is projected to increase incrementally, because SMRs could be built in series as needed. SMRs might be particularly attractive in countries that currently rely on diesel generators for producing electricity. Small reactors could make economic sense because of the high cost of diesel generation compared to the low marginal cost of producing electricity from nuclear energy. (Keeping in mind the initial investment costs and the need to establish a national regulatory program.) Some SMR designs are fabricated in a factory and then delivered to the site. This could be a solution for markets that lack the qualified engineers and skilled craft workers needed to construct large reactors on site. This paper will provide an overview of the types and attributes of SMRs in use or under development worldwide, describe the similarities and important differences between designs, discuss potential applications for SMRs, including baseload electricity generation, electricity generation for remote locations and areas with

  13. Industrial companies' demand for electricity. Evidence from a micropanel

    International Nuclear Information System (INIS)

    Bjoerner, T.B.; Togeby, M.; Jensen, H.H.

    2001-01-01

    The paper presents a micro-econometric analysis of industrial companies' demand for electricity. Previous studies on electricity consumption in the industrial sector have relied on aggregate data or cross-section observations. Here we present an econometric study on electricity demand based on a panel of 2949 Danish companies followed from 1983 to 1996. It is found that estimators of electricity demand that take account of the panel structure (fixed effect models) yield considerably lower price and production elasticities compared to estimators that do not (like cross-section models). It is also investigated how various company characteristics like size, type of industrial sub-sector and electricity intensity in production influence price and production elasticities. It appears that companies with a high electricity intensity also have a high own-price elasticity

  14. Transforming Ontario's Power Generation Company

    International Nuclear Information System (INIS)

    Manley, J.; Epp, J.; Godsoe, P.C.

    2004-01-01

    The OPG Review Committee was formed by the Ontario Ministry of Energy to provide recommendations and advice on the future role of Ontario Power Generation Inc. (OPG) in the electricity sector. This report describes the future structure of OPG with reference to the appropriate corporate governance and senior management structure. It also discusses the potential refurbishing of the Pickering A nuclear generating Units 1, 2 and 3. The electricity system in Ontario is becoming increasingly fragile. The province relies heavily on electricity imports and the transmission system is being pushed to near capacity. Three nuclear generating units are out of service. The problems can be attributed to the fact that the electricity sector has been subjected to unpredictable policy changes for more than a decade, and that the largest electricity generator (OPG) has not been well governed. OPG has had frequent senior management change, accountability has been weak, and cost overruns have delayed the return to service of the Pickering nuclear power Unit 4. It was noted that the generating assets owned and operated by OPG are capable of providing more than 70 per cent of Ontario's electricity supply. Decisive action is needed now to avoid a potential supply shortage of about 5,000 to 7,000 megawatts by 2007. In its current state, OPG risks becoming a burden on ratepayers. Forty recommendations were presented, some of which suggest that OPG should become a rate-regulated commercial utility focused on running and maintaining its core generating assets. This would require that the government act as a shareholder, and the company operate like a commercial business. It was also emphasized that the market must be allowed to bring in new players. refs., tabs., figs

  15. Green marketing in the Massachusetts electric company retail competition pilot program

    Energy Technology Data Exchange (ETDEWEB)

    Rothstein, S.M.; Fang, J.M.

    1997-10-01

    With electric industry restructuring initiatives being introduced on the state and federal levels, retail access pilot programs serve an important function for examining competitive market issues, as well as marketing strategies and customer reactions to different power supply options. The experience gained through these pilots provides important insights into future power market operations, including the market for green power. The Massachusetts Electric Company`s (MECo`s) Choice: New England pilot for residential and small-business customers was a voluntary program developed primarily to test the billing and metering logistics that distribution companies will need in the competitive market. The pilot also offered a preview of program implementation and marketing under customer choice. It was the first retail competition pilot to explicitly include green power options in program design. The MECo pilot`s energy suppliers were selected through the issuance of a request for proposals (RFP). Respondents were asked to submit bids in one or more of three energy supply categories-price, green, and other options. These options were developed by the pilot administrator through internal meetings, discussions with state officials and other stakeholders, and a review of information from other similar pilots. For the green option, the pilot administrator did not establish a green standard. Instead, suppliers were allowed to submit offers that promoted environmental stewardship. Customer response to the different green options are reported. The pilot results clearly demonstrate that, in a competitive situation, there is interest in a variety of energy supply options, including green options. 2 tabs.

  16. Demonstration tokamak fusion power plant for early realization of net electric power generation

    International Nuclear Information System (INIS)

    Hiwatari, R.; Okano, K.; Asaoka, Y.; Shinya, K.; Ogawa, Y.

    2005-01-01

    A demonstration tokamak fusion power plant Demo-CREST is proposed as the device for early realization of net electric power generation by fusion energy. The plasma configuration for Demo-CREST is optimized to satisfy the electric breakeven condition (the condition for net electric power, P e net = 0 MW) with the plasma performance of the ITER reference operation mode. This optimization method is considered to be suitable for the design of a demonstration power plant for early realization of net electric power generation, because the demonstration power plant has to ensure the net electric generation. Plasma performance should also be more reliably achieved than in past design studies. For the plasma performance planned in the present ITER programme, net electric power from 0 to 500 MW is possible with Demo-CREST under the following engineering conditions: maximum magnetic field 16 T, thermal efficiency 30%, NBI system efficiency 50% and NBI current drive power restricted to 200 MW. By replacing the blanket system with one of higher thermal efficiency, a net electric power of about 1000 MW is also possible so that the performance of the commercial plant with Demo-CREST can also be studied from the economic point of view. The development path from the experimental reactor 'ITER' to the commercial plant 'CREST' through the demonstration power plant 'Demo-CREST' is proposed as an example of the fast track concept. (author)

  17. Maximizing the transferred power to electric arc furnace for having maximum production

    International Nuclear Information System (INIS)

    Samet, Haidar; Ghanbari, Teymoor; Ghaisari, Jafar

    2014-01-01

    In order to increase production of an EAF (electric arc furnace) by reduction of melting time, one can increase transferred power to the EAF. In other words a certain value of energy can be transferred to the EAF in less time. The transferred power to the EAF reduces when series reactors are utilized in order to have stable arc with desired characteristics. To compensate the reduced transferred power, the secondary voltage of the EAF transformer should be increased by tap changing of the transformer. On the other hand, after any tap changing of the EAF transformer, improved arc stability is degraded. Therefore, the series reactor and EAF transformer tap changing should be simultaneously determined to achieve arc with desired characteristics. In this research, three approaches are proposed to calculate the EAF system parameters, by which the optimal set-points of the different series reactor and EAF transformer taps are determined. The electric characteristics relevant to the EAF for the all transformer and series reactor taps with and without SVC (static VAr compensator) are plotted and based on these graphs the optimal set-points are tabulated. Finally, an economic evaluation is also presented for the methods. - Highlights: • The main goal is to transfer the maximum power to electric arc furnace. • Optimal transformer and series reactor taps are determined. • Arc stability and transferred power to EAF determine the optimal performance. • An economic assessment is done and the number of increased meltings is calculated

  18. Fusion neutronics plan in the development of fusion reactor. With the aim of realizing electric power

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Hiroo; Morimoto, Yuichi; Ochiai, Kentarou; Sugimoto, Masayoshi; Nishitani, Takeo; Takeuchi, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-10-01

    On June 1992, Atomic Energy Commission in Japan has settled Third Phase Program of Fusion Research and Development to achieve self-ignition condition, to realize long pulse burning plasma and to establish basis of fusion engineering for demonstration reactor. This report describes research plan of Fusion Neutron Laboratory in JAERI toward a development of fusion reactor with an aim of realizing electric power. The fusion neutron laboratory has a fusion neutronics facility (FNS), intense fusion neutron source. The plan includes research items in the FNS; characteristics of shielding and breeding materials, nuclear characteristics of materials, fundamental irradiation process of insulator, diagnostics materials and structural materials, and development of in-vessel diagnostic technology. Upgrade of the FNS is also described. Also, the International Fusion Material Irradiation Facility (IFMIF) for intense neutron source to develop fusion materials is described. (author)

  19. Potential of light water reactors for future nuclear power plants

    International Nuclear Information System (INIS)

    Gueldner, R.

    2003-01-01

    Energy consumption worldwide is going to increase further in the next few decades. Reliable supplies of electricity can be achieved only by centralized power plant structures. In this scenario, nuclear power plants are going to play a leading role as reliable and competitive plants, also under deregulated market conditions. Today, light water reactors have achieved a leading position, both technically and economically, contributing 85% to worldwide electricity generation in nuclear plants. They will continue to be a proven technology in power generation. In many countries, activities therefore are concentrated on extending the service life of plants beyond a period of forty years. New nuclear generating capacities are expected to be created and added from the end of this decade onward. Most of this capacity will be in light water reactors. The concepts of third-generation reactors will meet all economic and technical safety requirements of the 21st century and will offer considerable potential for further development. Probably some thirty years from now, fourth-generation nuclear power plants will be ready for commercial application. These plants will penetrate especially new sectors of the energy markets. Public acceptance of new nuclear power plants is not a matter of reactor lines, provided that safety requirements are met. The important issue is the management of radioactive waste. The construction of new nuclear power plants in Western Europe and North America mainly hinges on the ability to explain to the public that there is a need for new plants and that nuclear power is fundamental to assuring sustainable development. (orig.)

  20. The new tariff model based on marginal costs developing concept for Brazilian electric sector. A case study for Power and Light Company of Sao Paulo State (Brazil)

    International Nuclear Information System (INIS)

    Correia, S.P.S.

    1991-01-01

    A new methodology for power generation cost accounts in Brazilian electric sector is described, with the application of marginal costs theory and its deviation in developing economies. A case report from a Brazilian Power and Light Company is studied, focalizing the seasoning, the planning, the tariff model and the power generation, transmission and distribution. (M.V.M.). 19 refs, 28 figs, 1 tab

  1. Mini-cavity plasma core reactors for dual-mode space nuclear power/propulsion systems

    International Nuclear Information System (INIS)

    Chow, S.

    1976-01-01

    A mini-cavity plasma core reactor is investigated for potential use in a dual-mode space power and propulsion system. In the propulsive mode, hydrogen propellant is injected radially inward through the reactor solid regions and into the cavity. The propellant is heated by both solid driver fuel elements surrounding the cavity and uranium plasma before it is exhausted out the nozzle. The propellant only removes a fraction of the driver power, the remainder is transferred by a coolant fluid to a power conversion system, which incorporates a radiator for heat rejection. In the power generation mode, the plasma and propellant flows are shut off, and the driver elements supply thermal power to the power conversion system, which generates electricity for primary electric propulsion purposes

  2. 'Nuclearelectrica' Company messages for a broadly acceptable nuclear power program

    International Nuclear Information System (INIS)

    Stiopol, Mihaela; Bilegan, C. Iosif

    2001-01-01

    Romania started the nuclear power program about 20 years ago, by a high level Government decision. After 1989 the former Ministry of Electrical Power was transformed into a state owned company, RENEL, in which nuclear activities were also included. RENEL was a monopoly system responsible for production, transport and distribution of electricity in Romania. The deregulation process in the power sector was many times asked by the World Bank and International Monetary Fund, to split this monopoly system in separately activities: Production, Transport and Distribution. The first step occurred in July 1998, when the nuclear activities were externalized from RENEL. In nuclear sector two new entities were created: SN 'Nuclearelectrica' SA, a state own company that includes three branches: - Nuclear Power Production - Cernavoda NPP Unit 1; - Nuclear Fuel Plant-Pitesti; - Project Development Branch - Cernavoda Units 2-5. The second entity is the so-called Romanian Authority (Autonomous Reggie) for Nuclear Activities (RAAN), including as branches the heavy water fabrication plant 'ROMAG PROD', the Nuclear Research Institute (ICN) Pitesti and the Nuclear Engineering and Design Institute (CITON) Bucharest. The rest of conventional power sector was renamed, namely, CONEL. The organization process continued and in August 2000, by a Government Ordinance the CONEL was split into the following companies: - one for hydropower production 'HIDROELECTRICA'; - one for thermal power production 'TERMOELECTRICA'; - one for transport 'TRANSELECTRICA'; - one for distribution 'ELECTRICA'. The goal of a third step of restructuring process is the privatization in the power field. The steps of Romanian Power Sector Restructuring are presented. Since 1991 a Public Information program has been established. Depending on the evolution of the construction of the first Romanian nuclear power station, during the years, the messages changed. Everybody working in the nuclear field knows how difficult is

  3. Characteristics of Soil Structure Interaction for Reactor Building of Kashiwazaki-Kariwa Nuclear Power Plant

    International Nuclear Information System (INIS)

    Gil, Moon Joo; Jung, Rae Young; Hyun, Chang Hun; Kim, Moon Soo; Lim, Nam Hyoung

    2010-01-01

    On 16 July 2007, the Nigataken-chuetsu-oki earthquake registering a moment magnitude of 6.8 occurred at a depth of about 15 km. As a result of this earthquake, noticeable shaking exceeding the design ground motion was measured at the Tokyo Electric Power Company (TEPCO) Kashiwazaki-Kariwa Nuclear Power Station (KKN), the biggest nuclear power plant in the world, located at about 16 km away from the epicenter. This earthquake triggered a fire at an electrical transformer and insignificant damage on some parts of facilities. This event gave an impulse to study on the damage and safety margin of nuclear power plant due to the strong earthquake exceeding design basis. As a part of those efforts, KARISMA (KAshiwazaki-Kariwa Research Initiative for Seismic Margin Assessment) benchmark study was launched by the IAEA in terms of an international collaborative research. The main objectives of this research are to estimate the structural behavior and to evaluate the seismic margin of reactor building considering the effects of Soil-Structure Interaction (SSI). This paper presents verification of structural model developed here and validation of soil foundation characteristics through soil-column analysis. It has also been demonstrated that the spring constants and damping coefficient obtained from impedance analysis represent well the soil foundation characteristics

  4. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S [ed.

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

  5. Operating Experience at the Aagesta Nuclear Power Station

    International Nuclear Information System (INIS)

    Sandstroem, S.

    1966-09-01

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW t ) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965

  6. Operating Experience at the Aagesta Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S. (ed.)

    1966-09-15

    Sweden's first nuclear power reactor Agesta, achieved criticality on July 17, 1963. Full power (65 MW{sub t}) was attained on March 20, 1964. Aagesta is a heavy water cooled and moderated pressure vessel reactor used for production of electricity as well as for district heating. The design, assembly and construction etc, of the reactor was described in detail in a staff report by AB Atomenergi, 'The Aagesta Nuclear Power Station' edited by B McHugh, which was published in September, 1964. In the book experiences from the commissioning and the first operation of the reactor were reported as well as findings from the extensive reactor physics studies made during this period. The report now presented is written by members of the operating team at Aagesta since its start. It reflects in general the experiences up to the end of 1965. The Aagesta Log, however, covers the period up to the normal summer stop 1966. The reactor has hitherto produced 506,000 MWh power of which 48,700 MWh have been electric power. In July 1965 the responsibility for the reactor operation was taken over by the Swedish State Power Board from AB Atomenergi, which company had started the reactor and operated it until the summer break 1965.

  7. Empirical assessment of market power in the Alberta wholesale electricity market

    International Nuclear Information System (INIS)

    Qu, F.

    2007-01-01

    In the 1990s, many countries began to unbundle regulated electricity monopolies into generation, transmission, distribution and retail companies. Transmission and distribution services remained regulated, but generation and retail services were open for competition. Wholesale and retail electricity markets were created. This paper presented a newly developed competitiveness index specifically for the Alberta market through a simple and standard economic approach. The Alberta Electric Utilities Act came into effect in January 1996. This paper described how the Alberta wholesale electricity market works and demonstrated how to model market power in the electricity market. In this study, power generating companies in Alberta were divided into 2 groups. The first group contained the 5 largest firms called strategic firms, while the other group contained the small generating companies called non-strategic firms or the competitive fringe. In the sample years 2003 and 2004, strategic firms withheld capacity when price was above marginal cost and behaved within the range of competitive pricing. They were more likely to price competitively than to use unilateral market power prices. In addition, firms had higher price-cost margins during the off-peak season. This paper explained in detail the reason for this unusual off-peak pattern. The index to measure a firm's strategic behaviour in the Alberta electricity market was developed according to price-cost margin data where firm-behaviour effect was distinguished from the demand-elasticity effect. It was concluded that policy-makers and regulations should consider the magnitude and source of market power when designing market structure, rules and trading practices. 9 refs., 5 tabs., 2 figs

  8. Extension of cycle 8 of Angra-1 reactor, optimization of electric power generation reduction

    International Nuclear Information System (INIS)

    Miranda, Anselmo Ferreira; Moreira, Francisco Jose; Valladares, Gastao Lommez

    2000-01-01

    The main objective of extending fuel cycle length of Angra-1 reactor, is in fact of that each normal refueling are changed about 40 fuel elements of the reactor core. Considering that these elements do not return for the reactor core, this procedure has became possible a more gain of energy of these elements. The extension consists in, after power generation corresponding to a cycle burnup of 13700 MWD/TMU or 363.3 days, to use the reactivity gain by reduction of power and temperature of primary system for power generation in a low energy patamar

  9. Evaluation of lifecycle CO2 emissions from the Japanese electric power sector in the 21st century under various nuclear scenarios

    International Nuclear Information System (INIS)

    Tokimatsu, Koji; Kosugi, Takanobu; Asami, Takayoshi; Williams, Eric; Kaya, Yoichi

    2006-01-01

    The status and prospects of the development of Japanese nuclear power are controversial and uncertain. Many deem that nuclear power can play key roles in both supplying energy and abating CO 2 emissions; however, due to severe nuclear accidents, public acceptance of nuclear power in Japan has not been fully obtained. Moreover, deregulation and liberalization of the electricity market impose pressure on large Japanese electric power companies with regard to both the operation of nuclear power plants and the development of the nuclear fuel cycle. Long-term Japanese CO 2 reduction strategies up to 2100 are of environmental concern and are socially demanded under the circumstances described above. Taking these factors into account, we set the following two objectives for this study. One is to estimate lifecycle CO 2 (LCCO 2 ) emissions from Japanese nuclear power, and the other is to evaluate CO 2 emissions from the Japanese electric power sector in the 21st century by quantifying the relationship between LCCO 2 emissions and scenarios for the adoption of nuclear power. In the pursuit of the above objectives, we first create four scenarios of Japanese adoption of nuclear power, that range from nuclear power promotion to phase-out. Next, we formulate four scenarios describing the mix of the total electricity supply in Japan till the year 2100 corresponding to each of these nuclear power scenarios. CO 2 emissions from the electric power sector in Japan till the year 2100 are estimated by summing those generated by each respective electric power technology and LCCO 2 emission intensity. The LCCO 2 emission intensity of nuclear power for both light water reactors (LWR) and fast breeder reactors (FBR) includes the uranium fuel production chain, facility construction/operation/decommission, and spent fuel processing/disposal. From our investigations, we conclude that the promotion of nuclear power is clearly a strong option for reducing CO 2 emissions by the electric power

  10. Nuclear power reactors

    International Nuclear Information System (INIS)

    1982-11-01

    After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

  11. A Game Theoretical Approach Based Bidding Strategy Optimization for Power Producers in Power Markets with Renewable Electricity

    Directory of Open Access Journals (Sweden)

    Yi Tang

    2017-05-01

    Full Text Available In a competitive electricity market with substantial involvement of renewable electricity, maximizing profits by optimizing bidding strategies is crucial to different power producers including conventional power plants and renewable ones. This paper proposes a game-theoretic bidding optimization method based on bi-level programming, where power producers are at the upper level and utility companies are at the lower level. The competition among the multiple power producers is formulated as a non-cooperative game in which bidding curves are their strategies, while uniform clearing pricing is considered for utility companies represented by an independent system operator. Consequently, based on the formulated game model, the bidding strategies for power producers are optimized for the day-ahead market and the intraday market with considering the properties of renewable energy; and the clearing pricing for the utility companies, with respect to the power quantity from different power producers, is optimized simultaneously. Furthermore, a distributed algorithm is provided to search the solution of the generalized Nash equilibrium. Finally, simulation results were performed and discussed to verify the feasibility and effectiveness of the proposed non-cooperative game-based bi-level optimization approach.

  12. Safety evaluation report related to the operation of Catawba Nuclear Station, Units 1 and 2. Docket Nos. 50-413 and 50-414, Duke Power Company, et al

    International Nuclear Information System (INIS)

    1983-02-01

    The Safety Evaluation Report for the application filed by Duke Power Company, North Carolina Municipal Power Agency Number 1, North Carolina Electric Membership Corporation, and Saluda River Electric Cooperative, Inc. as applicants and owners, for licenses to operate the Catawba Nuclear Station, Units 1 and 2 (Docket Nos. 50-413 and 50-414), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in York County, South Carolina, approximately 9.6 km (6 mi) north of Rock Hill and adjacent to Lake Wylie. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can be operated by the applicant without endangering the health and safety of the public

  13. Decision of OLG Hamm of 1.7.81 concerning nonpayment of electric power from nuclear power plants

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    1. If the electricity consumer denies even in the second instance the right of the energy supply company to cut off the power and to break the contract, the energy supply company is naturally interested in bringing the matter concerning the contents of the two related parties' legal position, before court. 2. About the question whether a supply embargo offends the consitutional principle of proportionality. 3. By exercising the fundamental human right of defending one's conscientions beliefs by means of partial payment of the electricity bill the electricity consumer interferes with the energy supply company's basic right of freedom of business and violates it. By doing this the consumer goes beyond his basic rights making his move thereby inadmissable. 4. The power cut is not an action against the freedom of opinion but against a breach of the law that is inadmissable according to Art. 5 GG (section 5 Basic Law of the FRG). 5. About the admissability of the abrupt termination of a contract for the supply of electricity. (orig.) [de

  14. Nuclear safety. Concerns about the nuclear power reactors in Cuba

    International Nuclear Information System (INIS)

    Wells, Jim; Aloise, Gene; Flaherty, Thomas J.; Fitzgerald, Duane; Zavala, Mario; Hayward, Mary Alice

    1992-09-01

    In 1976, the Soviet Union and Cuba concluded an agreement to construct two 440-megawatt nuclear power reactors near Cienfuegos on the south central coast of Cuba, about 180 miles south of Key West, Florida. The construction of these reactors, which began around 1983, was a high priority for Cuba because of its heavy dependence on imported oil. Cuba is estimated to need an electrical generation capacity of 3,000 megawatts by the end of the decade. When completed, the first reactor unit would provide a significant percentage (estimated at over 15 percent) of Cuba's need for electricity. It is uncertain when Cuba's nuclear power reactors will become operational. On September 5, 1992, Fidel Castro announced the suspension of construction at both of Cuba's reactors because Cuba could not meet the financial terms set by the Russian government to complete the reactors. Cuban officials had initially planned to start up the first of the two nuclear reactors by the end of 1993. However, before the September 5 announcement, it was estimated that this reactor would not be operational until late 1995 or early 1996. The civil construction (such as floors and walls) of the first reactor is currently estimated to be about 90 percent to 97 percent complete, but only about 37 percent of the reactor equipment (such as pipes, pumps, and motors) has been installed. The civil construction of the second reactor is about 20 percent to 30 percent complete. No information was available about the status of equipment for the second reactor. According to former Cuban nuclear power and electrical engineers and a technician, all of whom worked at the reactor site and have recently emigrated from Cuba, Cuba's nuclear power program suffers from poor construction practices and inadequate training for future reactor operators. One former official has alleged, for example, that the first reactor containment structure, which is designed to prevent the accidental release of radioactive material into

  15. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

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

  16. Competitiveness through cooperation between electricity and information technology. TESLA - Information technology and electric power systems technology programme 1998-2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    The electricity markets are being opened up to competition all round the world. To succeed in competition electricity sellers want new information technology tools to use in managing the sale of electricity. The network companies are aiming to step up utilization of their distribution capacity and to optimize power quality and the reliability of supply. Consumers need solutions with which they can manage their own power consumption and tendering sellers. The Nordic countries have been the first to deregulate their electricity markets. This head start in time is being made use of to generate a head start in technology. Tekes has initiated a technology programme for the years 1998 to 2002, named TESLA - Information Technology and Electric Power Systems, to promote the competitiveness of the Finnish electricity industry in changing conditions. The objective of the programme is to adapt information technology extensively to power distribution and thus develop the potential for Finland`s electricity industry to succeed on world markets. At the moment power distribution technology forms about one third of Finland`s energy technology exports. The programme is also aimed at developing new data transfer and data processing applications for companies in information technology clusters. For Finnish parties in the electricity markets the programme will produce ways and means of (1) improving management and use of distribution networks, (2) implementing competition in electricity sales, and (3) increasing the efficiency of electricity use

  17. NSTX Electrical Power Systems

    International Nuclear Information System (INIS)

    A. Ilic; E. Baker; R. Hatcher; S. Ramakrishnan; et al

    1999-01-01

    The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physic Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect NSTX needs. The design of the NSTX electrical power system was tailored to suit the available infrastructure and electrical equipment on site. Components were analyzed to verify their suitability for use in NSTX. The total number of circuits and the location of the NSTX device drove the major changes in the Power system hardware. The NSTX has eleven (11) circuits to be fed as compared to the basic three power loops for TFTR. This required changes in cabling to insure that each cable tray system has the positive and negative leg of cables in the same tray. Also additional power cabling had to be installed to the new location. The hardware had to b e modified to address the need for eleven power loops. Power converters had to be reconnected and controlled in anti-parallel mode for the Ohmic heating and two of the Poloidal Field circuits. The circuit for the Coaxial Helicity Injection (CHI) System had to be carefully developed to meet this special application. Additional Protection devices were designed and installed for the magnet coils and the CHI. The thrust was to making the changes in the most cost-effective manner without compromising technical requirements. This paper describes the changes and addition to the Electrical Power System components for the NSTX magnet systems

  18. Station Blackout Analysis of HTGR-Type Experimental Power Reactor

    Science.gov (United States)

    Syarip; Zuhdi, Aliq; Falah, Sabilul

    2018-01-01

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

  19. Electric Power quality Analysis in research reactor: Impacts on nuclear safety assessment and electrical distribution reliability

    International Nuclear Information System (INIS)

    Touati, Said; Chennai, Salim; Souli, Aissa

    2015-01-01

    The increased requirements on supervision, control, and performance in modern power systems make power quality monitoring a common practise for utilities. Large databases are created and automatic processing of the data is required for fast and effective use of the available information. Aim of the work presented in this paper is the development of tools for analysis of monitoring power quality data and in particular measurements of voltage and currents in various level of electrical power distribution. The study is extended to evaluate the reliability of the electrical system in nuclear plant. Power Quality is a measure of how well a system supports reliable operation of its loads. A power disturbance or event can involve voltage, current, or frequency. Power disturbances can originate in consumer power systems, consumer loads, or the utility. The effect of power quality problems is the loss power supply leading to severe damage to equipments. So, we try to track and improve system reliability. The assessment can be focused on the study of impact of short circuits on the system, harmonics distortion, power factor improvement and effects of transient disturbances on the Electrical System during motor starting and power system fault conditions. We focus also on the review of the Electrical System design against the Nuclear Directorate Safety Assessment principles, including those extended during the last Fukushima nuclear accident. The simplified configuration of the required system can be extended from this simple scheme. To achieve these studies, we have used a demo ETAP power station software for several simulations. (authors)

  20. Electric Power quality Analysis in research reactor: Impacts on nuclear safety assessment and electrical distribution reliability

    Energy Technology Data Exchange (ETDEWEB)

    Touati, Said; Chennai, Salim; Souli, Aissa [Nuclear Research Centre of Birine, Ain Oussera, Djelfa Province (Algeria)

    2015-07-01

    The increased requirements on supervision, control, and performance in modern power systems make power quality monitoring a common practise for utilities. Large databases are created and automatic processing of the data is required for fast and effective use of the available information. Aim of the work presented in this paper is the development of tools for analysis of monitoring power quality data and in particular measurements of voltage and currents in various level of electrical power distribution. The study is extended to evaluate the reliability of the electrical system in nuclear plant. Power Quality is a measure of how well a system supports reliable operation of its loads. A power disturbance or event can involve voltage, current, or frequency. Power disturbances can originate in consumer power systems, consumer loads, or the utility. The effect of power quality problems is the loss power supply leading to severe damage to equipments. So, we try to track and improve system reliability. The assessment can be focused on the study of impact of short circuits on the system, harmonics distortion, power factor improvement and effects of transient disturbances on the Electrical System during motor starting and power system fault conditions. We focus also on the review of the Electrical System design against the Nuclear Directorate Safety Assessment principles, including those extended during the last Fukushima nuclear accident. The simplified configuration of the required system can be extended from this simple scheme. To achieve these studies, we have used a demo ETAP power station software for several simulations. (authors)

  1. Nuclear Power Reactor simulator - based training program

    International Nuclear Information System (INIS)

    Abdelwahab, S.A.S.

    2009-01-01

    nuclear power stations will continue playing a major role as an energy source for electric generation and heat production in the world. in this paper, a nuclear power reactor simulator- based training program will be presented . this program is designed to aid in training of the reactor operators about the principles of operation of the plant. also it could help the researchers and the designers to analyze and to estimate the performance of the nuclear reactors and facilitate further studies for selection of the proper controller and its optimization process as it is difficult and time consuming to do all experiments in the real nuclear environment.this program is written in MATLAB code as MATLAB software provides sophisticated tools comparable to those in other software such as visual basic for the creation of graphical user interface (GUI). moreover MATLAB is available for all major operating systems. the used SIMULINK reactor model for the nuclear reactor can be used to model different types by adopting appropriate parameters. the model of each component of the reactor is based on physical laws rather than the use of look up tables or curve fitting.this simulation based training program will improve acquisition and retention knowledge also trainee will learn faster and will have better attitude

  2. 10-75-kWe-reactor-powered organic Rankine-cycle electric power systems (ORCEPS) study. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    1977-03-30

    This 10-75 kW(e) Reactor-ORCEPS study was concerned with the evaluation of several organic Rankine cycle energy conversion systems which utilized a /sup 235/U-ZrH reactor as a heat source. A liquid metal (NaK) loop employing a thermoelectric converter-powered EM pump was used to transfer the reactor energy to the organic working fluid. At moderate peak cycle temperatures (750/sup 0/F), power conversion unit cycle efficiencies of up to 25% and overall efficiencies of 20% can be obtained. The required operating life of seven years should be readily achievable. The CP-25 (toluene) working fluid cycle was found to provide the highest performance levels at the lowest system weights. Specific weights varies from 100 to 50 lb/kW(e) over the power level range 10 to 75 kW(e). (DLC)

  3. Annual Report 1999. Electric power in Sweden

    International Nuclear Information System (INIS)

    2000-07-01

    Barsebaeck 1 was closed on 30 November 1999. Barsebaeck's output of approximately 4 TWh per year will primarily be replaced by imports from coal-fired plants in Denmark and Germany. During the year, the closure of Swedish fossil-fired condensing power stations continued. With that, over 3,000 MW of peak-load power has been shut down during recent years. Consequently, situations entailing shortages of power can arise. On the deregulated electricity market, it is only the system operators that have a satisfactory overview of the overall electricity balance. The Swedish Power Association has thus lobbied the government as regards the need to elucidate Svenska Kraftnaet's responsibility. In a governmental decision from December, Svenska Kraftnaet was given the task of, among other things, monitoring the available capacity during peak loads and developing market instruments that can contribute to safeguarding the availability of power during peak loads. Svenska Kraftnaet has acquired gas turbines with a combined output power of 400 MW from Vattenfall. In order to cover the remaining requirement for rapid disruption reserves, Svenska Kraftnaet also has agreements with several power producers regarding a further 800 MW of gas turbine capacity. One further possibility lies in agreements with industry regarding the disconnection of consumption during times of peak loading. On 1 January 2000, the nuclear power tax was increased by SEK 0.005 per kWh to SEK 0.027 per kWh. This means that the nuclear power companies pay approximately SEK 1,800 MSEK per year in fiscal taxation on their nuclear power generation. The tax on electrical energy, paid by the consumer, was raised by SEK 0.011 to SEK 0.162 per kWh. The tax on diesel fuel was increased at the same time by SEK 0.25 per litre. In addition, a special network fee of SEK 0.002 per kWh came into existence in order to finance small-scale electricity generation, following removal of the obligation-to-receive system. The Swedish

  4. Annual Report 1999. Electric power in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-15

    Barsebaeck 1 was closed on 30 November 1999. Barsebaeck's output of approximately 4 TWh per year will primarily be replaced by imports from coal-fired plants in Denmark and Germany. During the year, the closure of Swedish fossil-fired condensing power stations continued. With that, over 3,000 MW of peak-load power has been shut down during recent years. Consequently, situations entailing shortages of power can arise. On the deregulated electricity market, it is only the system operators that have a satisfactory overview of the overall electricity balance. The Swedish Power Association has thus lobbied the government as regards the need to elucidate Svenska Kraftnaet's responsibility. In a governmental decision from December, Svenska Kraftnaet was given the task of, among other things, monitoring the available capacity during peak loads and developing market instruments that can contribute to safeguarding the availability of power during peak loads. Svenska Kraftnaet has acquired gas turbines with a combined output power of 400 MW from Vattenfall. In order to cover the remaining requirement for rapid disruption reserves, Svenska Kraftnaet also has agreements with several power producers regarding a further 800 MW of gas turbine capacity. One further possibility lies in agreements with industry regarding the disconnection of consumption during times of peak loading. On 1 January 2000, the nuclear power tax was increased by SEK 0.005 per kWh to SEK 0.027 per kWh. This means that the nuclear power companies pay approximately SEK 1,800 MSEK per year in fiscal taxation on their nuclear power generation. The tax on electrical energy, paid by the consumer, was raised by SEK 0.011 to SEK 0.162 per kWh. The tax on diesel fuel was increased at the same time by SEK 0.25 per litre. In addition, a special network fee of SEK 0.002 per kWh came into existence in order to finance small-scale electricity generation, following removal of the obligation-to-receive system

  5. Care management at Ikata Power Station

    International Nuclear Information System (INIS)

    Sakai, Koji

    1982-01-01

    For operating nuclear power stations safely and economically, it is necessary to control nuclear fuel itself and reactor cores. Nuclear fuel must be controlled consistently in view of quantitative balance and operational method over the whole nuclear fuel cycle of uranium ore, fabrication, burning in reactors and reprocessing, based on the plan of using fuel in electric power companies. The control of the burning in reactors is called core management, and it is important because the users of fuel execute it. For dealing with such core management works, Shikoku Electric Power Co., Inc., has developed the computer code system for grasping the state of fuel exchange and the burning condition in reactors and used it since 1972. The outline of the core management in Ikata Power Station is reported in this paper centering around computing works. The core management works are divided into those at the time of regular inspection and those in operation. In the regular inspection, fuel inspection, fuel exchange and reactor physics test are performed. In operation, the burning condition of fuel is grasped. The technical computations corresponding to these works are explained, and the examples of computations are shown. (Kako, I.)

  6. 78 FR 72877 - Arkansas Electric Corporation v. Oklahoma Gas and Electric Company; Notice of Complaint

    Science.gov (United States)

    2013-12-04

    ... Electric Corporation v. Oklahoma Gas and Electric Company; Notice of Complaint Take notice that on November... Commission (Commission), 18 CFR 385.206, Arkansas Electric Corporation (Complainant) filed a formal complaint against Oklahoma Gas and Electric Company (Respondents), alleging that the Respondent's Production Formula...

  7. Planning and administration of human resources in Brazilian Electric Power Companies; Planejamento e administracao de recursos humanos nas empresas brasileiras do setor de energia eletrica

    Energy Technology Data Exchange (ETDEWEB)

    Dias, Devanir Vieira

    1985-12-01

    Administration and planning of human resources in Brazilian Companies of Electric Power Sector analyzes the evolution of the concept of business planning. This work explore the specific literature of this theme, giving emphasis in predict methods and human resources development and planning models. Is also presented a case study, realized in 1979, which comprehended 84 % of Brazilian Energy Companies. This study aims to evaluate the results of an implementation of this planning and development models 64 refs., 12 figs., 22 tabs.

  8. High Efficiency Nuclear Power Plants Using Liquid Fluoride Thorium Reactor Technology

    Science.gov (United States)

    Juhasz, Albert J.; Rarick, Richard A.; Rangarajan, Rajmohan

    2009-01-01

    An overall system analysis approach is used to propose potential conceptual designs of advanced terrestrial nuclear power plants based on Oak Ridge National Laboratory (ORNL) Molten Salt Reactor (MSR) experience and utilizing Closed Cycle Gas Turbine (CCGT) thermal-to-electric energy conversion technology. In particular conceptual designs for an advanced 1 GWe power plant with turbine reheat and compressor intercooling at a 950 K turbine inlet temperature (TIT), as well as near term 100 MWe demonstration plants with TITs of 950 and 1200 K are presented. Power plant performance data were obtained for TITs ranging from 650 to 1300 K by use of a Closed Brayton Cycle (CBC) systems code which considered the interaction between major sub-systems, including the Liquid Fluoride Thorium Reactor (LFTR), heat source and heat sink heat exchangers, turbo-generator machinery, and an electric power generation and transmission system. Optional off-shore submarine installation of the power plant is a major consideration.

  9. Gas-fired wind power and electric hydrogen

    OpenAIRE

    Hemmes, K.

    2006-01-01

    In the seemingly endless discussions about the pros and cons of wind power even its advocates have to agree that though wind can fly, with offshore wind farms soon to become reality, this only exacerbates the problem of the winds changeability. Even now the major producers of electricity and power grid companies foresee grave difficulties from the peaks and dips in supply of this green power source. Dr Kas Hemmes of the faculty of Systems Engineering, Policy Analysis, and Management at TU Del...

  10. Research and development activities for reactor decommissioning. Developing technology of Fuji Electric Co., Ltd

    International Nuclear Information System (INIS)

    Shirakawa, Masahiro; Takaya, Jyunichi; Mizukoshi, Seiji; Hosoda, Hiroshi; Tomizuka, Chiaki; Funaguchi, Susumu; Ito, Katsuhito

    1997-01-01

    Fuji Electric Co., Ltd. is conducting decommissioning R and D for commercial reactor, especially for gas cooled reactor since the construction of the Tokai-1 power station of JAPCO, in the field of system engineering, residual radioactivity evaluation, dismantling of core internals, remote handling, treatment and disposal of radioactive waste, and radioactivity measurement. These R and D have been performed mainly under contract of JAPCO and JAERI. This paper gives a summary of the present status and future plan concerning technical development for decommissioning of nuclear reactor by Fuji Electric Co., Ltd. (author)

  11. Maintenance management of nuclear power reactors at the stage of research and development

    International Nuclear Information System (INIS)

    Takaya, Shigeru; Chikazawa, Yoshitaka; Kubo, Shigenobu; Hayashida, Kiichi; Tagawa, Akihiro; Yamashita, Atsushi

    2016-07-01

    A maintenance management required to nuclear power reactors at the R and D stage was discussed in this report. It is the most important to ensure safety of nuclear power plants by taking account of characteristics of nuclear power reactors at the R and D stage. In addition, it is needed to establish a system of maintenance management technologies suitable for reactor types. In this report, objectives of maintenance management of nuclear power reactors at the R and D stage were clarified. Next, requirements and consideration for maintenance management of nuclear power reactors at the R and D stage were discussed according to the objectives. 'Code for Maintenance at Nuclear Power Plants' and 'Guide for Maintenance at Nuclear Power Plants' published by the Japan Electric Association were refereed in the discussion. Then, a draft of codes for maintenance management of nuclear power plants at the R and D stage was newly proposed. Finally, an example that the draft codes were applied to components containing sodium, typical components of sodium-cooled fast reactor, was presented. (author)

  12. Safety Evaluation Report related to the full-term operating license for Millstone Nuclear Power Station, Unit No. 1 (Docket No. 50-245)

    International Nuclear Information System (INIS)

    1985-10-01

    The Safety Evaluation Report for the full-term operating license application filed by the Connecticut Light and Power Company, the Hartford Electric Light Company, Western Massachusetts Electric Company and the Millstone Point Company [(now known as Connecticut Light and Power Company (CL and P) and Western Massachusetts Electric Company (WMECO) having authority to possess Millstone-1, 2, and 3, and the Northeast Nuclear Energy Company (NNECO) as the responsible entity for operation of the facilities)] for Millstone Nuclear Power Station Unit 1 has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. The facility is located in the town of Waterford, Connecticut. Subject to favorable resolution of the items discussed in this report, the staff concludes that the facility can continue to be operated without endangering the health and safety of the public

  13. 78 FR 72552 - Airworthiness Directives; General Electric Company Turbofan Engines

    Science.gov (United States)

    2013-12-03

    ... Airworthiness Directives; General Electric Company Turbofan Engines AGENCY: Federal Aviation Administration (FAA... General Electric Company model GEnx-2B67 and GEnx-2B67B turbofan engines. This AD was prompted by the... certain serial number General Electric Company (GE) model GEnx-2B67 and GEnx-2B67B turbofan engines. The...

  14. Method of bringing nuclear power plant to fractional electrical load conditions

    International Nuclear Information System (INIS)

    Iljunin, V.G.; Kuznetsoy, I.A.; Murogov, V.M.; Shmelev, A.N.

    1978-01-01

    A method is described of bringing a nuclear power plant to fractional electric load conditions, which power plant comprises at least two nuclear reactors, at least one nuclear reactor being a breeder and both reactors transferring heat to the turbine working substance, consisting in that the consumption of the turbine working substance is reduced in accordance with a predetermined fractional load. At the same time, the amount of heat being transferred from the nuclear reactors to the turbine working substance is reduced, for which purpose the reactors are included in autonomous cooling circuits to successively transfer heat to the turbine working substance. The breeding reactor is included in the cooling circuit with a lower coolant temperature, the temperature of the coolant at the inlet and outlet of the breeder being reduced to a level ensuring the operation of the nuclear power plant in predetermined fractional load conditions, due to which the power of the breeder is increased, and afterheat is removed

  15. Advances in commercial heavy water reactor power stations

    International Nuclear Information System (INIS)

    Brooks, G.L.

    1987-01-01

    Generating stations employing heavy water reactors have now firmly established an enviable record for reliable, economic electricity generation. Their designers recognize, however, that further improvements are both possible and necessary to ensure that this reactor type remains attractively competitive with alternative nuclear power systems and with fossil-fuelled generation plants. This paper outlines planned development thrusts in a number of important areas, viz., capital cost reduction, advanced fuel cycles, safety, capacity factor, life extension, load following, operator aida, and personnel radiation exposure. (author)

  16. Wishful thinking and real problems: Small modular reactors, planning constraints, and nuclear power in Jordan

    International Nuclear Information System (INIS)

    Ramana, M.V.; Ahmad, Ali

    2016-01-01

    Jordan plans to import two conventional gigawatt scale nuclear reactors from Russia that are expensive and too large for Jordan's current electricity grid. Jordan efforts to establish nuclear power might become easier in some ways if the country were to construct Small Modular Reactors, which might be better suited to Jordan's financial capabilities and its smaller electrical grid capacity. But, the SMR option raises new problems, including locating sites for multiple reactors, finding water to cool these reactors, and the higher cost of electricity generation. Jordan's decision has important implications for its energy planning as well as for the market for SMRs. - Highlights: •Jordan is planning to purchase two large reactors from Russia. •Large reactors would be inappropriate to Jordan's small electricity grid. •Small modular reactors would be more appropriate to Jordan's grid, but have problems. •The market for small modular reactors will be smaller than often projected. •Jordan should consider the financial impact of building a large nuclear reactor.

  17. Capital cost: pressurized water reactor plant. Commercial electric power cost studies

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-01

    The investment cost study for the 1139 MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume contains the drawings, equipment list and site description.

  18. Capital cost: pressurized water reactor plant. Commercial electric power cost studies

    International Nuclear Information System (INIS)

    1977-06-01

    The investment cost study for the 1139 MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume contains the drawings, equipment list and site description

  19. 78 FR 56594 - Airworthiness Directives; General Electric Company Turbofan Engines

    Science.gov (United States)

    2013-09-13

    ... Airworthiness Directives; General Electric Company Turbofan Engines AGENCY: Federal Aviation Administration (FAA... General Electric Company (GE) GE90-76B, -85B, -90B, -94B, -110B1, and - 115B turbofan engines. This AD was...) Applicability This AD applies to General Electric Company (GE): (1) GE90-76B, -85B, -90B, and -94B turbofan...

  20. Electric Power Monthly, June 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-13

    The EPM is prepared by the Electric Power Division; Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), Department of Energy. This publication provides monthly statistics at the national, Census division, and State levels for net generation, fuel consumption, fuel stocks, quantity and quality of fuel, electricity sales, and average revenue per kilowatthour of electricity sold. Data on net generation are also displayed at the North American Electric Reliability Council (NERC) region level. Additionally, company and plant level information are published in the EPM on capability of new plants, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fuel. Quantity, quality, and cost of fuel data lag the net generation, fuel consumption, fuel stocks, electricity sales, and average revenue per kilowatthour data by 1 month. This difference in reporting appears in the national, Census division, and State level tables. However, at the plant level, all statistics presented are for the earlier month for the purpose of comparison. 40 tabs.

  1. Nuclear electric capacity expansion in Mexico: system effects of reactor size and cost

    International Nuclear Information System (INIS)

    Thayer, G.R.; Abbey, D.S.; Hardie, R.W.; Enriquez, R.P.; Uria, E.G.

    1984-01-01

    Mexico's electrical generation capacity could more than double over the next ten years - from about 15 GWe currently to as much as 35 GWe in 1990. While new capacity additions will be predominantly oil-fired in the 1980's, nuclear power will become increasingly important in the 1990's. This study investigated the appropriate size of new, nuclear capacity additions by assessing the implications of installing different size reactors into Mexico's electrical grid. Included in the assessments of reactor sizes are estimates of electrical generation costs and comparisons of the effective load-carrying capability of a 10 GWe nuclear capacity expansion

  2. Reactor control device

    International Nuclear Information System (INIS)

    Fukami, Haruo; Morimoto, Yoshinori.

    1981-01-01

    Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

  3. Parameter study toward economical magnetic fusion power reactors

    International Nuclear Information System (INIS)

    Yoshida, Tomoaki; Okano, Kunihiko; Nanahara, Toshiya; Hatayama, Akiyoshi; Yamaji, Kenji; Takuma, Tadashi.

    1996-01-01

    Although the R and D of nuclear fusion reactors has made a steady progress as seen in ITER project, it has become of little doubt that fusion power reactors require hugeness and enormous amount of construction cost as well as surmounting the physics and engineering difficulties. Therefore, it is one of the essential issues to investigate the prospect of realizing fusion power reactors. In this report we investigated the effects of physics and engineering improvements on the economics of ITER-like steady state tokamak fusion reactors using our tokamak system and costing analysis code. With the results of this study, we considered what is the most significant factor for realizing economical competitive fusion reactors. The results show that with the conventional TF coil maximum field (12T), physics progress in β-value (or Troyon coefficient) has the most considerable effect on the reduction of fusion plant COE (Cost of Electricity) while the achievement of H factor = 2-3 and neutron wall load =∼5MW/m 2 is necessary. The results also show that with the improvement of TF coil maximum field, reactors with a high aspect ratio are economically advantageous because of low plasma current driving power while the improvement of current density in the conductors and yield strength of support structures is indispensable. (author)

  4. Power companies international year book 1997

    International Nuclear Information System (INIS)

    Anon.

    1996-12-01

    The Power Companies International Yearbook covers around 250 major international power generating and distributing companies worldwide, giving a comprehensive overview of this dynamic global industry. Both publicly and privately owned companies are features. It details financial performance, ownership status, affiliated businesses, activities, operations, key personnel, type/capacity of generation, subsidiary activities and plans for diversification within and outside the global power sector. (Author)

  5. Commissioning of the THTR-300-MWe prototype power plant - A milestone for further application of this high-temperature reactor line

    International Nuclear Information System (INIS)

    Simon, M.; Baust, E.; Schoening, J.

    1986-10-01

    With the completion of the THTR 300 and the development of the follow-on plant HTR 500, the BBC/HRB company group has taken the pebble bed high-temperature reactor to the threshold of the commercial stage. The HTR is an important innovation in the field of reactor technology which can play an important role in the intermediate and long-term supply of safe, environmental friendly and economic energy. The power level of 550 MW meets the requirements of the present energy market which shows a trend towards smaller power units as a result of grid size, investment effort, and the slower increase in electricity demand in industrial nations. The advantages of the high-temperature reactor, such as high thermal efficiency, low waste heat, low radiation exposure of operating and maintenance personnel, high inherent safety, simple mode of operation, flexible fuel cycle with the potential to extend fuel resources, high availability, are currently uncontested and will represent the future standards for the peaceful uses of nuclear energy. For special applications in industry (steam and electric power as a cogeneration product) and in case of special siting conditions (near industrial centers), BBC/HRB developed a small 100 MW HTR, which can also be constructed as a 200 MW twin plant at favorable cost conditions. For an economic use of domestic coal in a processed form, the HTR represents the optimum solution as to economic and environmental aspects as well as extension of resources, especially if combined with conventional gasification procedures and in direct application of nuclear process heat at high gas temperatures of about 950 deg. C. In this field the development of the heat-exchanging components remains to be completed, before commercial application will be possible. The HTR is particularly well suited for erection in developing countries and industrial threshold countries which turn to nuclear energy for the first time. On an international level the interest in the

  6. Operational and Environmental Efficiencies of Japanese Electric Power Companies from 2003 to 2015: Influence of Market Reform and Fukushima Nuclear Power Accident

    Directory of Open Access Journals (Sweden)

    Mika Goto

    2017-01-01

    Full Text Available This study measures operational and environmental efficiencies of nine incumbent electric power companies (EPCos in Japan and examines an influence of market reform and Fukushima nuclear power plant accident on efficiencies using a data set from 2003 to 2015. This study applies output-oriented radial data envelopment analysis (DEA model to the measurement of efficiencies. Three inputs and three desirable outputs are used for the measurement of operational efficiency, and one undesirable output besides inputs and desirable outputs is used to measure environmental efficiency. EPCos produce not only desirable output, for example, electricity, but also undesirable output, for example, CO2, for their operations. For the measurement of environmental efficiency, this study uses a unique DEA model that assumes occurrence of ecotechnology innovation. The results reveal that environmental efficiency of EPCos is mostly invariant over the period of this study, while operational efficiency decreases in the same period. In addition, the results present that Japanese EPCos make efforts to reduce CO2 emissions by promoting ecotechnology innovation. The Kruskal–Wallis rank sum test indicates differences in operational and environmental efficiencies among EPCos. Such performance differences might become larger as market liberalization advances, which could lead to further structural changes of the industry.

  7. Micro-structured nuclear fuel and novel nuclear reactor concepts for advanced power production

    International Nuclear Information System (INIS)

    Popa-Simil, Liviu

    2008-01-01

    Many applications (e.g. terrestrial and space electric power production, naval, underwater and railroad propulsion and auxiliary power for isolated regions) require a compact-high-power electricity source. The development of such a reactor structure necessitates a deeper understanding of fission energy transport and materials behavior in radiation dominated structures. One solution to reduce the greenhouse-gas emissions and delay the catastrophic events' occurrences may be the development of massive nuclear power. The actual basic conceptions in nuclear reactors are at the base of the bottleneck in enhancements. The current nuclear reactors look like high security prisons applied to fission products. The micro-bead heterogeneous fuel mesh gives the fission products the possibility to acquire stable conditions outside the hot zones without spilling, in exchange for advantages - possibility of enhancing the nuclear technology for power production. There is a possibility to accommodate the materials and structures with the phenomenon of interest, the high temperature fission products free fuel with near perfect burning. This feature is important to the future of nuclear power development in order to avoid the nuclear fuel peak, and high price increase due to the immobilization of the fuel in the waste fuel nuclear reactor pools. (author)

  8. Profiting from competition: Financial tools for electric generation companies

    Science.gov (United States)

    Richter, Charles William, Jr.

    Regulations governing the operation of electric power systems in North America and many other areas of the world are undergoing major changes designed to promote competition. This process of change is often referred to as deregulation. Participants in deregulated electricity systems may find that their profits will greatly benefit from the implementation of successful bidding strategies. While the goal of the regulators may be to create rules which balance reliable power system operation with maximization of the total benefit to society, the goal of generation companies is to maximize their profit, i.e., return to their shareholders. The majority of the research described here is conducted from the point of view of generation companies (GENCOs) wishing to maximize their expected utility function, which is generally comprised of expected profit and risk. Strategies that help a GENCO to maximize its objective function must consider the impact of (and aid in making) operating decisions that may occur within a few seconds to multiple years. The work described here assumes an environment in which energy service companies (ESCOs) buy and GENCOs sell power via double auctions in regional commodity exchanges. Power is transported on wires owned by transmission companies (TRANSCOs) and distribution companies (DISTCOs). The proposed market framework allows participants to trade electrical energy contracts via the spot, futures, options, planning, and swap markets. An important method of studying these proposed markets and the behavior of participating agents is the field of experimental/computational economics. For much of the research reported here, the market simulator developed by Kumar and Sheble and similar simulators has been adapted to allow computerized agents to trade energy. Creating computerized agents that can react as rationally or irrationally as a human trader is a difficult problem for which we have turned to the field of artificial intelligence. Some of our

  9. Westinghouse Electric. Know-how and top technology from Germany support non-polluting, safe, cost-effective power supply worldwide

    International Nuclear Information System (INIS)

    2011-01-01

    Westinghouse Electric Company LLC is one the world's leading firms in the commercial nuclear power field with a staff of approx. 15,000, of whom approx. 5,000 work in Europe. As part of the Toshiba Group, Westinghouse supports power utilities in the Americas, Asia, and EMEA (Europe, Middle East, Africa) regions with a broad range of products and services in nuclear power plants, nuclear fuel, nuclear services, and nuclear automation. The German-based company, Westinghouse Electric Germany GmbH, has more than 500 persons at the locations of Mannheim; Hamburg; Baden, Switzerland; and Metz, France. For more than 40 years, it has been successfully operating in field services, plant engineering, waste management, and nuclear automation. The Mannheim head office works the nuclear markets in Germany, Switzerland, the Czech Republic, Slovakia, and Hungary. Under global resource utilization and products schemes, staff from Germany is employed also in projects all over the world. Present construction of a large number of new plants of the AP1000 registered reactor line in China and USA as well as planning and licensing steps for the construction of new nuclear power plants in Europe constitute a major contribution by Westinghouse to the worldwide renaissance of nuclear power. As a partner of utilities, Westinghouse also upgrades existing plants by backfitting and modernizing components and systems, management of aging, safety analyses, non-destructive testing, replacement of safety and operations I and C etc. for plant life extension and safe, economically viable continued operation. (orig.)

  10. Improvement of system code importing evaluation of Life Cycle Analysis of tokamak fusion power reactors

    International Nuclear Information System (INIS)

    Kobori, Hikaru; Kasada, Ryuta; Hiwatari, Ryoji; Konishi, Satoshi

    2016-01-01

    Highlights: • We incorporated the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code. • We calculated CO_2 emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. • We found that the objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. • The tokamak fusion reactor can reduce CO_2 emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. • The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant. - Abstract: This study incorporate the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code to calculate CO_2 emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. Competitiveness of tokamak fusion power reactors is expected to be evaluated by the cost and environmental impact represented by the CO_2 emissions, compared with present and future power generating systems such as fossil, nuclear and renewables. Result indicated that (1) The objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. (2) The tokamak fusion reactor can reduce CO_2 emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. (3) The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant.

  11. Improvement of system code importing evaluation of Life Cycle Analysis of tokamak fusion power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kobori, Hikaru [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan); Kasada, Ryuta, E-mail: r-kasada@iae.kyoto-u.ac.jp [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan); Hiwatari, Ryoji [Central Research Institute of Electric Power Industry, Tokyo (Japan); Konishi, Satoshi [Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Kyoto 611-0011 (Japan)

    2016-11-01

    Highlights: • We incorporated the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code. • We calculated CO{sub 2} emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. • We found that the objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. • The tokamak fusion reactor can reduce CO{sub 2} emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. • The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant. - Abstract: This study incorporate the Life Cycle Analysis (LCA) of tokamak type DEMO reactor and following commercial reactors as an extension of a system code to calculate CO{sub 2} emissions from reactor construction, operation and decommissioning that is considered as a major environmental cost. Competitiveness of tokamak fusion power reactors is expected to be evaluated by the cost and environmental impact represented by the CO{sub 2} emissions, compared with present and future power generating systems such as fossil, nuclear and renewables. Result indicated that (1) The objective of conceptual design of the tokamak fusion power reactor is moved by changing evaluation index. (2) The tokamak fusion reactor can reduce CO{sub 2} emissions in the life cycle effectively by reduction of the amount involved in the replacement of internal components. (3) The tokamak fusion reactor achieves under 0.174$/kWh electricity cost, the tokamak fusion reactor is contestable with 1500 degrees-class LNG-fired combined cycle power plant.

  12. Significance assessment of small-medium sized reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kanno, Minoru [Japan Atomic Power Co., Research and Development Dept., Tokyo (Japan)

    2002-12-01

    Preliminary assessment for deployment of small-medium sized reactor (S and M reactor) as a future option has been conducted at the JAPCO (Japan Atomic Power Company) under the cooperation with the CRIERI (Central Research Institute of Electric Power Industry). Significance of the S and M reactor introduction is listed as follows; lower investment cost, possible siting near demand side, enlarged freedom of siting, shorter transmission line, good compatibility with slow increase of demand and plain explanation of safety using simpler system such as integral type vessel without piping, natural convection core cooling and passive safety system. The deployment of simpler plant system, modular shop fabrication, ship-shell structured building and longer operation period can assure economics comparable with that of a large sized reactor, coping with scale-demerit. Also the S and M reactor is preferable in size for the nuclear heat utilization such as hydrogen production. (T. Tanaka)

  13. Small and medium power reactors: the past, present and future

    International Nuclear Information System (INIS)

    Smith, T.G.G.

    1987-01-01

    The history of small and medium power reactors (SMPRs) is reviewed. Although the power range goes up to plants with an electricity output of 600MWe, the focus is on plants of 250-300 MWe. The role of the International Atomic Energy Agency in promoting their use for electrical energy production for developing countries is examined. It can be shown that there is a considerable potential market for SMPRs which will increase later this century and into the next. There are, however, a number of problems to be overcome. These are not in the technical aspects but problems of costs and financing. Thus efforts should be made to reduce capital costs, shorten construction time and find potential customers who are acceptable borrowers to the international banking world. Various types of reactor are examined. (U.K.)

  14. Small size modular fast reactors in large scale nuclear power

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.; Toshinsky, G.I.; Komlev, O.G.; Dragunov, U.G.; Stepanov, V.S.; Klimov, N.N.; Kopytov, I.I.; Krushelnitsky, V.N.

    2005-01-01

    The report presents an innovative nuclear power technology (NPT) based on usage of modular type fast reactors (FR) (SVBR-75/100) with heavy liquid metal coolant (HLMC) i. e. eutectic lead-bismuth alloy mastered for Russian nuclear submarines' (NS) reactors. Use of this NPT makes it possible to eliminate a conflict between safety and economic requirements peculiar to the traditional reactors. Physical features of FRs, an integral design of the reactor and its small power (100 MWe), as well as natural properties of lead-bismuth coolant assured realization of the inherent safety properties. This made it possible to eliminate a lot of safety systems necessary for the reactor installations (RI) of operating NPPs and to design the modular NPP which technical and economical parameters are competitive not only with those of the NPP based on light water reactors (LWR) but with those of the steam-gas electric power plant. Multipurpose usage of transportable reactor modules SVBR-75/100 of entirely factory manufacture assures their production in large quantities that reduces their fabrication costs. The proposed NPT provides economically expedient change over to the closed nuclear fuel cycle (NFC). When the uranium-plutonium fuel is used, the breeding ratio is over one. Use of proposed NPT makes it possible to considerably increase the investment attractiveness of nuclear power (NP) with fast neutron reactors even today at low costs of natural uranium. (authors)

  15. Evaluation on Influence of Unstable Primary-Energy Price in a Deregulated Electric Power Market—Analysis based on a simulation model approach—

    Science.gov (United States)

    Maitani, Tatsuyuki; Tezuka, Tetsuo

    The electric power market of Japan has been locally monopolized for a long time. But, like many countries, Japan is moving forward with the deregulation of its electric power industry so that any power generation company could sell electric power in the market. The power price, however, will fluctuate inevitably to balance the power supply and demand. A new appropriate market design is indispensable when introducing new market mechanisms in the electric power market to avoid undesirable results of the market. The first stage of deregulation will be the competition between an existing large-scaled power utility and a new power generation company. In this paper we have investigated the wholesale market with competition of these two power companies based on a simulation model approach. Under the competitive situation the effects of exogenous disturbance may bring serious results and we estimated the influence on the market when the price of fossil fuel rises. The conclusion of this study is that several types of Nash equilibriums have been found in the market: the larger the new power generation company becomes, the higher the electricity price under the Nash equilibriums rises. Because of the difference in their structure of generation capacity, the existing large-scaled power utility gets more profit while the new power generation company loses its profit when the price of fossil fuel rises.

  16. Conceptual design of a Tokamak hybrid power reactor (THPR)

    International Nuclear Information System (INIS)

    Matsuoka, F.; Imamura, Y.; Inoue, M.; Asami, N.; Kasai, M.; Yanagisawa, I.; Ida, T.; Takuma, T.; Yamaji, K.; Akita, S.

    1987-01-01

    A conceptual design of a fusion-fission hybrid tokamak reactor has been carried out to investigate the engineering feasibility and promising scale of a commercial hybrid reactor power plant. A tokamak fusion driver based on the recent plasma scaling law is introduced in this design study. The major parameters and features of the reactor are R=6.06 m, a=1.66 m, Ip=11.8 MA, Pf=668 MW, double null divertor plasma and steady state burning with RF current drive. The fusion power has been determined with medium energy multiplication in the blanket so as to relieve thermal design problems and produce electric power around 1000 MW. Uranium silicide is used for the fast fission blanket material to promise good nuclear performance. The coolant of the blanket is FLIBE and the tritium breeding blanket material is Li 2 O ceramics providing breeding ratio above unity

  17. 15 years of information and educational programme of Czech Power Company CEZ

    International Nuclear Information System (INIS)

    Dufkova, M.

    2007-01-01

    The education program is the most important long-term communication programme of CEZ. It was established in 1992 shortly after an establishment of Czech Power Company. The support of education and talented students is doubtless a positive activity bringing a benefit to the company, especially in the field of nuclear energy. Students, who have been currently addressed with this program, are future consumers of electricity and as voters and politicians they shall decide on further development of power industry and nuclear installations. We care for them to make qualified decisions. CEZ has so far been the only Czech industrial company, which offers such program to schools. Education is the most important activity in the gaining support for nuclear energy. (author)

  18. On global environment problems in electric power business

    International Nuclear Information System (INIS)

    Sugi, Masashi

    1992-01-01

    The former environmental problems were atmospheric pollution, water quality contamination, noise and vibration nuisance, waste disposal and so on mainly at interior or district level, but now, the influence that the problems such as the global warming due to carbon dioxide emission, the ozone layer breaking due to freon gas, acid rain going over boundaries and so on exert to environment spreads to wide areas, therefore, various research and investigation have been carried out as the environmental problems on global scale at national and international levels. It has become an important subject to make the preservation of global environment and durable economical development compatible by effectively utilizing limited resources and energy. The electric power companies have advanced positively the prevention of pollution and the preservation of environment, and attained the environment preservation of top level in the world. The consciousness of people on environmental problems has heightened, therefore the construction and operation of power plants harmonized to districts are important. The countermeasures to environmental problems taken by electric power companies are reported. (K.I.)

  19. New approaches to nuclear power

    KAUST Repository

    Dewan, Leslie

    2018-01-21

    The world needs a cheap, carbon-free alternative to fossil fuels to feed its growing electricity demand. Nuclear power can be a good solution to the problem, but is hindered by issues of safety, waste, proliferation, and cost. But what if we could try a new approach to nuclear power, one that solves these problems? In this lecture, the CEO of Transatomic Power will talk about how their company is advancing the design of a compact molten salt reactor to support the future of carbon-free energy production. Can the designs of new reactor push the boundaries of nuclear technology to allow for a safe, clean, and affordable answer to humanityメs energy needs? Nuclear power involves capturing the energy produced in nuclear fission reactions, which emerges as heat. This heat is most frequently used to boil water into steam, which then drives a turbine to produce electricity in a nuclear power plant. Worldwide, there is a renaissance of new nuclear technology development -- a new generation of young engineers are racing to develop more advanced nuclear reactors for a better form of power generation. Transatomic Power, specifically, is advancing the design of an easily contained and controlled, atmospheric pressure, high power density molten salt reactor that can be built at low cost. The road to commercialization is long, and poses many challenges, but the benefits are enormous. These new reactors push the boundaries of technology to allow for better, safer ways to power the world.

  20. Nuclear reactor development in China for non-electrical applications

    International Nuclear Information System (INIS)

    Sun Yuliang; Zhong Daxin; Dong Duo; Xu Yuanhui

    1998-01-01

    In parallel to its vigorous program of nuclear power generation, China has attached great importance to the development of nuclear reactors for non-electrical applications. The Institute of Nuclear Energy Technology (INET) in Beijing has been developing technologies of the water-cooled heating reactor and the modular high temperature gas-cooled reactor. In 1989, a 5 MW water cooled test reactor was erected. Currently, an industrial demonstration nuclear heating plant is being projected. Feasibility studies are being made of sea-water desalination using the INET developed nuclear heating reactor as heat source. Also, a 10 MW high temperature gas-cooled test reactor is being constructed at INET in the framework of China's national high-tech program. The paper gives an overview of China's energy market situation. With respect to China's technology development of high temperature gas-cooled reactors and water cooled heating reactors, the paper describes some general requirements on the technical development, reviews the national programs and activities, describes briefly the design and safety features of the reactor concepts, discusses aspects of application potentials. (author)

  1. A Survey of the Hazards to Electrical Power Systems

    International Nuclear Information System (INIS)

    Johnson, Gary

    2015-01-01

    This paper presents the preliminary results of a survey of severe accidents and the lessons learned that are important to the design of electrical power systems. This survey of historical accidents since 1952 identified 19 known incidents in which significant fuel melt occurred within a reactor core. In each of these incidents unexpected events or event sequences played an important role. In all cases the event sequences resulted in bypass of two or more levels of defense in depth. This study offers clear lessons for electrical power robustness: 1) Robust design must be based upon a clear understanding of what can go wrong, and 2) Robust design will reduce, but cannot eliminate, the potential for failure of electrical power systems. In order to better understand 'what is the worst that can happen' known hazards are reviewed to identify the challenges that they can present to electrical power systems. Recognizing that unexpected events cannot always be prevented the paper discusses the need for methods to restore plant power sources or provide for alternate power supplies when the plant power sources fail. (authors)

  2. Scoping calculations of power sources for nuclear electric propulsion

    International Nuclear Information System (INIS)

    Difilippo, F.C.

    1994-05-01

    This technical memorandum describes models and calculational procedures to fully characterize the nuclear island of power sources for nuclear electric propulsion. Two computer codes were written: one for the gas-cooled NERVA derivative reactor and the other for liquid metal-cooled fuel pin reactors. These codes are going to be interfaced by NASA with the balance of plant in order to making scoping calculations for mission analysis

  3. SP-100 space reactor power system readiness

    International Nuclear Information System (INIS)

    Josloff, A.T.; Matteo, D.N.; Bailey, H.S.

    1992-01-01

    This paper discusses the SP-100 Space Reactor Power System which is being developed by GE, under contract to the U.S. Department of Energy, to provide electrical power in the range of 10's to 100's of kW. The system represents an enabling technology for a wide variety of earth orbital and interplanetary science missions, nuclear electric propulsion (NEP) stages, and lunar/Mars surface power for the Space Exploration Initiative (SEI). The technology and design is now at a state of readiness to support the definition of early flight demonstration missions. Of particular importance is that SP-100 meets the demanding U.S. safety performance, reliability and life requirements. The system is scalable and flexible and can be configured to provide 10's to 100's of kWe without repeating development work and can meet DoD goals for an early, low-power demonstration flight in the 1996-1997 time frame

  4. Maintenance of EDF nuclear power plants and servicing companies. Progress report

    International Nuclear Information System (INIS)

    Baize, Jean-Marc; Reveillon, Sylvie

    1997-01-01

    French Electricity Company (EDF - Electricite de France) and the associated servicing companies, engaged in maintenance partnership from 1991, reinforce and expand their policy by undersigning a progress charter, to cope with the safety and nuclear sector competition issues. This charter stipulates the mutual engagements in the following sectors: 1. Transparency in calling for servicing; 2. Development of the intervenors' professionalism; 3. Improvement in forecasting activity tasks; 4. Radioprotection; 5. Safety and working conditions. The 55 reactors of the EDF nuclear stock are stopped annually for around 6 weeks for refueling. On this occasion the essential maintenance works necessary to ensure the optimal safety of the installations are carried out. The maintenance requires the intervention of 30,000 employees, 10,000 EDF agents and 20,000 external intervenors and represents an amount of 14 million working hours. The full maintenance expenses amounts up to 11 billion FF in 1996, 6 billion of which are assigned to external companies

  5. Reactor power control device

    International Nuclear Information System (INIS)

    Doi, Kazuyori.

    1981-01-01

    Purpose: To automatically control the BWR type reactor power by simple and short-time searching the load pattern nearest to the required pattern at a nuclear power plant side. Constitution: The reactor power is automatically regulated by periodical modifying of coefficients fitting to a reactor core model, according as a required load pattern. When a load requirement pattern is given, a simulator estimates the total power change and the axial power distribution change from a xenon density change output calculated by a xenon dynamic characteristic estimating device, and a load pattern capable of being realized is searched. The amount to be recirculated is controlled on the basis of the load patteren thus searched, and the operation of the BWR type reactor is automatically controlled at the side of the nuclear power plant. (Kamimura, M.)

  6. Duke Power Company's control rod wear program

    International Nuclear Information System (INIS)

    Culp, D.C.; Kitlan, M.S. Jr.

    1990-01-01

    Recent examinations performed at several foreign and domestic pressurized water reactors have identified significant control rod cladding wear, leading to the conclusion that previously believed control rod lifetimes are not attainable. To monitor control rod performance and reduce safety concerns associated with wear, Duke Power Company has developed a comprehensive control rod wear program for Ag-In-Cd and boron carbide (B 4 C) rods at the McGuire and Catawba nuclear stations. Duke Power currently uses the Westinghouse 17 x 17 Ag-In-Cd control rod design at McGuire Unit 1 and the Westinghouse 17 x 17 hybrid B 4 C control rod design with a Ag-In-Cd tip at McGuire Unit 2 and Catawba Units 1 and 2. The designs are similar, with the exception of the absorber material and clad thickness. There are 53 control rods per unit

  7. The nuclear power electricity an opportunity for Mexico. Final report

    International Nuclear Information System (INIS)

    Fernandez de la Garza, R.; Garcia, C. F.; Trejo R, S.; Zazueta R, T.; Castaneda G, M. A.; Cruz B, H. J.; Mercado V, J. J.

    2009-01-01

    Inside this document the outstanding information is presented included in the report that develops the technical, financial, environmental and social aspects to consider for the incorporation from a new power plant to the national interconnected system, which was elaborated and presented to the nuclear power plant of Laguna Verde in August of 2009. The treated topics are: the nuclear power electricity, the experience of Laguna Verde, advanced reactors to consider for a new nuclear power plant, environmental aspects, costs of a new nuclear power plant, financing, socioeconomic impact. This work was prepared to evaluate the feasibility of building a new unit of nuclear power plant in Mexico before the evident resurgence at world level of use of nuclear energy to generate electricity. It is important that Mexico maintains inside its development programs and construction, to the nuclear power electricity like a viable and sure alternative of generating electricity, being able to take advantage of experience won with the operation of Laguna Verde, allowing that the country has diverse technologies for electricity generation and have technical capacity to manage the tip technology. (Author)

  8. WITAMIR-I: A tandem mirror power reactor

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Beyer, J.B.

    1983-01-01

    A conceptual design of a near term commercial tandem mirror power reactor will be presented. The basic configuration utilizes Yin-yang minimum B end plugs with inboard thermal barriers, which are pumped by neutral beam injection. The maximum magnetic fields are 6.1 T, 8.1 T and 15 T in the central cell, Yin-yang, and thermal barrier magnets, respectively. The blanket utilizes Pb 83 Li 17 as the coolant and breeder, and HT-9 as the structural material. This configuration yields a high energy multiplication (1.37), a sufficient tritium breeding ratio (1.07) and has a major advantage with respect to maintenance. A single stage direct convertor is used at one end and an electron thermal dump at the other end. The plasma Q is 28 at a fusion power level of 3000 MWsub(th); the net electrical output is 1530 MWe and the overall efficiency is 39%. Cost estimates indicate that WITAMIR-I is competitive with recent tokamak power reactor designs. (author)

  9. Comparative Study on Electric Generation Cost of HTR with Another Electric Plant Using LEGECOST Program

    International Nuclear Information System (INIS)

    Mochamad-Nasrullah; Soetrisnanto, Arnold Y.; Tosi-Prastiadi; Adiwardojo

    2000-01-01

    Monetary and economic crisis in Indonesia resulted in impact of electricity and demand and supply planning that it has to be reevaluated. One of the reasons is budget limitation of the government as well as private companies. Considering this reason, the economic calculation for all of aspect could be performed, especially the calculation of electric generation cost. This paper will discuss the economic aspect of several power plants using fossil and nuclear fuel including High Temperature Reactor (HTR). Using Levelized Generation Cost (LEGECOST) program developed by IAEA (International Atomic Energy Agency), the electric generation cost of each power plant could be calculated. And then, the sensitivity analysis has to be done using several economic parameters and scenarios, in order to be known the factors that influence the electric generation cost. It could be concluded, that the electric generation cost of HTR is cheapest comparing the other power plants including nuclear conventional. (author)

  10. The structure of atomic power industry with allowance for energy production other than electricity

    International Nuclear Information System (INIS)

    Aleksandrov, A.P.; Legasov, V.A.; Sidorenko, V.A.; Ponomarev-Stepnoj, N.N.; Protsenko, A.N.; Grebennik, V.N.; Glushkov, E.S.

    1977-01-01

    The important tendency in the development of nuclear power is broadening the scope of its application for substitution of mineral fuel by the nuclear one not only at the electrical power production but in other energy consuming fields of industry. The development of large-scale nuclear power plants permits the provision of the significant part of energy supply of all kinds and save on oil and gas. Scales and rates of development of nuclear power are estimated for the model society on the basis of predicted need energy consumption per capita. The possible rates and scales of nuclear power development are determined at some alternative amounts of potential reserves of organic fuel (oil, gas) per capita and within the economically and ecologically reasonable scales of coal utilization. There has been given the analysis of possible scopes of application of nuclear power industry: for production of electricity, central heating, hydrogen generation, gasification of coals, metallurgy, chemistry by means of medium- and high-temperature reactors. The conceivable relation between electrical energy and heat production in energetics and the nuclear power industry and the dynamics of change in this relation is being forecasted. The promising development of high temperature helium reactors has been discussed. Considerations on possible effect of thorium cycle on the structure of nuclear power industry are outlined. The nuclear power industry is being developed mainly on the basis of nuclear power plants with thermal reactors and it should not be expected for the next decade that its structure is to change significantly. However, the development of only this type reactors will require, as early as the end of this century, the significant consumption of natural uranium and considerable increase in capacities of uranium output and uranium enrichment industry. Therefore, in the following stages of development of nuclear power industry it is necessary to introduce fast breeders

  11. Digital control application for the advanced boiling water reactor

    International Nuclear Information System (INIS)

    Fennern, L.E.; Pearson, T.; Wills, H.D.; Swire Rhodes, L.; Pearson, R.L.

    1986-01-01

    The Advanced Boiling Water Reactor (ABWR) is a 1300 MWe class Nuclear Power Plant whose design studies and demonstration tests are being performed by the three manufacturers, General Electric, Toshiba and Hitachi, under requirement specifications from the Tokyo Electric Power Company. The goals are to apply new technology to the BWR in order to achieve enhanced operational efficiencies, improved safety measures and cost reductions. In the plant instrumentation and control areas, traditional analog control equipment and wire cables will be replaced by distributed digital microprocessor based control units communicating with each other and the control room over fiber optic multiplexed data buses

  12. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... systems. (8) Emergency ac electrical power systems, including: Emergency diesel generators (EDGs...

  13. Capital cost: pressurized water reactor plant. Commerical electric power cost studies

    International Nuclear Information System (INIS)

    1977-06-01

    The investment cost study for the 1139-MW(e) pressurized water reactor (PWR) central station power plant consists of two volumes. This volume includes in addition to the foreword and summary, the plant description and the detailed cost estimate

  14. Performance issues for a changing electric power industry

    Energy Technology Data Exchange (ETDEWEB)

    1995-01-01

    Extremely cold weather created record demands for electricity in the eastern two-thirds of the United States during the week of January 16, 1994. Fuel-related problems, mostly the result of transportation constraints resulting from ice accumulation on roads and water-ways, and unexpected generating capacity outages at utilities and nonutilities resulted in demand not being met. Some utilities asked nonessential customers along with State governments and a portion of the Federal Government to shut down. Two electric control areas, the Pennsylvania-New Jersey-Maryland Interconnection (PJM) and Virginia Electric & Power Company (VEPCO), instituted rolling blackouts. This disturbance was reported widely in the press and, along with other disturbances, peaked renewed interest in the reliability of the electric power system. The renewed interest in reliability has coincided with substantial changes that are beginning to occur in the structure and competitiveness of the electric power industry. Juxtaposing the question of reliability and the issue of changing industry structure leads to the central concern of this report: What effect, if any, will the changing structure of the industry have on the reliability of the system?

  15. A Takagi–Sugeno fuzzy power-distribution method for a prototypical advanced reactor considering pump degradation

    Directory of Open Access Journals (Sweden)

    Yue Yuan

    2017-08-01

    Full Text Available Advanced reactor designs often feature longer operating cycles between refueling and new concepts of operation beyond traditional baseload electricity production. Owing to this increased complexity, traditional proportional–integral control may not be sufficient across all potential operating regimes. The prototypical advanced reactor (PAR design features two independent reactor modules, each connected to a single dedicated steam generator that feeds a common balance of plant for electricity generation and process heat applications. In the current research, the PAR is expected to operate in a load-following manner to produce electricity to meet grid demand over a 24-hour period. Over the operational lifetime of the PAR system, primary and intermediate sodium pumps are expected to degrade in performance. The independent operation of the two reactor modules in the PAR may allow the system to continue operating under degraded pump performance by shifting the power production between reactor modules in order to meet overall load demands. This paper proposes a Takagi–Sugeno (T–S fuzzy logic-based power distribution system. Two T–S fuzzy power distribution controllers have been designed and tested. Simulation shows that the devised T–S fuzzy controllers provide improved performance over traditional controls during daily load-following operation under different levels of pump degradation.

  16. A Takagi-Sugeno fuzzy power-distribution method for a prototypical advanced reactor considering pump degradation

    Energy Technology Data Exchange (ETDEWEB)

    Yuan, Yue [Institute of Nuclear and New Energy Technology, Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Beijing (China); Coble, Jamie [Dept. of Nuclear Engineering, University of Tennessee, Knoxville (United States)

    2017-08-15

    Advanced reactor designs often feature longer operating cycles between refueling and new concepts of operation beyond traditional baseload electricity production. Owing to this increased complexity, traditional proportional–integral control may not be sufficient across all potential operating regimes. The prototypical advanced reactor (PAR) design features two independent reactor modules, each connected to a single dedicated steam generator that feeds a common balance of plant for electricity generation and process heat applications. In the current research, the PAR is expected to operate in a load-following manner to produce electricity to meet grid demand over a 24-hour period. Over the operational lifetime of the PAR system, primary and intermediate sodium pumps are expected to degrade in performance. The independent operation of the two reactor modules in the PAR may allow the system to continue operating under degraded pump performance by shifting the power production between reactor modules in order to meet overall load demands. This paper proposes a Takagi–Sugeno (T–S) fuzzy logic-based power distribution system. Two T–S fuzzy power distribution controllers have been designed and tested. Simulation shows that the devised T–S fuzzy controllers provide improved performance over traditional controls during daily load-following operation under different levels of pump degradation.

  17. The strategy of experimental power reactor licensing in Indonesia

    International Nuclear Information System (INIS)

    Moch Djoko Birmano

    2015-01-01

    Currently, BATAN has being planned to develop Experimental Power Reactor (EPR), that is the research nuclear reactor that can generate power (electricity or heat). The EPR is planned will be built in the National Center for Research of Science and Technology (Puspiptek) area at Serpong, South Tangerang, Banten Province, with the choice of reactor types is HTGR with the power size of 10 MWth. As stated in the Act No. 10 year 1997 on Nuclear Power, that every construction and operation of nuclear reactors and other nuclear installations and decommissioning of nuclear reactors required to have a permit. Furthermore, the its implementation arrangements is regulated in Government Regulation (GR) No. 2 year 2014 on Licensing of Nuclear Installations and Nuclear Material Utilization, which contains the requirements and procedures for the licensing process since site, construction, commissioning, operation, and decommissioning, it means licensing is implemented during the activity of construction, operation and decommissioning of NPPs.While, for the more detailed licensing arrangements available in the guidelines of BAPETEN Chairman Regulation (BCR). This study was conducted to understand the legal and institutional aspects, types and stages, and the licensing process of RDE, and identify licensing strategy so that timely as planned. Methodologies used include the literature study, consultation with experts in BAPETEN, discussions in the national seminar including FGD. (author)

  18. Efficiency of Finish power transmission network companies

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    The Finnish Energy Market Authority has investigated the efficiency of power transmissions network companies. The results show that the intensification potential of the branch is 402 million FIM, corresponding to about 15% of the total costs of the branch and 7.3 % of the turnout. Energy Market Authority supervises the reasonableness of the power transmission prices, and it will use the results of the research in supervision. The research was carried out by the Quantitative Methods Research Group of Helsinki School of Economics. The main objective of the research was to create an efficiency estimation method for electric power distribution network business used for Finnish conditions. Data of the year 1998 was used as basic material in the research. Twenty-one of the 102 power distribution network operators was estimated to be totally efficient. Highest possible efficiency rate was 100, and the average of the efficiency rates of all the operators was 76.9, the minimum being 42.6

  19. Report on countermeasure to plant life management of the nuclear power plants at three electric power companies

    International Nuclear Information System (INIS)

    1999-01-01

    Three nuclear power reactors of the Fukushima-1 nuclear power plant, the Mihama-1 power plant and the Tsuruga-1 power plant were investigated according to the estimation plan shown in the Fundamental Concept on Plant Life Management of Agency of Natural Resources and Energy, Ministry of International Trade and Industry on April, 1996. Their reports contained the technical evaluation against, the responsive items to and the future examinations of the plant life management. In special, in the responsive items, some items to be added to the present maintenance process and some technical developmental problems are described in details and concretely. (G.K.)

  20. Containment for small pressurized water reactors

    International Nuclear Information System (INIS)

    Siler, W.C.; Marda, R.S.; Smith, W.R.

    1977-01-01

    Babcock and Wilcox Company has prepared studies under ERDA contract of small and intermediate size (313, 365 and 1200 MWt) PWR reactor plants, for industrial cogeneration or electric power generation. Studies and experience with nuclear plants in this size range indicate unfavorable economics. To offset this disadvantage, modular characteristics of an integral reactor and close-coupled vapor suppression containment have been exploited to shorten construction schedules and reduce construction costs. The resulting compact reactor/containment complex is illustrated. Economic studies to date indicate that the containment design and the innovative construction techniques developed to shorten erection schedules have been important factors in reducing estimated project costs, thus potentially making such smaller plants competetive with competing energy sources

  1. Electricity tariff design for transition economies. Application to the Libyan power system

    Energy Technology Data Exchange (ETDEWEB)

    Reneses, Javier; Gomez, Tomas; Rivier, Juan [Universidad Pontificia Comillas, Madrid (Spain); Angarita, Jorge L. [Europraxis Operations, Madrid (Spain)

    2011-01-15

    This paper presents a general electricity tariff design methodology, especially applicable for transition economies. These countries are trying to modernize their power systems from a centralized environment (with normally, a public vertically integrated electric company) to a liberalized framework (unbundling electricity companies and, eventually, starting a privatization process). Two issues arise as crucial to achieving a successful transition: (1) ensuring cost recovery for all future unbundled activities (generation, transmission, distribution and retailing), and (2) sending the right price signals to electricity customers, avoiding cross-subsidies between customer categories. The design of electricity tariffs plays a pivotal role in achieving both objectives. This paper proposes a new tariff design methodology that, complying with these two aforementioned criteria, requires a low amount of information regarding system data and customer load profiles. This is important since, typically, volume and quality of data are poor in those countries. The presented methodology is applied to computing tariffs for the Libyan power system in 2006, using real data. (author)

  2. Calibration of RB reactor power

    International Nuclear Information System (INIS)

    Sotic, O.; Markovic, H.; Ninkovic, M.; Strugar, P.; Dimitrijevic, Z.; Takac, S.; Stefanovic, D.; Kocic, A.; Vranic, S.

    1976-09-01

    The first and only calibration of RB reactor power was done in 1962, and the obtained calibration ratio was used irrespective of the lattice pitch and core configuration. Since the RB reactor is being prepared for operation at higher power levels it was indispensable to reexamine the calibration ratio, estimate its dependence on the lattice pitch, critical level of heavy water and thickness of the side reflector. It was necessary to verify the reliability of control and dosimetry instruments, and establish neutron and gamma dose dependence on reactor power. Two series of experiments were done in June 1976. First series was devoted to tests of control and dosimetry instrumentation and measurements of radiation in the RB reactor building dependent on reactor power. Second series covered measurement of thermal and epithermal neuron fluxes in the reactor core and calculation of reactor power. Four different reactor cores were chosen for these experiments. Reactor pitches were 8, 8√2, and 16 cm with 40, 52 and 82 fuel channels containing 2% enriched fuel. Obtained results and analysis of these results are presented in this document with conclusions related to reactor safe operation

  3. Estabilishing requirements for the next generation of pressurized water reactors--reducing the uncertainty

    International Nuclear Information System (INIS)

    Chernock, W.P.; Corcoran, W.R.; Rasin, W.H.; Stahlkopf, K.E.

    1987-01-01

    The Electric Power Research Institute is managing a major effort to establish requirements for the next generation of U.S. light water reactors. This effort is the vital first step in preserving the viability of the nuclear option to contribute to meet U.S. national electric power capacity needs in the next century. Combustion Engineering, Inc. and Duke Power Company formed a team to participate in the EPRI program which is guided by a Utility Steering committee consisting of experienced utility technical executives. A major thrust of the program is to reduce the uncertainties which would be faced by the utility executives in choosing the nuclear option. The uncertainties to be reduced include those related to safety, economic, operational, and regulatory aspects of advanced light water reactors. This paper overviews the Requirements Document program as it relates to the U.S. Advanced Light Water Reactor (ALWR) effort in reducing these uncertainties and reports the status of efforts to establish requirements for the next generation of pressurized water reactors. It concentrates on progress made in reducing the uncertainties which would deter selection of the nuclear option for contributing to U.S. national electric power capacity needs in the next century and updates previous reports in the same area. (author)

  4. Negative Effects of Antimonopoly Regulation on the Russian Electric Power Industry

    Directory of Open Access Journals (Sweden)

    Elena NEPRINTSEVA

    2017-07-01

    Full Text Available With the antimonopoly regulation in the domestic economy getting more stringent an analysis of the current measures of antimonopoly regulation in terms of their efficiency is now becoming ever more relevant. The aim of the study - analyze how the measures of antimonopoly regulation affect competitive relationships in the electric power industry. The following methods have been used in this work: empirical method, cause-effect method and scientific abstraction method. The article sets out an analysis of the antimonopoly regulation measures that the antimonopoly authority applies. It also provides an assessment of consequences that follow from such methods being applied for the promotion of competitive relationships on the market of electric power and capacity. A conclusion has been reached that the antimonopoly regulation measures being applied impede the progress of competitive relationships on the market of electric power and capacity. The continuing process of reformation in electric power industry aims to liberalize relationships in the area of electric power production. Yet, as a result of this process, generating capacities are becoming increasingly more concentrated mainly around state companies. This is mainly caused by the lack of certainty regarding the results of the industry reformation and a more stringent state regulation over the last years of the reforms. At the same time, for the purposes of limiting the market force, measures of antimonopoly regulation are being applied to generating companies. Such measures have an adverse effect on competitive relationships and stimulate further concentration.

  5. Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

    International Nuclear Information System (INIS)

    Wati, Nurokhim

    2008-01-01

    Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

  6. Improvement of the electric power sector through the access to the national power transmission system - SINTREL (Brazilian National System of Electric Power Transmission); Aperfeicoamento do setor de energia eletrica atraves do acesso a transmissao - SINTREL (Sistema Nacional de Transmissao de Energia Eletrica)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-04-01

    This report presents the organization and the operation of SINTREL (Brazilian National System of Electric Power Transmission), the national power transmission system, and it defines its function in the process of reform of the Brazilian electric sector. Besides showing the traditional organization of the companies and of the electric system, and the evolution of the organization of the Brazilian electric system to favor the competition.

  7. Report for the Prime Minister. Making the future French electric power organization a success

    International Nuclear Information System (INIS)

    Dumont, J.L.

    1998-01-01

    This report from the French Deputy of the Meuse region aims at taking stock of four main questions raised by the future organization of the French electric power industry in the context of the opening of the European power market: the public utility of electric power, the future missions of Electricite de france (EdF) company, the questions in relation with the personnel status in the electric power industry, and the status of the regulating authority. In order to give some elements of answer to these questions, the report has been divided into 2 parts: part 1 presents the power production, transport and distribution in the future electric power regulation (the renewal of nuclear facilities, the building of non-nuclear units, the exploitation of the power distribution network, the accounting dissociation and the transparency of accountancy, the organization of network access, the eligible clients, the direct power lines, the obligations of purchase, the distribution and the role of local authorities). Part 2 presents the four main stakes of the modernization of the French electric power sector: the electric power public utility (public concern and rights, government policy, sustain of innovation, environment protection and energy mastery, the transportation and distribution networks, the role of operators and the financing), the future evolution of EdF (missions and organization, future of the public company), the social modernization of the electric power sector (present day status, adaptation, evolution, pensions), the organization and role of the future regulation authority. The propositions of the author are reported in the appendix. (J.S.)

  8. Mirror hybrid reactor blanket and power conversion system conceptual design

    International Nuclear Information System (INIS)

    Schultz, K.R.; Backus, G.A.; Baxi, C.B.; Dee, J.B.; Estrine, E.A.; Rao, R.; Veca, A.R.

    1976-01-01

    The conceptual design of the blanket and power conversion system for a gas-cooled mirror hybrid fusion-fission reactor is presented. The designs of the fuel, blanket module and power conversion system are based on existing gas-cooled fission reactor technology that has been developed at General Atomic Company. The uranium silicide fuel is contained in Inconel-clad rods and is cooled by helium gas. The fuel is contained in 16 spherical segment modules which surround the fusion plasma. The hot helium is used to raise steam for a conventional steam cycle turbine generator. The details of the method of support for the massive blanket modules and helium ducts remain to be determined. Nevertheless, the conceptual design appears to be technically feasible with existing gas-cooled technology. A preliminary safety analysis shows that with the development of a satisfactory method of primary coolant circuit containment and support, the hybrid reactor could be licensed under existing Nuclear Regulatory Commission regulations

  9. Tandem mirror reactor power balance studies

    International Nuclear Information System (INIS)

    Gorker, G.E.; Perkins, L.J.

    1985-01-01

    A tandem mirror reactor (TMR) power plant balance model has been developed and is now being used as a computer aid for performing parametric studies. End-cell power injection into the plasma and the physics thermal Q are used to determine the fusion power. About 80% of the fusion power is transferred by high-energy neutrons to the blanket modules and structures. The other 20% of the fusion power in the high-energy alpha particles is used to heat the deuterium-tritium (D-T) plasma. Most of the plasma-ionized particles transfer their energy to the halo dumps and direct converters. The plant efficiency is calculated for three different system cycles: (1) the pressurized water/saturated steam cycle; (2) the superheated steam cycle; and (3) the more complex superheat/reheat cycle. There is a signficiant improvement in plant efficiency as the electrical power multiplication factor and steam cycle efficiency increases

  10. Power Nuclear Reactors: technology and innovation for development in future; Centrales Nucleares de Potencia: tecnologias actuales e innovaciones para el futuro

    Energy Technology Data Exchange (ETDEWEB)

    Suarez Antola, R [Universidad Catolica del Uruguay, Montevideo(Uruguay); Ministerio de Industria Energia y Minerria, Montevideo(Uruguay)

    2009-07-01

    The conference is about some historicals task of the fission technology as well as many types of Nuclear Reactors. Enrichment of fuel, wastes, research reactors and power reactors, a brief advertisment about Uruguay electric siystem and power generation, energetic worldwide, proliferation, safety reactors, incidents, accidents, Three-Mile Island accident, Chernobil accident, damages, risks, classification and description of Power reactors steam generation, nuclear reactor cooling systems, future view.

  11. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  12. Development of nuclear power plant management system for Kyushu Electric Power Co., Inc

    International Nuclear Information System (INIS)

    Nakamura, Kenichi; Akiyoshi, Tatsuo; Tanimoto, Kazuo; Ogura, Kazuhito; Ibi, Yuji; Kawasaki, Michiyuki

    2002-01-01

    The Kyushu Electric Power Co., Ltd. progresses development of the nuclear power plant management system using IT under aims at upgrading of efficiency, level, and reliability on maintenance and administration business under five years planning since 1999 fiscal year. The outline of the system are explained in this paper. As a result of preparation on power station net work and personal computers set in all of company, an environment capable of using these infrastructures and introducing large scale systems on transverse business over every groups of each power station could be established. (G.K.)

  13. Current training initiatives at Nuclear Electric plc

    International Nuclear Information System (INIS)

    Fowler, C.D.

    1993-01-01

    Nuclear Electric, one of the three generating companies to emerge from the demise of the U.K.'s Central Electricity Generating Board (CEGB), owns and operates the commercial nuclear power stations in England and Wales. The U.K. government proscribed further construction beyond Sizewell B, the United Kingdom's first pressurized water reactor (PWR) station, pending the outcome of a review of the future of nuclear power to be held in 1994. The major challenges facing Nuclear Electric at its formation in 1990 were therefore to demonstrate that nuclear power is safe, economical, and environmentally acceptable and to complete the PWR station under construction on time and within budget. A significant number of activities were started that were designed to increase output, reduce costs, and ensure that the previous excellent safety standards were maintained. A major activity was to reduce the numbers of staff employed, with a recognition from the outset that this reduction could only be achieved with a significant human resource development program. Future company staff would have to be competent in more areas and more productive. This paper summarizes some of the initiatives currently being pursued throughout the company and the progress toward ensuring that staff with the required competences are available to commission and operate the Sizewell B program in 1994

  14. Power Peaking Effect of OTTO Fuel Scheme Pebble Bed Reactor

    Science.gov (United States)

    Setiadipura, T.; Suwoto; Zuhair; Bakhri, S.; Sunaryo, G. R.

    2018-02-01

    Pebble Bed Reactor (PBR) type of Hight Temperature Gas-cooled Reactor (HTGR) is a very interesting nuclear reactor design to fulfill the growing electricity and heat demand with a superior passive safety features. Effort to introduce the PBR design to the market can be strengthen by simplifying its system with the Once-through-then-out (OTTO) cycle PBR in which the pebble fuel only pass the core once. Important challenge in the OTTO fuel scheme is the power peaking effect which limit the maximum nominal power or burnup of the design. Parametric survey is perform in this study to investigate the contribution of different design parameters to power peaking effect of OTTO cycle PBR. PEBBED code is utilized in this study to perform the equilibrium PBR core analysis for different design parameter and fuel scheme. The parameters include its core diameter, height-per-diameter (H/D), power density, and core nominal power. Results of this study show that diameter and H/D effectsare stronger compare to the power density and nominal core power. Results of this study might become an importance guidance for design optimization of OTTO fuel scheme PBR.

  15. Economic aspects of electricity and industrial heat generating reactors

    International Nuclear Information System (INIS)

    Gaussens, J.; Moulle, N.; Dutheil, F.

    1964-01-01

    The economic advantage of electricity-generating nuclear stations decreases when their size decreases. However, when a counter-pressure turbine is joined on to a reactor and the residual heat can be properly used, it can be shown that fairly low capacity nuclear equipment may compete with conventional equipment under certain realistic enough conditions. The aim of this paper is to define these special conditions under which nuclear energy can be profitable. They are connected with the location and the general economic environment of the station, the pattern of the electricity and heat demands it must meet, the level of fuel and specific capital costs, nuclear and conventional. These conditions entail certain technical and economic specifications for the reactors used in this way otherwise they are unlikely to be competitive. In addition, these results are referred to the potential steam and electricity market, which leads us to examine certain uses for the heat generated by double purpose power stations; for example, to supply combined industrial plants, various types of town heating and for removal of salt from sea water. (authors) [fr

  16. Safety evaluation report related to the operation of Susquehanna Steam Electric Station, Units 1 and 2. Docket Nos. 50-387 and 50-388, Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc

    International Nuclear Information System (INIS)

    1982-11-01

    In April 1981, the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0776) regarding the application of the Pennsylvania Power and Light Company (the licensee) and the Allegheny Electric Cooperative, Inc. (co-licensee) for licenses to operate the Susquehanna Steam Electric Station, Units 1 and 2, located on a site in Luzerne County, Pennsylvania. Supplement 1, issued in June 1981, addressed outstanding issues. Supplement 2, issued in September 1981, contains the ACRS Report and responses. Supplement 3, issued in July 1982, contains the resolution to five items previously identified as open and closes them out. On July 17, 1982, License NPF-14 was issued to allow Unit 1 operation at power levels not to exceed 5% of rated power. This supplement discusses the resolution of several license conditions that have been met

  17. Nuclear power in the UK electricity market

    International Nuclear Information System (INIS)

    Coffey, J.M.

    1995-01-01

    Nuclear Electric was formed in the public sector to operate only nuclear power plant, and the Company has been foremost in developing the UK's capability for PWR design and construction. It is now obliged to compete on equal terms with privately-owned generators, and we have made it clear that we would invest in further nuclear plant only if the terms were commercially attractive to the company. The competitive environment in which we now operate has led us to recognise that the priority for the Company in the Nuclear Review is to seek the commercial flexibility which accompanies privatisation. Accordingly, our evidence to the Government in the Nuclear Review has shown that the problems of confidence which surrounded nuclear power in 1989 have been substantially resolved. The improved accounting costs and low avoidable costs of the existing stations make the commercial case for their continued operation. The completion of Szewell B has not only given us a gist class new, profitable power plant, but given confidence in the costs and performance of any follow-on PWRs. In the longer term, a greater recognition of the external environmental costs of fossil-fuel generation may swing the market in favour of nuclar power construction. (orig.) [de

  18. The electric power market in Europe. The stakes and forecasts of the market reconfiguration

    International Nuclear Information System (INIS)

    2002-01-01

    This study takes stock on the eight main european electric power markets. It provides data on the electric power sector, knowledge on the european market competition, it analyzes the european companies mastership and management, the market reconfiguration, it evaluates and compares the financial performance of the sector leaders. (A.L.B.)

  19. Current status of nuclear power generation in Japan and directions in water cooled reactor technology development

    International Nuclear Information System (INIS)

    Miwa, T.

    1991-01-01

    Electric power demand aspects and current status of nuclear power generation in Japan are outlined. Although the future plan for nuclear power generation has not been determined yet the Japanese nuclear research centers and institutes are investigating and developing some projects on the next generation of light water reactors and other types of reactors. The paper describes these main activities

  20. Electric power monthly, July 1999, with data for April 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The Electric Power Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), Department of Energy prepares the Electric Power Monthly (EPM). This publication provides monthly statistics at the State, Census division, and US levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity retail sales, associated revenue, and average revenue per kilowatt hour of electricity sold. In addition, data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. The EIA publishes statistics in the EPM on net generation by energy source; consumption, stocks, quantity, quality, and cost of fossil fuels; and capability of new generating units by company and plant. 1 fig., 64 tabs.

  1. Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor

    International Nuclear Information System (INIS)

    Donoghue, J.E.; Donohew, J.N.; Golub, G.R.; Kenneally, R.M.; Moore, P.B.; Sands, S.P.; Throm, E.D.; Wetzel, B.A.

    1994-02-01

    This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC's ''Statement of Policy for the Regulation of Advanced Nuclear Power Plants'' (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC's preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant's research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified

  2. Institutional innovations required for widespread use of nuclear power

    International Nuclear Information System (INIS)

    Johnson, W.R.

    1992-01-01

    The social and economic benefits of additional electrical generating capacity in lesser developed countries are unquestioned, and a case can be made from economic and environmental considerations that much of this capacity should be nuclear powered. Obstacles to the introduction of nuclear power in the developing world include lack of a technical infrastructure and capital cost. Manpower shortage also detracts from a country's ability to effectively regulate a nuclear power enterprise. Two variations on the traditional institutional methods for supplying and regulating nuclear electric power are proposed. The first would be independent international companies that would design, finance, build, operate and maintain nuclear power stations, and sell electricity to local systems. The second would be an international safety regulatory system that could offer uniform, effective regulations and enforcement of the entire nuclear power enterprise at a level consistent with accepted world standards. These proposals coupled with the modular Advanced Liquid Metal Reactor based on Integral Fast Reactor technology would make possible a safe, economically feasible nuclear power operation that could be located anywhere in the world. (author). 7 refs

  3. Power reactors in member states

    International Nuclear Information System (INIS)

    1975-01-01

    This is the first issue of a periodical computer-based listing of civilian nuclear power reactors in the Member States of the IAEA, presenting the situation as of 1 April 1975. It is intended as a replacement for the Agency's previous annual publication of ''Power and Research Reactors in Member States''. In the new format, the listing contains more information about power reactors in operation, under construction, planned and shut down. As far as possible all the basic design data relating to reactors in operation have been included. In future these data will be included also for other power reactors, so that the publication will serve to give a clear picture of the technical progress achieved. Test and research reactors and critical facilities are no longer listed. Of interest to nuclear power planners, nuclear system designers, nuclear plant operators and interested professional engineers and scientists

  4. The French Electricity Company (EDF) and GEC ALSTHOM have signed the agreement for Chinese Laibin B electric power plant

    International Nuclear Information System (INIS)

    1997-01-01

    EDF and GEC ALSTHOM together with the government of Chinese Province Guangxi have organized in Pekin on 3 september 1997 a ceremony for signing a BOOT (Build, Own, Operate, Transfer) contract for the Coal Power Plant (2 x 360 MW) at Laibin B. This is the first Chinese BOOT contract in the power domain entirely financed by foreign capital. The two western companies which were retained for this project, following an international call for offers, invest USD 150 million of its own founds in this USD 600 million project. They will hold 60% and 40% of the capital of the company created for this project, respectively. The construction power plant is planned to be completed at the end of 1999 - beginning of 2000. After 15 years of industrial operation the power plant will be transferred to the autonomous government of the Province Guangxi. The communique contains the following 8 files: 1. The Laibin B power plant; 2. Build, Own, Operate, Transfer; 3. The autonomous Guangxi Province; 4. An outline of EDF in China; 5. Profile/activities of GEC ALSTHOM in China; 6. The 'Credit Agricole Indosuez' in China; 7. BZW Barclays PLC; 8. HSBC Investment Banking in China

  5. Evaluation of electric power distribution systems: period 1984/89

    International Nuclear Information System (INIS)

    Britto Filho, W.A. de; Pinto, V.G.

    1992-01-01

    The historical evolution of electric power distribution systems in Brazil, during 1984 to 1989 is described, showing the consumer market with the physical expansion of Distribution Networks and the results of quality from the services made by the companies to their clients. (C.G.C.)

  6. Vibrations measurement at the Embalse nuclear power plant's electrical generator

    International Nuclear Information System (INIS)

    Salomoni, R.C.; Belinco, C.G.; Pastorini, A.J.; Sacchi, M.A.

    1987-01-01

    After the modifications made at the Embalse nuclear power plant's electrical generator to reduce its vibration level produced by electromagnetic phenomena, it was necessary to perform measurements at the new levels, under different areas and power conditions. To this purpose, a work was performed jointly with the 'Vibrations Team' of the ANSALDO Company (the generator constructor) and the Hydrodynamic Assays Division under the coordination and supervision of the plant's electrical maintenance responsible. This paper includes the main results obtained and the instrumentation criteria and analysis performed. (Author)

  7. Risk management in the electric power sector, v. 16(61)

    International Nuclear Information System (INIS)

    Iliev, Atanas; Minovski, Dragan

    2008-01-01

    This paper presents the basics of the risk theory and the main methods which could be applied for risk management in electrical power system utilities. Taking into consideration that the risk and uncertainty not be completely eliminated, the engineers have to know to manage the risk and uncertainty. The main goal is to minimized the negative effects from accepted risk in order to increase expected incomes and expected profit. Special attention is dedicated to risk management in complex project in Electric Power Systems in a new deregulated electricity market which has the influence to the market stability, expected incomes and quality of the delivered electricity. Specially, the risk management in the companies - producers of the electricity is analysed, since theirs further investments in a rehabilitation of the current power plants as well in the construction of the new plants will be based on the economical principles of profit. (Author)

  8. Risk management in the electric power sector, v. 16(62)

    International Nuclear Information System (INIS)

    Iliev, Atanas; Minovski, Dragan

    2008-01-01

    This paper presents the basics of the risk theory and the main methods which could be applied for risk management in electrical power system utilities. Taking into consideration that the risk and uncertainty not be completely eliminated, the engineers have to know to manage the risk and uncertainty. The main goal is to minimized the negative effects from accepted risk in order to increase expected incomes and expected profit. Special attention is dedicated to risk management in complex project in Electric Power Systems in a new deregulated electricity market which has the influence to the market stability, expected incomes and quality of the delivered electricity. Specially, the risk management in the companies - producers of the electricity is analysed, since theirs further investments in a rehabilitation of the current power plants as well in the construction of the new plants will be based on the economical principles of profit. (Author)

  9. Irradiation effects on Zr-2.5Nb in power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Song, C., E-mail: Carol.Song@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2016-06-15

    Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, 'High Power Channel-type Reactor') reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr- 2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge. (author)

  10. Electric power monthly, February 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-16

    The Electric Power Monthly (EMP) presents monthly electricity statistics. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data in this report are presented for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. This publication provides monthly statistics at the US, Census division, and State levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. Statistics by company and plant are published in the EPM on the capability of new generating units, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fossil fuels.

  11. Electric power monthly, January 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The Electric Power Monthly (EPM) presents monthly electricity statistics. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data in this report are presented for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. This publication provides monthly statistics at the US Census division, and State levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. Statistics by company and plant are published in the EPM on the capability of new generating units, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fossil fuels

  12. Electric power monthly, January 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-26

    The Electric Power Monthly (EPM) presents monthly electricity statistics. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data in this report are presented for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. This publication provides monthly statistics at the US Census division, and State levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. Statistics by company and plant are published in the EPM on the capability of new generating units, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fossil fuels.

  13. Electric power monthly, October 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-20

    The Electric Power Monthly (EPM) presents monthly electricity statistics. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. Data in this report are presented for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. This publication provides monthly statistics at the US, Census division, and State levels for net generation, fossil fuel consumption and stocks, quantity and quality of fossil fuels, cost of fossil fuels, electricity sales, revenue, and average revenue per kilowatthour of electricity sold. Data on net generation, fuel consumption, fuel stocks, quantity and cost of fossil fuels are also displayed for the North American Electric Reliability Council (NERC) regions. Statistics by company and plant are published in the EPM on the capability of new generating units, net generation, fuel consumption, fuel stocks, quantity and quality of fuel, and cost of fossil fuels.

  14. Ultrahigh temperature vapor core reactor-MHD system for space nuclear electric power

    Science.gov (United States)

    Maya, Isaac; Anghaie, Samim; Diaz, Nils J.; Dugan, Edward T.

    1991-01-01

    The conceptual design of a nuclear space power system based on the ultrahigh temperature vapor core reactor with MHD energy conversion is presented. This UF4 fueled gas core cavity reactor operates at 4000 K maximum core temperature and 40 atm. Materials experiments, conducted with UF4 up to 2200 K, demonstrate acceptable compatibility with tungsten-molybdenum-, and carbon-based materials. The supporting nuclear, heat transfer, fluid flow and MHD analysis, and fissioning plasma physics experiments are also discussed.

  15. Reactor power reduction system and method

    International Nuclear Information System (INIS)

    Bruno, S.J.; Dunn, S.A.; Raber, M.

    1978-01-01

    A method of operating a nuclear power reactor is disclosed which enables an accelerated power reduction of the reactor without completely shutting the reactor down. The method includes monitoring the incidents which, upon their occurrence, would require an accelerated power reduction in order to maintain the reactor in a safe operation mode; calculating the power reduction required on the occurrence of such an incident; determining a control rod insertion sequence for the normal operation of the reactor, said sequence being chosen to optimize reactor power capability; selecting the number of control rods necessary to respond to the accelerated power reduction demand, said selection being made according to a priority determined by said control rod insertion sequence; and inserting said selected control rods into the reactor core. 11 claims, 13 figures

  16. Supercritical Water Reactor Cycle for Medium Power Applications

    International Nuclear Information System (INIS)

    BD Middleton; J Buongiorno

    2007-01-01

    Scoping studies for a power conversion system based on a direct-cycle supercritical water reactor have been conducted. The electric power range of interest is 5-30 MWe with a design point of 20 MWe. The overall design objective is to develop a system that has minimized physical size and performs satisfactorily over a broad range of operating conditions. The design constraints are as follows: Net cycle thermal efficiency (ge)20%; Steam turbine outlet quality (ge)90%; and Pumping power (le)2500 kW (at nominal conditions). Three basic cycle configurations were analyzed. Listed in order of increased plant complexity, they are: (1) Simple supercritical Rankine cycle; (2) All-supercritical Brayton cycle; and (3) Supercritical Rankine cycle with feedwater preheating. The sensitivity of these three configurations to various parameters, such as reactor exit temperature, reactor pressure, condenser pressure, etc., was assessed. The Thermoflex software package was used for this task. The results are as follows: (a) The simple supercritical Rankine cycle offers the greatest hardware simplification, but its high reactor temperature rise and reactor outlet temperature may pose serious problems from the viewpoint of thermal stresses, stability and materials in the core. (b) The all-supercritical Brayton cycle is not a contender, due to its poor thermal efficiency. (c) The supercritical Rankine cycle with feedwater preheating affords acceptable thermal efficiency with lower reactor temperature rise and outlet temperature. (d) The use of a moisture separator improves the performance of the supercritical Rankine cycle with feedwater preheating and allows for a further reduction of the reactor outlet temperature, thus it was selected for the next step. Preliminary engineering design of the supercritical Rankine cycle with feedwater preheating and moisture separation was performed. All major components including the turbine, feedwater heater, feedwater pump, condenser, condenser pump

  17. Scaling of silent electrical discharge reactors for hazardous organics destruction

    International Nuclear Information System (INIS)

    Coogan, J.J.; Rosocha, L.A.; Brower, M.J.; Kang, M.; Schmidt, C.A.

    1993-01-01

    Silent electrical discharges are used to produce highly reactive free radicals that destroy hazardous compounds entrained in gaseous effluents at ambient gas temperatures and pressures. We have carried out destruction experiments at Los Alamos on a range of volatile organic compounds (VOCs), including trichloroethylene (TCE), carbon tetrachloride, perchloroethylene (PCE), and chlorofluorocarbons (CFCs). We have measured a ''nine-factor'', the amount of energy required to reduce the VOC concentration by a factor of ten. For practical reactor power densities, the ''nine-factor'' can be used to predict the destruction an removal efficiency (DRE) in terms of gas flow rate and the number of reactor modules. This report proposes a modular, stackable architecture for scaling up the reactor throughput

  18. Dossier: energy in the center of debates. Electric power: Eurostat shades light to the situation

    International Nuclear Information System (INIS)

    Tourneur, J.C.

    2003-01-01

    Eurostat, the European Communities office of statistics, has analyzed the 1999-2000 competition indicators in the electric power market of the European member states. In the year 2000, the biggest company of each state was producing between 23 and 97% of the electric power. (J.S.)

  19. Outline of electric power installation plan for fiscal 1981

    International Nuclear Information System (INIS)

    Murakami, Masami

    1981-01-01

    The electric power installation plan for fiscal 1981 was submitted by power companies to the Minister of International Trade and Industry at the end of March. In 1990, the total demand of electric power will be 907.9 billion kWh, and the yearly rate of growth will be about 5%. The peak demand of electric power continues to be acute, and is expected to be 175.74 million kW. In order to supply power so as to always balance the demand, the reserve power of 8 to 10% of the maximum demand is required. According to the submitted plan, the power sources determined already are not sufficient, therefore it was planned to present 61 plants of 11.94 million kW in 1981 and 64 plants of 19.61 million kW in 1982 to the Power Source Development Coordination Council. If the power source development progresses as planned, the adequate rate to reserve is maintained up to 1990, and the stable supply of electric power seems to be secured. However when some delay occurs in the plan, serious obstacle to the demand and supply may arise. This plan fundamentally follows the policy to deversify power sources toward the target of substitute energy supply for petroleum. The power transmission facilities are also strengthened and expanded. The investment plan for fiscal 1981 is shown. (Kako, I.)

  20. Windonomics. Empirical essays on the economics of wind power in the Nordic electricity market

    Energy Technology Data Exchange (ETDEWEB)

    Mauritzen, Johannes

    2012-07-01

    From the introduction: The following chapters in this dissertation take up three topics surrounding the interaction of wind power investment in Denmark and the functioning of the deregulated Nordic electricity market. The first two chapters take up the issue of how wind power a affects prices in the deregulated market. I find that electricity price variation in the spot market is lower in days with more wind power. In the following chapter I extend this analysis to see how wind power in Denmark affects prices in neighbouring hydro power dominated Norway. I find that wind power affects the magnitude of trade between the countries asymmetrically - dependent on the net direction of trade. I also find that wind power has a slight but statistically significant negative effect on prices in Norway, likely due to a slackening of hydro power producers supply constraints. The last chapter starts with the observation that most turbines are scrapped in order to make room for a newer turbine. An opportunity cost that comes from the interaction of scarce land resources, technological change and government policy is then a dominant reason for the scrapping of wind turbines. This leads to the implication that turbines located on windier, better situated land have a higher risk of being scrapped. Policy is also shown to have a strong and in some respects unexpected effect on scrappings. Over the last two decades two major trends have taken place in power markets around the world. The first has been a movement towards market based power systems. Vertically integrated power companies have been split into component generation, transmission and retailing companies. Generation and retailing have been opened to competition. Increasingly, regulated prices and bilateral trade are being replaced by regulated markets that establish prices through auction mechanisms. The second trend has been investment in renewable and intermittent energy sources - notably wind power. What started as

  1. Advanced materials: The key to attractive magnetic fusion power reactors

    International Nuclear Information System (INIS)

    Bloom, E.E.

    1992-01-01

    Fusion is one of the most attractive central station power sources from the viewpoint of potential safety and environmental impact characteristics. Studies also indicate that fusion can be economically competitive with other options such as fission reactors and fossil-fired power stations. However, to achieve this triad of characteristics we must develop advanced materials with properties tailored for performance in the various fusion reactor systems. This paper discusses the desired characteristics of materials and the status of materials technology in four critical areas: (1) structural material for the first wail and blanket (FWB), (2) plasma-facing materials, (3) materials for superconducting magnets, and (4) ceramics for electrical and structural applications

  2. Advanced materials - the key to attractive magnetic fusion power reactors

    International Nuclear Information System (INIS)

    Bloom, E.E.

    1992-01-01

    Fusion is one of the most attractive central station power sources from the viewpoint of potential safety and environmental impact characteristics. Studies also indicate that fusion can be economically competitive with other options such as fission reactors and fossil-fired power stations. However, to achieve this triad of characteristics we must develop advanced materials with properties tailored for performance in the various fusion reactor systems. This paper discusses the desired characteristics of materials and the status of materials technology in four critical areas: (1) structural materials for the first wall and blanket (FWB), (2) plasmafacing materials, (3) materials for superconducting magnets, and (4) ceramics for electrical and structural applications. (author)

  3. Slovak Electric, Plc., 1997

    International Nuclear Information System (INIS)

    1997-06-01

    Slovenske elektrarne, a.s. (Slovak Electric, Plc.) was established on November 1, 1994 as one entity among new entities created as successors to the former Slovensky energeticky podnik. The subject activity is the generation of electric power, operation of transmission 220 kV and 400 kV systems, transit, import, export, and sales of electric power. Besides these activities the company deals with generation, distribution, and sales of heat. The company operates one nuclear power station, three thermal power plants, and thirty hydro power plants. One nuclear Power plant is under construction (state up tu June 1997). On this CD ROM next chapters are presented: (1) The structure of the company; (2) The production Units; (3) The economic power of the company; (4) The operation culture of the company; (5) The strategic plans of the company

  4. Feasible reactor power cutback logic development for an integral reactor

    International Nuclear Information System (INIS)

    Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

    2013-01-01

    Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

  5. Safety evaluation report related to the operation of Clinton Power Station, Unit No. 1. Docket No. 50-461, Illinois Power Company

    International Nuclear Information System (INIS)

    1982-07-01

    Information is presented concerning site characteristics; design criteria for structures, systems, and components; reactor coolant and connected systems; engineered safety systems; instrumentation and controls; electric power system; auxiliary systems; radiation protection; and conduct of operations

  6. The convergence of electric power and natural gas industries. Mergers and acquisitions in the United States

    International Nuclear Information System (INIS)

    Meritet, S.

    2000-01-01

    Deep transformations have taken place in the US electric power industry, in terms of organisation and competition. The reforms of the regulation of this sector have changed the operation rules and, as an answer, the companies have adapted their behaviour. The reorganization is characterized by the combination between new competitive markets with new occupations. The deregulation and the technical progress accelerate the reconfiguration of the industry with the convergence of the natural gas and electric power activities. Since 1996, the numerous mergers-acquisitions between companies are representative of the tight links existing between the two energy sources. In this work, the convergence of the natural gas and power industries in the US is examined. The study of the reconciliation between power and gas companies (mainly the utilities) stresses on the improvement of the combined companies efficiency. The first part deals with the reconfiguration of the US power industry. The second part analyzes the consequences of the gas-electricity mergers and acquisitions. It includes the exploitation of financial data and a classical econometric test about the 'size-scale-spread' relation. The re-composition of the value chain is at the center of the industrial economy problem: it gives the opportunity for new forms of markets and firms. (J.S.)

  7. Overview of US heavy-ion fusion commercial electric power systems assessment project. Revision

    International Nuclear Information System (INIS)

    Dudziak, D.J.; Pendergrass, J.H.; Saylor, W.W.

    1986-01-01

    The US heavy-ion fusion (HIF) research program is oriented toward development of multiple-beam induction linacs. Over the last two years an assessment has been performed of the potential of HIF as a competitive commercial electric power source. This assessment involved several technology performance and cost issues (e.g., final beam transport system, target manufacturing, beam stability in reactor cavity environments, and reactor cavity clearing), as well as overall power plant systems integration and tradeoff studies. Results from parametric analyses using a systems code developed in the project show cost of electricity (COE) values comparable with COEs from other magnetic fusion and inertial confinement fusion (ICF) plant studies; viz, 50-60 mills/kWh (1985 dollars) for 1-GWe plants. Also, significant COE insensitivity to major accelerator, target, and reactor parameters was demonstrated

  8. Analysis of loss of electrical power with the CATHENA model of the blanket and first wall cooling loop for the SEAFP reactor design

    International Nuclear Information System (INIS)

    Ross, W.E.

    1994-08-01

    This report documents the thermosyphoning analysis which was performed with the CATHENA network model of one of the blanket and first wall cooling loops of the SEAFP reactor design. This thermosyphoning analysis is similar to that reported in CFFTP-G--9355, Volume 4 except that a much larger decay power transient is used. Also, the pressurizer heaters are turned off following the loss of electrical power. This analysis is performed to assess the primary heat transport system behaviour for a complete loss of electrical power event (total loss of flow) and to estimate the rate of heatup of the in-core components. A description of the important aspects of the transient thermalhydraulic behaviour including coolant temperatures, circuit and sector flows, circuit pressure, pressurizer level and steam bleed flow, and first wall and blanket temperatures are provided. (author). 8 refs., 2 tabs., 26 figs

  9. Reactor power distribution monitor

    International Nuclear Information System (INIS)

    Hoizumi, Atsushi.

    1986-01-01

    Purpose: To grasp the margin for the limit value of the power distribution peaking factor inside the reactor under operation by using the reactor power distribution monitor. Constitution: The monitor is composed of the 'constant' file, (to store in-reactor power distributions obtained from analysis), TIP and thermocouple, lateral output distribution calibrating apparatus, axial output distribution synthesizer and peaking factor synthesizer. The lateral output distribution calibrating apparatus is used to make calibration by comparing the power distribution obtained from the thermocouples to the power distribution obtained from the TIP, and then to provide the power distribution lateral peaking factors. The axial output distribution synthesizer provides the power distribution axial peaking factors in accordance with the signals from the out-pile neutron flux detector. These axial and lateral power peaking factors are synthesized with high precision in the three-dimensional format and can be monitored at any time. (Kamimura, M.)

  10. Problems and legislative remedies of the parallel law systems in Japan for nuclear power reactors

    International Nuclear Information System (INIS)

    Irie, Kazutomo

    2011-01-01

    There are two established laws governing nuclear power reactors in Japan. One is the Electricity Utilities Industry Law, which regulates the nuclear power reactors, and the other is the so-called 'Reactor Regulation Law', which dually regulates the reactors in some phases. When a graded approach on the regulation of nuclear reactors was adopted, it extended over these two laws and was legislatively imperfect. Such imperfection created problems from the beginning. Also, the original regulatory structures presented by these laws had become obscure during the operation process of the graded regulation. The situation becomes further complicated by the revision of these laws in recent years. It appears that the trait of the regulatory procedural structure of the Electricity Utilities Industry Law has been weakened. As there is a pressing need to review the entire regulatory structure and to propose a unified regulatory system by combining these laws, this paper examines the merits and demerits of combining these laws under a unified regulation. (author)

  11. The Central Research Institute of Electric Power Industry and nuclear energy. Real images and views for compatibility of specialty and sociality

    International Nuclear Information System (INIS)

    Sato, Motohide

    2004-01-01

    The Central Research Institute of Electric Power Industry (CRIEPI) has been a motive power supporting electric energy and rich society in Japan as a center of electric power field in Japan under always challenging technologies advancing at a step since beginning of business as a special research institute on electrical power technology in Japan. And, on today receiving whole of liberalization on electric business, CRIEPI plans to carry out new development closer to society and nationals under a flag of 'contribution to society' by making its specialty and sociality compatible. Therefore, when social discussion on nuclear energy constructing basis of electric energy in Japan is noisy, here were summarized efforts, actual results, and topics for individual researching subjects shown as follows under showing basic attitude of CRIEPI to the nuclear energy: maintenance and administration techniques to rationally secure soundness of the light water reactor apparatuses; intermediate storage technique on spent fuels (concrete cask storage); survey, design and safety evaluation techniques supporting landfill disposal business of high level radioactive wastes; dry recycle technique and metal fuel fast reactors applicable to spent fuel processing at light water reactors; and small size fast reactors (4S reactors) usable for diverse applications. (G.K.)

  12. On the legal nature of electricity supply contracts concluded by electricity companies and power stations generating electricity from renewable energy sources

    International Nuclear Information System (INIS)

    Herrmann, B.J.

    1998-01-01

    Section 2 of the German Act for enhanced use of electricity from renewable energy sources (StEG) defines the obligation to contract but not the contractual obligations, i.e. the conditions of performance of the contract (supply and purchase of electricity and the legal obligations of contractors). The analysis here shows that characterising this mandatory contract required by the act as an agreement of purchase and sale more appropriately describes the legal nature of the contract and the intent of the legislator than other contracts for supply and purchase of electricity, as for instance those concluded by electric utilities and their customers. One specific aspect elaborated by the author is that the StEG does not constitute an obligation to supply on the part of the renewable energy generating power station, so that the power station operator is not obliged to ensure availability of the electricity at any time or in terms of supplies that can be called off by the purchasing utility, whereas the electric utility is obliged by section 2 of the StEG to purchase the contractual amounts from the generating station. (orig./CB) [de

  13. Main unit electrical protection at Sizewell 'B' power station

    International Nuclear Information System (INIS)

    Fischer, A.; Keates, T.

    1992-01-01

    For any power station, reliable electrical protection of the main generating units (generators plus generator transformers) has important commercial implications. Spurious trips cause loss of generation and consequent loss of revenue, while failure to rapidly isolate a fault leads to unnecessary damage and again, loss of generation and revenue. While these conditions apply equally to Sizewell B there are additional factors to be taken into consideration. A spurious trip of a main generating unit may lead to a trip of the reactor with an associated challenge to the shutdown and core cooling plant. The generator transformers, besides exporting power from the generators to the 400 kV National Grid, also import power from the Grid to the 11 kV Main Electrical System, which in turn is the preferred source of supply to the Essential Electrical System. The Main Unit Protection is designed to clear generator faults leaving this off-site power route intact. Hence failure to operate correctly could affect the integrity of the Essential Electrical Supplies. (Author)

  14. Progress in space nuclear reactor power systems technology development - The SP-100 program

    Science.gov (United States)

    Davis, H. S.

    1984-01-01

    Activities related to the development of high-temperature compact nuclear reactors for space applications had reached a comparatively high level in the U.S. during the mid-1950s and 1960s, although only one U.S. nuclear reactor-powered spacecraft was actually launched. After 1973, very little effort was devoted to space nuclear reactor and propulsion systems. In February 1983, significant activities toward the development of the technology for space nuclear reactor power systems were resumed with the SP-100 Program. Specific SP-100 Program objectives are partly related to the determination of the potential performance limits for space nuclear power systems in 100-kWe and 1- to 100-MW electrical classes. Attention is given to potential missions and applications, regimes of possible space power applicability, safety considerations, conceptual system designs, the establishment of technical feasibility, nuclear technology, materials technology, and prospects for the future.

  15. Electricity investments and nuclear development: investment choice modeling based on value creation

    International Nuclear Information System (INIS)

    Tehrani, B.S.; Bocquer, J.C.; Tomoda, T.

    2014-01-01

    While nuclear power may experience a technological breakthrough in Europe with Generation IV nuclear reactors within 2040, several events could question this possibility such as the Fukushima accident, the climate issues and the electricity market liberalization. This paper aims at analyzing investment choices in power generation capacities in the European scope, using simple DSM-inspired approaches. The power company and interacting stake holders in the investment choice process are considered as a complex system, and dependencies between investment drivers associated with each stake holder are studied. Focusing on the value for the power company, the compatibility of each power company with each of considered technologies is assessed through a Domain Mapping Matrix, including not only technical drivers, but also associated policy and market drivers. Technology preferences are modeled for main European companies in a set of scenarios, these preferences being then used to explore trends in generation mix. (authors)

  16. HTGR nuclear power plants: features of the VGR-50 high temperature reactor

    International Nuclear Information System (INIS)

    Glebov, V.P.; Bogoyavlenskii, R.G.; Glushkov, E.S.; Grebennik, V.N.; Ponomarev-Stepnoi, N.N.; Vinogradov, V.P.

    1983-01-01

    Current developmental trends in the power industry are guided to an appreciable extent by the increasing shortages of fossil fuels (coal, petroleum, natural gas) and by ecological problems. Assuming a continuing trend in worldwide consumption of energy resources, we see the electric power industry using up 20%, the other 80% (petroleum, coal, natural gas) going into generating industrial process heat and space heat, transportation, the chemical processing industry, the metallurgical industry, and other branches of industry. In the future, nuclear power will have the job of not only meeting the needs of the electric power industry, but also generating process heat. The most promising type of nuclear power plant available for solving complex problems in generation of electric power and heat for technological processes in the metallurgical processing industry and chemical processing industry is the one based around high-temperature reactors

  17. High-temperature nuclear reactor power plant cycle for hydrogen and electricity production – numerical analysis

    Directory of Open Access Journals (Sweden)

    Dudek Michał

    2016-01-01

    Full Text Available High temperature gas-cooled nuclear reactor (called HTR or HTGR for both electricity generation and hydrogen production is analysed. The HTR reactor because of the relatively high temperature of coolant could be combined with a steam or gas turbine, as well as with the system for heat delivery for high-temperature hydrogen production. However, the current development of HTR’s allows us to consider achievable working temperature up to 750°C. Due to this fact, industrial-scale hydrogen production using copper-chlorine (Cu-Cl thermochemical cycle is considered and compared with high-temperature electrolysis. Presented calculations show and confirm the potential of HTR’s as a future solution for hydrogen production without CO2 emission. Furthermore, integration of a hightemperature nuclear reactor with a combined cycle for electricity and hydrogen production may reach very high efficiency and could possibly lead to a significant decrease of hydrogen production costs.

  18. The Electric Company Writers' Notebook.

    Science.gov (United States)

    Children's Television Workshop, New York, NY.

    This handbook outlines the curriculum objectives for the children's television program, "The Electric Company." The first portion of the text delineates strategies for teaching symbol/sound analysis, including units on blends, letter groups, and word structure. A second section addresses strategies for reading for meaning, including…

  19. The PBMR electric power generation plant

    International Nuclear Information System (INIS)

    Perez S, G.; Santacruz I, I.; Martin del Campo M, C.

    2003-01-01

    This work has as purpose to diffuse in a general way the technology of the one modulate reactor of pebble bed. Because our country is in developing ways, the electric power demand goes in increase with that which it is presented the great challenge of satisfying this necessity, not only being in charge of the one fact per se, but also involving the environmental aspect and of security. Both factors are covered by the PBMR technology, which we approach in their basic aspects with the purpose that the public opinion knows it and was familiarized with this type of reactors that well could represent a solution for our growing electricity demand. We will treat this reactor visualizing it like part of a generation plant defining in first place to the itself reactor. We will see because that the system PBMR consists of 2 main sections: the reactor and the unit of energy conversion, highlighting that the principle of the PBMR reactor operation is based on the thermodynamic Brayton cycle cooled by helium and that, in turn, it transmits the energy in form of heat toward a gas turbine. In what concerns to the fuel, it peculiar design due to its spherical geometry is described, aspect that make to this reactor different from the traditional ones that use fuel rods. In fact in the fuel spheres of the PBMR it is where it resides great part of it inherent security since each particle of fuel, consistent in uranium dioxide, is lined one with coal and silicon carbide those which form an impenetrable barrier containing to the fuel and those radioactive products that result of the nuclear reactions. Such particles are encapsulated in graphite to form the sphere or 'pebble', of here born the name of this innovative technology. (Author)

  20. Modeling and forecasting of electrical power demands for capacity planning

    International Nuclear Information System (INIS)

    Al-Shobaki, S.; Mohsen, M.

    2007-01-01

    Jordan imports oil from neighboring countries for use in power production. As such, the cost of electricity production is high compared to oil producing countries. It is anticipated that Jordan will face major challenges in trying to meet the growing energy and electricity demands while also developing the energy sector in a way that reduces any adverse impacts on the economy, the environment and social life. This paper described the development of forecasting models to predict future generation and sales loads of electrical power in Jordan. Two models that could be used for the prediction of electrical energy demand in Amman, Jordan were developed and validated. An analysis of the data was also presented. The first model was based on the levels of energy generated by the National Electric Power Company (NEPCO) and the other was based on the levels of energy sold by the company in the same area. The models were compared and the percent error was presented. Energy demand was also forecasted across the next 60 months for both models. Results were then compared with the output of the in-house forecast model used by NEPCO to predict the levels of generated energy needed across the 60 months time period. It was concluded that the NEPCO model predicted energy demand higher than the validated generated data model by an average of 5.25 per cent. 8 refs., 5 tabs., 15 figs

  1. Modeling and forecasting of electrical power demands for capacity planning

    Energy Technology Data Exchange (ETDEWEB)

    Al-Shobaki, S. [Hashemite Univ., Zarka (Jordan). Dept. of Industrial Engineering; Mohsen, M. [Hashemite Univ., Zarka (Jordan). Dept. of Mechanical Engineering

    2007-07-01

    Jordan imports oil from neighboring countries for use in power production. As such, the cost of electricity production is high compared to oil producing countries. It is anticipated that Jordan will face major challenges in trying to meet the growing energy and electricity demands while also developing the energy sector in a way that reduces any adverse impacts on the economy, the environment and social life. This paper described the development of forecasting models to predict future generation and sales loads of electrical power in Jordan. Two models that could be used for the prediction of electrical energy demand in Amman, Jordan were developed and validated. An analysis of the data was also presented. The first model was based on the levels of energy generated by the National Electric Power Company (NEPCO) and the other was based on the levels of energy sold by the company in the same area. The models were compared and the percent error was presented. Energy demand was also forecasted across the next 60 months for both models. Results were then compared with the output of the in-house forecast model used by NEPCO to predict the levels of generated energy needed across the 60 months time period. It was concluded that the NEPCO model predicted energy demand higher than the validated generated data model by an average of 5.25 per cent. 8 refs., 5 tabs., 15 figs.

  2. The Effect of Current-Limiting Reactors on the Tripping of Short Circuits in High-Voltage Electrical Equipment

    International Nuclear Information System (INIS)

    Volkov, M. S.; Gusev, Yu. P.; Monakov, Yu. V.; Cho, Gvan Chun

    2016-01-01

    The insertion of current-limiting reactors into electrical equipment operating at a voltage of 110 and 220 kV produces a change in the parameters of the transient recovery voltages at the contacts of the circuit breakers for disconnecting short circuits, which could be the reason for the increase in the duration of the short circuit, damage to the electrical equipment and losses in the power system. The results of mathematical modeling of the transients, caused by tripping of the short circuit in a reactive electric power transmission line are presented, and data are given on the negative effect of a current-limiting resistor on the rate of increase and peak value of the transient recovery voltages. Methods of ensuring the standard requirements imposed on the parameters of the transient recovery voltages when using current-limiting reactors in the high-voltage electrical equipment of power plants and substations are proposed and analyzed

  3. Core Power Limits For A Lead-Bismuth Natural Circulation Actinide Burner Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Cliff Bybee; Kim, D.; Todreas, N. E.; Mujid S. Kazimi

    2002-04-01

    The Idaho National Engineering and Environmental Laboratory and Massachusetts Institute of Technology are investigating the suitability of lead-bismuth cooled fast reactors for producing low-cost electricity as well as for actinide burning. The design being considered here is a pool type reactor that burns actinides and utilizes natural circulation of the primary coolant, a conventional steam power conversion cycle, and a passive decay heat removal system. Thermal-hydraulic evaluations of the actinide burner reactor were performed to determine allowable core power ratings that maintain cladding temperatures below corrosion-established temperature limits during normal operation and following a loss-of-feedwater transient. An economic evaluation was performed to optimize various design parameters by minimizing capital cost. The transient power limit was initially much more restrictive than the steady-state limit. However, enhancements to the reactor vessel auxiliary cooling system for transient decay heat removal resulted in an increased power limit of 1040 MWt, which was close to the steady-state limit. An economic evaluation was performed to estimate the capital cost of the reactor and its sensitivity to the transient power limit. For the 1040 MWt power level, the capital cost estimate was 49 mills per kWhe based on 1999 dollars.

  4. Reactor power cutback system test experience at YGN 4

    International Nuclear Information System (INIS)

    Chi, Sung Goo; Kim, Se Chang; Seo, Jong Tae; Eom, Young Meen; Wook, Jeong Dae; Choi, Young Boo

    1995-01-01

    YGN 3 and 4 are the nuclear power plants having System 80 characteristics with a rated thermal output of 2815 MWth and a nominal net electrical output of 1040 MWe. YGN 3 achieved commercial operation on March 31, 1995 and YGN 4 completed Power Ascension Test (PAT) at 20%, 50%, 80% and 100% power by September 23, 1995. YGN 3 and 4 design incorporates the Reactor POwer Cutback System (RPCS) which reduces plant trips caused by Loss of Load (LOL)/ Turbine Trip 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 systems. The RPCS is designed to rapidly reduce reactor power by dropping preselected Control Element Assemblies (CEAs) while other NSSS control systems maintain process parameters within acceptable ranges. Extensive RPCS related tests performed during the initial startup of YGN 4 demonstrated that the RPCS can maintain the reactor on-line without opening primary or secondary safety valves and without actuating the Engineered Safety Features Actuation System (ESFAS). It is expected that use of the RPCS at YGN will increase the overall availability of the units and reduce the number of challenges to plant safety systems

  5. Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2

    International Nuclear Information System (INIS)

    Tijerina S, F.

    2008-01-01

    The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

  6. Market power versus regulatory power in the Spanish electricity system, 1973-1996

    International Nuclear Information System (INIS)

    Garrues-Irurzun, Josean

    2010-01-01

    This study not only establishes that the institutional changes (the change of political regime) and economic changes (the energy crisis) that occurred during the 70s and 80s had an important effect on business strategies within the Spanish electricity sector, but, above all, it shows how the resulting regulatory model was not the product of any clearly defined plan on the part of the Spanish authorities (as the majority of authors seem to implicitly or explicitly maintain), but rather it arose from the dialectical interaction between companies which resisted losing the power of the market, and institutions which, in order to define any medium term energy policy in the future European domestic electricity market, required an increase in their regulatory power. (author)

  7. Space and Terrestrial Power System Integration Optimization Code BRMAPS for Gas Turbine Space Power Plants With Nuclear Reactor Heat Sources

    Science.gov (United States)

    Juhasz, Albert J.

    2007-01-01

    In view of the difficult times the US and global economies are experiencing today, funds for the development of advanced fission reactors nuclear power systems for space propulsion and planetary surface applications are currently not available. However, according to the Energy Policy Act of 2005 the U.S. needs to invest in developing fission reactor technology for ground based terrestrial power plants. Such plants would make a significant contribution toward drastic reduction of worldwide greenhouse gas emissions and associated global warming. To accomplish this goal the Next Generation Nuclear Plant Project (NGNP) has been established by DOE under the Generation IV Nuclear Systems Initiative. Idaho National Laboratory (INL) was designated as the lead in the development of VHTR (Very High Temperature Reactor) and HTGR (High Temperature Gas Reactor) technology to be integrated with MMW (multi-megawatt) helium gas turbine driven electric power AC generators. However, the advantages of transmitting power in high voltage DC form over large distances are also explored in the seminar lecture series. As an attractive alternate heat source the Liquid Fluoride Reactor (LFR), pioneered at ORNL (Oak Ridge National Laboratory) in the mid 1960's, would offer much higher energy yields than current nuclear plants by using an inherently safe energy conversion scheme based on the Thorium --> U233 fuel cycle and a fission process with a negative temperature coefficient of reactivity. The power plants are to be sized to meet electric power demand during peak periods and also for providing thermal energy for hydrogen (H2) production during "off peak" periods. This approach will both supply electric power by using environmentally clean nuclear heat which does not generate green house gases, and also provide a clean fuel H2 for the future, when, due to increased global demand and the decline in discovering new deposits, our supply of liquid fossil fuels will have been used up. This is

  8. Low-temperature thermionics in space nuclear power systems with the safe-type fast reactor

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.; Yarygin, V.I.; Lazarenko, G.E.; Zabudko, A.N.; Ovcharenko, M.K.; Pyshko, A.P.; Mironov, V.S.; Kuznetsov, R.V.

    2007-01-01

    The potentialities of the use of the low-temperature thermionic converters (TIC) with the emitter temperature ≤ 1500 K in the space nuclear power system (SNPS) with the SAFE-type (Safe Affordable Fission Engine) fast reactor proposed and developed by common efforts of American experts have been considered. The main directions of the 'SAFE-300-TEG' SNPS (300 kW(thermal)) design update by replacing the thermoelectric converters with the low-temperature high-performance thermionic converters (with the barrier index V B ≤ 1.9 eV and efficiency ≥ 10%) meant for a long-term operation (5 years at least) as the components of the SAFE-300-TIC SNPS for a Lunar base have been discussed. The concept of the SNPS with the SAFE-type fast reactor and low-temperature TICs with specific electric power of about 1.45 W/cm 2 as the components of the SAFE-300-TIC system meeting the Nasa's initial requirements to a Lunar base with the electric power demand of about 30 kW(electrical) for robotic mission has been considered. The results, involving optimization and mass-and-size estimation, show that the SAFE-300-TIC system meets the initial requirements by Nasa to the lunar base power supply. The main directions of the system update aimed at the output electric power increase up to 100 kW(electrical) have also been presented. (authors)

  9. Nuclear power reactors in the world. April 2000 ed.

    International Nuclear Information System (INIS)

    2000-01-01

    Nuclear data presented in this annual publication are based on actual statistical data collected by the IAEA Power Reactor Information System (PRIS). Energy and electricity data for 1999 are estimated since latest available information from the Statistical Office of the United Nations is for 1997. Population data originate from the 'World Population Prospects' (revision 1999) published by the Population Division of the UN Statistical office, and the 1999 values are estimates. The future growth of energy, electricity and nuclear power up to 2020 is presented as low and high estimates in order to encompass the uncertainties associated with the future. These estimates should be viewed as very general growth trends whose validity must constantly be subjected to critical review

  10. Interaction in the large energetic companies in the Republic of Macedonia

    International Nuclear Information System (INIS)

    Janevski, Risto

    1999-01-01

    After disintegration of former power energetic system of Yugoslavia 1991, the Republic of Macedonia has faced enormous problems in the energetic field. It was necessary to realize all options in order to secure enough electric power for normal economic capacities function. In that course a direct involvement of five large companies, which represent very significant energetic subjects, will largely determine the future energetic conditions and circumstances in our country. These are the following companies: P.E. Electric Power Company Of Macedonia; OKTA Crude Oil Refinery; Heat Power Company; HEK Jugohrom; Fenimak. The paper presents the electric power consumption of these macro energetic companies during the period 1991-1998

  11. [Tampa Electric Company IGCC project]. 1996 DOE annual technical report, January--December 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    Tampa Electric Company`s Polk Power Station Unit 1 (PPS-1) Integrated Gasification Combined Cycle (IGCC) demonstration project uses a Texaco pressurized, oxygen-blown, entrained-flow coal gasifier to convert approximately 2,000 tons per day of coal to syngas. The gasification plant is coupled with a combined cycle power block to produce a net 250 MW electrical power output. Coal is slurried in water, combined with 95% pure oxygen from an air separation unit, and sent to the gasifier to produce a high temperature, high pressure, medium-Btu syngas with a heat content of about 250 BTUs/cf (HHV). The syngas then flows through a high temperature heat recovery unit which cools the syngas prior to its entering the cleanup systems. Molten coal ash flows from the bottom of the high temperature heat recovery unit into a water-filled quench chamber where it solidifies into a marketable slag by-product. Approximately 10% of the raw, hot syngas at 900 F is designed to pass through an intermittently moving bed of metal-oxide sorbent which removes sulfur-bearing compounds from the syngas. PPS-1 will be the first unit in the world to demonstrate this advanced metal oxide hot gas desulfurization technology on a commercial unit. The emphasis during 1996 centered around start-up activities.

  12. Research and development of a super fast reactor (12). Considerations for the reactor characteristics

    International Nuclear Information System (INIS)

    Goto, Shoji; Ishiwatari, Yuki; Oka, Yoshiaki

    2008-01-01

    A research program aimed at developing the Super Fast Reactor (Super FR) has been entrusted by the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan since December 2005. It includes the following three projects. (A) Development of the Super Fast Reactor concept. (B)Thermal-hydraulic experiments. (C) Materials development. Tokyo Electric Power Company (TEPCO) has joined this program and works on part (A) together with the University of Tokyo. From the utility's viewpoint, it is important to consider the most desirable characteristics for Super FR to have. Four issues were identified in project (A), (1) Fuel design, (2) Reactor core design, (3) Safety, and (4) Plant characteristics of Super FR. This report describes the desired characteristics of Super FR with respect to item (1) fuel design and item (2) Reactor core design, as compared with a boiling water reactor (BWR) plant. The other two issues will be discussed in this project, and will also be considered in the design process of Super FR. (author)

  13. Reactor power control system

    International Nuclear Information System (INIS)

    Tomisawa, Teruaki.

    1981-01-01

    Purpose: To restore reactor-power condition in a minimum time after a termination of turbine bypass by reducing the throttling of the reactor power at the time of load-failure as low as possible. Constitution: The transient change of the internal pressure of condenser is continuously monitored. When a turbine is bypassed, a speed-control-command signal for a coolant recirculating pump is generated according as the internal pressure of the condenser. When the signal relating to the internal pressure of the condenser indicates insufficient power, a reactor-control-rod-drive signal is generated. (J.P.N.)

  14. Deregulation of the California electric power industry: An analysis of electric and natural gas corporate mergers and their effect on the California electric power market

    Science.gov (United States)

    Hornbuckle, James Dixon

    Deregulation of the electric utility industry in California is moving in a direction that places greater reliance on the market forces of competition. Investor owned utilities (IOU's) are using mergers and acquisitions to improve their ability to compete in this new environment. Two large mergers were proposed in 1996 that could affect the California market. The first is between Enron Corporation, a large power marketer and Portland General Corporation, owner of Portland General Electric. The second is between Pacific Enterprises Inc., owner of Southern California Gas Company, the largest natural gas utility in the U. S., and Enova Corporation, owner of San Diego Gas and Electric Company. Understanding the impact of these mergers on the California electric power market is the focus of this study. This study examines hypotheses dealing with: (1) Merger Strategy, (2) Efficiency, and (3) Market Power. Using the Miles and Snow (1978) typology, I develop a strategic orientation model for the merger participants and their competitors. The results suggest a two-stage strategic orientation: (1) regulated core business stage, where the firms follow a Defender strategy, and (2) unregulated business stage, where the firms follow a Prospector strategy. Further, the results show the mergers are consistent with the strategy of Enron and Pacific Enterprises. Event study methodology, dollar gains/losses and market value weighted returns are used to determine if the mergers support the efficiency hypothesis. The evidence suggests the mergers lead to increased competitive advantage through improved efficiency for the participants. The results also suggest the mergers do not harm the rivals. The results of structural changes made by the California Public Utilities Commission (CPUC) in deregulation of the California market and analysis of the mergers by the CPUC and the Public Utility Commission of Oregon suggest that the exercise of market power is not a significant issue. Finally

  15. 75 FR 8753 - Carolina Power & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental...

    Science.gov (United States)

    2010-02-25

    ... Dusenbury of the North Carolina Department of Environment and Natural Resources regarding the environmental... & Light Company, Brunswick Steam Electric Plant, Units 1 and 2; Environmental Assessment and Finding of No... identification of licensing and regulatory actions requiring environmental assessments,'' the NRC prepared an...

  16. The electric power engineering handbook electric power generation, transmission, and distribution

    CERN Document Server

    Grigsby, Leonard L

    2012-01-01

    Featuring contributions from worldwide leaders in the field, the carefully crafted Electric Power Generation, Transmission, and Distribution, Third Edition (part of the five-volume set, The Electric Power Engineering Handbook) provides convenient access to detailed information on a diverse array of power engineering topics. Updates to nearly every chapter keep this book at the forefront of developments in modern power systems, reflecting international standards, practices, and technologies. Topics covered include: * Electric Power Generation: Nonconventional Methods * Electric Power Generation

  17. A review of fast reactor programme in Japan

    International Nuclear Information System (INIS)

    1998-01-01

    This report describes the development and activities on fast reactor in Japan for the period of April 1996 - March 1997. During this period, the 30th duty cycle operation has been started in the Experimental Fast Reactor ''''Joyo''''. The cause investigation on the sodium leak incident has completed and the safety examination are being performed in the Prototype Fast Breeder Reactor ''''Monju''''. The three years design study since FY1994 on the plant optimization of the Demonstration FBR has been completed by the Japan Atomic Power Company (JAPC). Related research and development works are underway at several organizations under the discussion and coordination of the Japanese FBR R and D Steering Committee, which is composed of Power Reactor and Nuclear Fuel Development Corporation (PNC), JAPC, Japan Atomic Energy Research Institute (JAERI) and Central Research Institute of Electric Power Industry (CRIEPI). In November 1996, the Japan Atomic Energy Commission (JAEC) established a Social Gathering Meeting to discuss generally the significance of FBR development in Japan for the future. (author)

  18. Assessment of very high-temperature reactors in process application. Appendix I. Evaluation of the reactor system

    International Nuclear Information System (INIS)

    Jones, J.E. Jr.; Spiewak, I.

    1976-12-01

    In April 1974, the U.S. Atomic Energy Commission [now the Energy Research and Development Administration (ERDA)] authorized General Atomic Company, General Electric Company, and Westinghouse Electric Corp., Astronuclear Laboratory, to assess the available technology for producing heat using very high-temperature nuclear reactors. An evaulation of these studies and of the technical and economic potential of very high-temperature reactors (VHTR) is presented. The VHTR is a helium-cooled graphite-moderated reactor. The concepts and technology are evaluated for producing process stream temperatures of 649, 760, 871, 982, and 1093 0 C (1200, 1400, 1600, 1800, and 2000 0 F). There are a number of large industrial process heat applications that could utilize the VHTR

  19. Low power modular power generating reactors or Small Modular Reactors (SMR)

    International Nuclear Information System (INIS)

    Chenais, Jacques

    2016-01-01

    Electronuclear reactors were small reactors at the beginning, and then tend to be always bigger and more powerful, but since some recent times, several countries specialized in reactor design and fabrication (USA, Russia, China, and South Korea) have been developing Small Modular Reactors (SMR) of less than 300 MW. As France has already produced feasibility studies and is about to launch a SMR development programme, the author comments some specific aspects of this new architecture of reactors, characterises the targeted markets, gives an overview of the various more or less advanced existing concepts: a floating barge in Russia, the SMART 100 MW project in South Korea, several concepts in the USA (the mPower 125 MW, the NuScale 45 MW, the Westinghouse 225 MW, and the HI-SMUR 160 MW projects), the ACP 100 MW in China, the CAREM 27 MW in Argentina. French projects developed by the CEA, EDF, Areva and DCNS are then presented

  20. Identification of fast power reactivity effect in nuclear power reactor

    International Nuclear Information System (INIS)

    Efanov, A.I.; Kaminskas, V.A.; Lavrukhin, V.S.; Rimidis, A.P.; Yanitskene, D.Yu.

    1987-01-01

    A nuclear power reactor is an object of control with distributed parameters, characteristics of which vary during operation time. At the same time the reactor as the object of control has internal feedback circuits, which are formed as a result of the effects of fuel parameters and a coolant (pressure, temperature, steam content) on the reactor breeding properties. The problem of internal feedback circuit identification in a nuclear power reactor is considered. Conditions for a point reactor identification are obtained and algorithms of parametric identification are constructed. Examples of identification of fast power reactivity effect for the RBMK-1000 reactor are given. Results of experimental testing have shown that the developed method of fast power reactivity effect identification permits according to the data of normal operation to construct adaptive models for the point nuclear reactor, designed for its behaviour prediction in stationary and transition operational conditions. Therefore, the models considered can be used for creating control systems of nuclear power reactor thermal capacity (of RBMK type reactor, in particular) which can be adapted to the change in the internal feedback circuit characteristics