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Sample records for vver nuclear power

  1. Developing the European Center of Competence on VVER-Type Nuclear Power Reactors

    Science.gov (United States)

    Geraskin, Nikolay; Pironkov, Lyubomir; Kulikov, Evgeny; Glebov, Vasily

    2017-01-01

    This paper presents the results of the European educational projects CORONA and CORONA-II which are dedicated to preserving and further developing nuclear knowledge and competencies in the area of VVER-type nuclear power reactors technologies (Water-Water Energetic Reactor, WWER or VVER). The development of the European Center of Competence for…

  2. The virtual digital nuclear power plant: A modern tool for supporting the lifecycle of VVER-based nuclear power units

    Science.gov (United States)

    Arkadov, G. V.; Zhukavin, A. P.; Kroshilin, A. E.; Parshikov, I. A.; Solov'ev, S. L.; Shishov, A. V.

    2014-10-01

    The article describes the "Virtual Digital VVER-Based Nuclear Power Plant" computerized system comprising a totality of verified initial data (sets of input data for a model intended for describing the behavior of nuclear power plant (NPP) systems in design and emergency modes of their operation) and a unified system of new-generation computation codes intended for carrying out coordinated computation of the variety of physical processes in the reactor core and NPP equipment. Experiments with the demonstration version of the "Virtual Digital VVER-Based NPP" computerized system has shown that it is in principle possible to set up a unified system of computation codes in a common software environment for carrying out interconnected calculations of various physical phenomena at NPPs constructed according to the standard AES-2006 project. With the full-scale version of the "Virtual Digital VVER-Based NPP" computerized system put in operation, the concerned engineering, design, construction, and operating organizations will have access to all necessary information relating to the NPP power unit project throughout its entire lifecycle. The domestically developed commercial-grade software product set to operate as an independently operating application to the project will bring about additional competitive advantages in the modern market of nuclear power technologies.

  3. Assessment of computer codes for VVER-440/213-type nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Szabados, L.; Ezsol, Gy.; Perneczky [Atomic Energy Research Institute, Budapest (Hungary)

    1995-09-01

    Nuclear power plant of VVER-440/213 designed by the former USSR have a number of special features. As a consequence of these features the transient behaviour of such a reactor system should be different from the PWR system behaviour. To study the transient behaviour of the Hungarian Paks Nuclear Power Plant of VVER-440/213-type both analytical and experimental activities have been performed. The experimental basis of the research in the PMK-2 integral-type test facility , which is a scaled down model of the plant. Experiments performed on this facility have been used to assess thermal-hydraulic system codes. Four tests were selected for {open_quotes}Standard Problem Exercises{close_quotes} of the International Atomic Energy Agency. Results of the 4th Exercise, of high international interest, are presented in the paper, focusing on the essential findings of the assessment of computer codes.

  4. Neutron dosimetry in EDF experimental surveillance programme for VVER-440 nuclear power plants

    International Nuclear Information System (INIS)

    Brumovsky, M.; Erben, O.; Novosad, P.; Zerola, L.; Hogel, J.; Trollat, C.

    2001-01-01

    Fourteen chains containing experimental surveillance material specimens of the VVER 440/213 nuclear power reactor pressure vessels were irradiated in the surveillance channels of the Nuclear Power Plant Dukovany in the Czech Republic. The irradiation periods were one, two or three cycles. The chains contained different number and types of containers, the omitted ones were replaced by chain elements. All of the containers were instrumented with wire neutron fluence detectors, some of the containers in the chain had spectrometric sets of neutron fluence monitors. For the absolute fluence values evaluation it was taken into account time history of the reactor power and local changes of the neutron flux along the reactor core height, correction factors due to the orientation of monitors with respect to the reactor core centre. Unfolding programs SAND-II or BASA-CF were used. The relative axial fluence distribution was obtained from the O-wire measurements. Neutron fluence values above 0.5 MeV energy and above 1.0 MeV energy in the container axis on the axial positions of the sample centres and fluence values in the geometric centre of the samples was calculated making use the exponential attenuation model of the incident neutron beam. Received fast neutron fluence values can be used as reference values to all VVER-440 type 213 nuclear power plant reactors. (author)

  5. Thermal-hydraulic studies on the safety of VVER-440 type nuclear power plants

    International Nuclear Information System (INIS)

    Tuunanen, J.

    1994-01-01

    The thesis includes several thermal-hydraulic analyses related to the Loviisa VVER-440 nuclear power plant units. The work consists of experimental studies, analysis of the experiments, analysis of some plant transients and development of a calculational model for calculation of boric concentrations in the reactor. In the first part of thesis, in the case of simulation of boric acid solution behaviour during long-term cooling period of LOCAs, experiments were performed in scaled-down test facilities. The experimental data together with the results of RELAP5/MOD3 simulations were used to develop a model for calculations of boric acid concentrations in the reactor during LOCAs. In the second part, in the case of simulation of horizontal generators, experiments were performed with PACTEL integral test loop to simulate loss of feedwater transients. The PACTEL experiments as well as earlier REWETT-III natural circulation tests, were analyzed with RELAP5/MOD3 Version 5m5 code. The third part of the work consists of simulations of Loviisa VVER reactor pump trip transients with RELAP5/MOD1-Eur, RELAP5/MOD3 and CATHARE codes. (56 refs., 9 figs.)

  6. The role of PRA in the safety assessment of VVER Nuclear Power Plants in Ukraine

    International Nuclear Information System (INIS)

    Kot, C.

    1999-01-01

    Ukraine operates thirteen (13) Soviet-designed pressurized water reactors, VVERS. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs), in accordance with new SAR content requirements issued in September 1995, by the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine. The requirements are in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The last two requirements, on PRA and BDBA, are new, and the DBA requirements are an expanded version of the older SAR requirements. The US Department of Energy (USDOE), as part of its Soviet-Designed Reactor Safety activities, is providing assistance and technology transfer to Ukraine to support their nuclear power plants (NPPs) in developing a Western-type technical basis for the new SARs. USDOE sponsored In-Depth Safety Assessments (ISAs) are in progress at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1, and a follow-on study has been initiated at Khmenytskyy Unit 1. The ISA projects encompass most areas of plant safety evaluation, but the initial emphasis is on performing a detailed, plant-specific Level 1 Internal Events PRA. This allows the early definition of the plant risk profile, the identification of risk significant accident sequences and plant vulnerabilities and provides guidance for the remainder of the safety assessments

  7. Design issues concerning Iran's Bushehr nuclear power plant VVER-1000 conversion

    International Nuclear Information System (INIS)

    Carson, C.F.

    1996-01-01

    On January 8, 1995, the Atomic Energy Organization of Iran (AEOI) signed a contract for $800 million with the Russian Federation Ministry for Atomic Energy (Minatom) to complete Bushehr nuclear power plant (BNPP) unit 1. The agreement called for a Russian VVER-1000/320 pressurized water reactor (PWR) to be successfully installed into the existing German-built BNPP facilities in 5 yr. System design differences, bomb damage, and environmental exposure are key issues with which Minatom must contend in order to fulfill the contract. The AEOI under the Shah of Iran envisioned Bushehr as the first of many nuclear power plants, with Iran achieving 24 GW(electric) by 1993 and 34 GW(electric) by 2000. Kraftwerk Union AG (KWU) began construction of the two-unit plant near the Persian Gulf town of Halileh in 1975. Unit 1 was ∼80% complete and unit 2 was ∼50% complete when construction was interrupted by the 1979 Iranian Islamic revolution. Despite repeated AEOI attempts to lure KWU and other companies back to Iran to complete the plant, Western concerns about nuclear proliferation in Iran and repeated bombings of the plant during the 1980-1988 Iran-Iraq war dissuaded Germany from resuming construction

  8. Several perspectives on water-chemical cycles for nuclear power stations equipped with type VVER and RBMK reactors

    International Nuclear Information System (INIS)

    Mamet, A.P.; Mamet, V.A.; Pashevich, V.I.; Nazarenko, P.N.

    1982-01-01

    Water-chemical cycles for loops I and II of VVER reactors are discussed. These cycles are mixed ammonia-sodium with a variable concentration of boric acid and ammonia hydrazine with a pH factor of 9.1 +/- 0.1. New water-chemical cycles are considered for use in both existing and new nuclear power plants. Application of these new water-chemical cycles showed produce a significant improvement in operating conditions of nuclear power plants. Upon accumulation of sufficient operating experience with these cycles, it should be possible to raise the issue of revising applicable standard documentation

  9. The most extensive reconstruction of nuclear power plant with VVER 440/V230 reactor

    International Nuclear Information System (INIS)

    Ferenc, M.

    2000-01-01

    The nuclear power plant V-1 Bohunice consists of two VVER-440 units with V-230 reactors. Unit 1 was commissioned in 1978 and Unit 2 in 1980. Large experience and knowledge from the operation of previous units with V-230 reactors were incorporated into the V-1 design, which resulted in a higher level of safety and operational reliability of these units. The Siemens company which won an international bidding process developed these basic goals for the Gradual Upgrading into the so called Basic Engineering (BE). For the implementation of the Gradual Upgrading in line with the BE, Rekon consortium was established consisting of Siemens and VUJE. The implementation of the Gradual Upgrading is scheduled for the time period of 1996 - 2000. Siemens was responsible for the upgrading strategy - based on the approved results of the basic engineering phase and the PSAR, the engineering and realization of all I and C improvements, and also for the seismic upgrade. VUJE's responsibility covered the detailed engineering and implementation of mechanical, electrical and civil part of upgrading measures as well as overall organisation and evaluation of verification tests. The consortium awarded contracts for final planning and design, installation services and commissioning to other Slovakian subcontractors in order to ensure the largest possible local content. The gradual reconstruction of the V-1 Bohunice with V230 reactors represents a comprehensive reconstruction of safety-related systems and equipment. Following its completion, the units will be operated with a safety level accepted internationally. (author)

  10. Study, analysis, assess and compare the nuclear engineering systems of nuclear power plant with different reactor types VVER-1000, namely AES-91, AES-92 and AES-2006

    International Nuclear Information System (INIS)

    Le Van Hong; Tran Chi Thanh; Hoang Minh Giang; Le Dai Dien; Nguyen Nhi Dien; Nguyen Minh Tuan

    2015-01-01

    On November 25, 2009, in Hanoi, the National Assembly had been approved the resolution about policy for investment of nuclear power project in Ninh Thuan province which include two sites, each site has two units with power around 1000 MWe. For the nuclear power project at Ninh Thuan 1, Vietnam Government signed the Joint-Governmental Agreement with Russian Government for building the nuclear power plant with reactor type VVER. At present time, the Russian Consultant proposed four reactor technologies can be used for Ninh Thuan 1 project, namely: AES-91, AES-92, AES-2006/V491 and AES-2006/V392M. This report presents the main reactor engineering systems of nuclear power plants with VVER-1000/1200. The results from analysis, comparison and assessment between the designs of AES-91, AES-92 and AES-2006 are also presented. The obtained results show that the type AES-2006 is appropriate selection for Vietnam. (author)

  11. IVO participation in IAEA benchmark for VVER-type nuclear power plants seismic analysis and testing

    International Nuclear Information System (INIS)

    Varpasuo, P.

    1997-12-01

    This study is a part of the IAEA coordinated research program 'Benchmark study for the Seismic Analysis and Testing of VVER Type NPPs'. The study reports the numerical simulation of the blast test for Paks and Kozloduy nuclear power plants beginning from the recorded free-field response and computing the structural response at various points inside the reactor building. The full-scale blast tests of the Paks and Kozloduy NPPs took place in December 1994 and in July 1996. During the tests the plants operated normally. The instrumentation for the tests consisted of 52 recording channels with 200 Hz sampling rate. Detonating 100 kg charges in 50-meter deep boreholes at 2.5-km distance from the plant carried out the blast tests. The 3D structural models for both reactor buildings were analyzed in the frequency domain. The number of modes extracted in both cases was about 500 and the cut-off frequency was 25 Hz. In the response history run the responses of the selected points were evaluated. The input values for response history run were the three components of the excitation, which were transformed from time domain to the frequency domain with the aid of Fourier transform. The analysis was carried out in frequency domain and responses were transferred back to time domain with inverse Fourier transform. The Paks and Kozloduy blast tests produced a wealth of information on the behavior of the nuclear power plant structures excited by blast type loads containing also the low frequency wave train if albeit with small energy content. The comparison of measured and calculated results gave information about the suitability of the selected analysis approach for the investigated blast type loading

  12. Possible emission of radioactive fission products during off-design accidents at a nuclear power plant with VVER-1000 reactor

    International Nuclear Information System (INIS)

    Dubkov, A.P.; Kozlov, V.F.; Luzanova, L.M.

    1995-01-01

    It is well known that eight nuclear power plants with VVER-1000 reactors have been constructed in Russia, Ukraine, and in the Republic of Belarus and they have been operating successfully without any serious accidents since 1980. These facilities have been analyzed for various accident scenarios, and measures have been incorporated which will prevent core damage during these possible events. However, an off-design accident can occur, and in such a case, the radiological consequences would exceed the worst design accidents. This paper reviews a number of potential off-design accidents in order to develop an accident plan to mitigate the consequences of such an accident

  13. Experience in modernization of safety I and C in VVER 440 nuclear power plants Bohunice V1 and Paks

    International Nuclear Information System (INIS)

    Martin, M.

    2000-01-01

    For nuclear power plants which have been in operation for more than 15 years, backfitting or even complete replacement of the instrumentation and control (I and C) equipment becomes an increasingly attractive option, motivated not only by the objective to reduce the cost of I and C system maintenance and repair but also to prolong or at least to safeguard the plant life-time: optimized spare-part management through use of standard equipment; reduction of number and variety of different items of equipment by implementing functions stepwise in application software; adding new functionality in the application software which was not possible in the old technology due to lack of space; safeguarding of long-term After-Sales-Service. Some years ago Bohunice V1 NPP, Slovak Republic and Paks NPP, Hungary intended to replace parts of their Safety I and C, mainly the Reactor Trip System, the Reactor Limitation System and the Neutron Flux Excore Instrumentation and Monitoring Systems. After a Basic Engineering Phase in Bohunice V1 and a Feasibility Study in Paks both plants decided to use the Siemens' Digital Safety I and C System TELEPERM XS to modernize their plants. Both Bohunice, Unit 2 and Paks, Unit 1 have been back on line for over six months with the new Digital Safety I and C. At the present time Bohunice, Unit 1 and within the next few months Paks, Unit 2 will be replaced. Trouble-free start-ups and no major problems under operation in the first two plants were based on: thorough understanding of the VVER 440 technology; comprehensive planning together with the plant operators and authorities; the possibility to adapt TELEPERM XS to every plant type; the execution of extensive pre-operational tests. Regarding these modernization measures Siemens, as well as the above Operators, have gained considerable experience in the field of I and C Modernization in VVER 440 NPPs. Important aspects of this experience are: how to transfer the VVER technology to TELEPERM XS; how to

  14. Structural strength during severe reactor accidents of the VVER- 91 nuclear power plant

    International Nuclear Information System (INIS)

    Varpasuo, P.

    1999-12-01

    The report summarises the studies carried out in Fortum Engineering (formerly IVO Power Engineering) between the years of 1992 and 1997 concerning ultimate strength of structures designed to mitigate and contain the consequences of various core melt accident scenarios. The report begins with the description of containment loading situations arising from core melt accidents. These situations are divided to fast and slow loads. Fast loads include ex-vessel steam explosions, steam spikes, hydrogen burns, direct containment heating and missiles. Slow loads are connected with pressure rise inside the containment in case when the containment heat removal system is not functioning. First part of report describes the analyses of reactor cavity based on axi-symmetric load assumptions. These studies are performed with various models like one degree of freedom idealisation, axi-symmetric modelling of geometry and full three-dimensional modelling of geometry. Second part of report describes the analyses of cavity based on non-axi-symmetric load assumptions. Here full 3D- geometry model is used combined with various physical models for the behaviour of reinforced concrete. Third part of report gives short account of the analysis of containment ultimate pressure capacity. The containment model in this case includes pre-stressing tendons and mild steel reinforcing bars. The load is assumed to axi-symmetric internal static pressure. The capacity of the reactor cavity against the ex-vessel steam explosion scenarios for VVER-91 plant concept is established for both axi-symmetric and non-axi-symmetric load models using ANACAP structural analysis code. The validation of the cavity response to ex-vessel steam explosion load using different commercially available codes gave mixed results for both axisymmetric and non-axi-symmetric load presentations.The ultimate static overpressure capacity of the VVER-91 reactor cavity structure was established to be of the order of 10 MPa. This result

  15. United States Department of Energy's reactor core protection evaluation methodology for fires at RBMK and VVER nuclear power plants. Revision 1

    International Nuclear Information System (INIS)

    1997-06-01

    This document provides operators of Soviet-designed RBMK (graphite moderated light water boiling water reactor) and VVER (pressurized light water reactor) nuclear power plants with a systematic Methodology to qualitatively evaluate plant response to fires and to identify remedies to protect the reactor core from fire-initiated damage

  16. Informational system to assist decision making at spent nuclear fuel transportation from VVER-440, VVER-1000 and RBMK-1000 nuclear power plants

    International Nuclear Information System (INIS)

    Kuryndin, A.V.; Kirkin, A.M.; Stroganov, A.A.

    2012-01-01

    The developed informational system provides an automated estimations of nuclear and radiation safety parameters during spent nuclear fuel transportation from WWER-440 and WWER-1000 and RBMK-1000 nuclear power plants to the nuclear fuel cycle facilities, and allows us to determine the optimum cask loading from the dose rates distribution outside of protection point of view [ru

  17. High energy pipe line break postulations and their mitigation - examples for VVER nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Zdarek, J.; Pecinka, L.; Kadecka, P.; Dotrel, J. [Nuclear Res. Inst., Rez (Czech Republic)

    1998-11-01

    The concept and the proposals for the protection and reinforcement of equipment against the effects of postulated rupture of the high-energy piping, in VVER Plant, are presented. The most recent version of the US NRC Guidelines has been used. The development of the legislation, the basic approach and selection of criteria for the assessment of the rupture of high energy piping, provide the basis for the application of the separation concept in the overall safety philosophy. (orig.)

  18. High energy pipe line break postulations and their mitigation - examples for VVER nuclear power plants

    International Nuclear Information System (INIS)

    Zdarek, J.; Pecinka, L.; Kadecka, P.; Dotrel, J.

    1998-01-01

    The concept and the proposals for the protection and reinforcement of equipment against the effects of postulated rupture of the high-energy piping, in VVER Plant, are presented. The most recent version of the US NRC Guidelines has been used. The development of the legislation, the basic approach and selection of criteria for the assessment of the rupture of high energy piping, provide the basis for the application of the separation concept in the overall safety philosophy. (orig.)

  19. Almost twenty years' search of transuranium isotopes in effluents discharged to air from nuclear power plants with VVER reactors.

    Science.gov (United States)

    Hölgye, Z; Filgas, R

    2006-04-01

    Airborne effluents of 5 stacks (stacks 1-5) of three nuclear power plants, with 9 pressurized water reactors VVER of 4,520 MWe total power, were searched for transuranium isotopes in different time periods. The search started in 1985. The subject of this work is a presentation of discharge data for the period of 1998-2003 and a final evaluation. It was found that 238Pu, 239,240Pu, 241Am, 242Cm, and 244Cm can be present in airborne effluents. Transuranium isotope contents in most of the quarterly effluent samples from stacks 2, 4 and 5 were not measurable. Transuranium isotopes were present in the effluents from stack l during all 9 years of the study and from stack 3 since the 3rd quarter of 1996 as a result of a defect in the fuel cladding. A relatively high increase of transuranium isotopes in effluents from stack 3 occurred in the 3rd quarter of 1999, and a smaller increase occurred in the 3rd quarter of 2003. In each instance 242Cm prevailed in the transuranium isotope mixtures. 238Pu/239,240Pu, 241Am/239,240Pu, 242Cm/239,240Pu, and 244Cm/239,240Pu ratios in fuel for different burn-up were calculated, and comparison of these ratios in fuel and effluents was performed.

  20. Conducting water chemistry of the secondary coolant circuit of VVER-based nuclear power plant units constructed without using copper containing alloys

    Science.gov (United States)

    Tyapkov, V. F.

    2014-07-01

    The secondary coolant circuit water chemistry with metering amines began to be put in use in Russia in 2005, and all nuclear power plant units equipped with VVER-1000 reactors have been shifted to operate with this water chemistry for the past seven years. Owing to the use of water chemistry with metering amines, the amount of products from corrosion of structural materials entering into the volume of steam generators has been reduced, and the flow-accelerated corrosion rate of pipelines and equipment has been slowed down. The article presents data on conducting water chemistry in nuclear power plant units with VVER-1000 reactors for the secondary coolant system equipment made without using copper-containing alloys. Statistical data are presented on conducting ammonia-morpholine and ammonia-ethanolamine water chemistries in new-generation operating power units with VVER-1000 reactors with an increased level of pH. The values of cooling water leaks in turbine condensers the tube system of which is made of stainless steel or titanium alloy are given.

  1. Implementation of New Reactivity Measurement System and New Reactor Noise Analysis Equipment in a VVER-440 Nuclear Power Plant

    Science.gov (United States)

    Vegh, János; Kiss, Sándor; Lipcsei, Sándor; Horvath, Csaba; Pos, István; Kiss, Gábor

    2010-10-01

    The paper deals with two recently developed, high-precision nuclear measurement systems installed at the VVER-440 units of the Hungarian Paks NPP. Both developments were motivated by the reactor power increase to 108%, and by the planned plant service time extension. The first part describes the RMR start-up reactivity measurement system with advanced services. High-precision picoampere meters were installed at each reactor unit and measured ionization chamber current signals are handled by a portable computer providing data acquisition and online reactivity calculation service. Detailed offline evaluation and analysis of reactor start-up measurements can be performed on the portable unit, too. The second part of the paper describes a new reactor noise diagnostics system using state-of-the-art data acquisition hardware and signal processing methods. Details of the new reactor noise measurement evaluation software are also outlined. Noise diagnostics at Paks NPP is a standard tool for core anomaly detection and for long-term noise trend monitoring. Regular application of these systems is illustrated by real plant data, e.g., results of standard reactivity measurements during a reactor startup session are given. Noise applications are also illustrated by real plant measurements; results of core anomaly detection are presented.

  2. Modernization programme for nuclear power plant units with VVER-1000 in Ukraine

    International Nuclear Information System (INIS)

    Shenderovich, V.

    1997-01-01

    All Ukrainian nuclear power plants with WWER type reactors are briefly described from the safety point of view. Information is given on the design and construction of the units. The main goals of upgrading are: elimination of incompliances with current safety standards, improvement of the reliability of safety significant systems, equipment and elements, and implementation of IAEA recommendations. A list of actions making up the large upgrading programme is given; it includes 181 measures to be taken. At present the measures are being designed in order to find appropriate engineering solutions, to develop technical specifications for new equipment, and to ensure precise cost estimation. (M.D.)

  3. Analysis of core damage frequency: Nuclear power plant Dukovany, VVER/440 V-213 Unit 1, internal events. Volume 1: Main report

    International Nuclear Information System (INIS)

    Pugila, W.J.

    1994-01-01

    This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for the Dukovany VVER/440 V-213 nuclear power plant, Unit 1. Section 1.1 describes the objectives of this study. Section 1.2 discusses the approach that was used for completing the Dukovany PSA. Section 1.3 summarizes the results of the PSA. Section 1.4 provides a comparison of the results of the Dukovany PSA with the results of other PSAs for different types of reactors worldwide. Section 1.5 summarizes the conclusions of the Dukovany PSA

  4. Nuclear fuel for VVER reactors. Actual state and trends

    International Nuclear Information System (INIS)

    Molchanov, V.

    2011-01-01

    The main tasks concerning development of FA design, development and modernization of structural materials, improvement of technology of structural materials manufacturing and FA fabrication and development of methods and codes are discussed in this paper. The main features and expected benefit of implementation of second generation and third generation fuel assembly for VVER-440 Nuclear Fuel are given. A brief review of VVER-440 and VVER-1000 Nuclear Fuel development before 1997 since 2010 is shown. A summary of VVER-440 and VVER-1000 Nuclear Fuel Today, including details about TVSA-PLUS, TVSA-ALFA, TVSA-12 and NPP-2006 Phase 2 tasks (2010-2012) is presented. In conclusion, as a result of large scope of R and D performed by leading enterprises of nuclear industry modern nuclear fuel for VVER reactors is developed, implemented and successfully operated. Fuel performance (burnup, lifetime, fuel cycles, operating reliability, etc.) meets the level of world's producers of nuclear fuel for commercial reactors

  5. Application of a Russian nuclear reactor simulator VVER-1000

    International Nuclear Information System (INIS)

    Lopez-Peniche S, A.; Salazar S, E.

    2012-10-01

    The objective of the present work is to give to know the most important characteristics in the Russian nuclear reactor of pressurized light water VVER-1000, doing emphasis in the differences that has with the western equivalent the reactor PWR in the design and the safety systems. Therefore, a description of the computerized simulation of the reactor VVER-1000 developed by the company Eniko TSO that the International Atomic of Energy Agency distributes to the states members with academic purposes will take place. The simulator includes mathematical models that represent to the essential systems in the real nuclear power plant, for what is possible to reproduce common faults and transitory characteristic of the nuclear industry with a behavior sufficiently attached to the reality. In this work is analyzed the response of the system before a turbine shot. After the accident in the nuclear power plant of Three Mile Island (US) they have been carried out improvements in the design of the reactor PWR and their safety systems. To know the reach and the limitations of the program, the events that gave place to this accident will be reproduced in the simulator VVER-1000. With base to the results of the simulation we will conclude that so reliable is the response of the safety system of this reactor. (Author)

  6. Problems and prospects connected with development of high-temperature filtration technology at nuclear power plants equipped with VVER-1000 reactors

    Science.gov (United States)

    Shchelik, S. V.; Pavlov, A. S.

    2013-07-01

    Results of work on restoring the service properties of filtering material used in the high-temperature reactor coolant purification system of a VVER-1000 reactor are presented. A quantitative assessment is given to the effect from subjecting a high-temperature sorbent to backwashing operations carried out with the use of regular capacities available in the design process circuit in the first years of operation of Unit 3 at the Kalinin nuclear power plant. Approaches to optimizing this process are suggested. A conceptual idea about comprehensively solving the problem of achieving more efficient and safe operation of the high-temperature active water treatment system (AWT-1) on a nuclear power industry-wide scale is outlined.

  7. Refurbishing the reactor protection systems of VVER-440/230 and VVER-1000/320 nuclear power plants with exclusively digital IandC systems

    International Nuclear Information System (INIS)

    Martin, M.

    1997-01-01

    The refurbishment of reactor protection systems of nuclear power plants is based on two sets of requirements: engineering aspects such as performance, qualification and licensing, as well as interfaces to other systems; and cost-benefit relationships, ease of service and maintenance as well as installation during scheduled outages. A number of WWER-440 and WWER-1000 nuclear plants have announced their intention to refurbish their protection systems. Since 1994, these plants have been placing orders with Siemens for new protection systems, including the neutron flux monitoring system utilizing the advanced system TELEPERM XS. This exclusively digital IandC system provides an excellent foundation for the remaining plant service life

  8. Optimization of fuel core loading pattern design in a VVER nuclear power reactors using Particle Swarm Optimization (PSO)

    International Nuclear Information System (INIS)

    Babazadeh, Davood; Boroushaki, Mehrdad; Lucas, Caro

    2009-01-01

    The two main goals in core fuel loading pattern design optimization are maximizing the core effective multiplication factor (K eff ) in order to extract the maximum energy, and keeping the local power peaking factor (P q ) lower than a predetermined value to maintain fuel integrity. In this research, a new strategy based on Particle Swarm Optimization (PSO) algorithm has been developed to optimize the fuel core loading pattern in a typical VVER. The PSO algorithm presents a simple social model by inspiration from bird collective behavior in finding food. A modified version of PSO algorithm for discrete variables has been developed and implemented successfully for the multi-objective optimization of fuel loading pattern design with constraints of keeping P q lower than a predetermined value and maximizing K eff . This strategy has been accomplished using WIMSD and CITATION calculation codes. Simulation results show that this algorithm can help in the acquisition of a new pattern without contravention of the constraints.

  9. Application of a Russian nuclear reactor simulator VVER-1000; Aplicacion de un simulador de reactor nuclear ruso VVER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Lopez-Peniche S, A. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04360 Mexico D. F. (Mexico); Salazar S, E., E-mail: alpsordo@hotmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2012-10-15

    The objective of the present work is to give to know the most important characteristics in the Russian nuclear reactor of pressurized light water VVER-1000, doing emphasis in the differences that has with the western equivalent the reactor PWR in the design and the safety systems. Therefore, a description of the computerized simulation of the reactor VVER-1000 developed by the company Eniko TSO that the International Atomic of Energy Agency distributes to the states members with academic purposes will take place. The simulator includes mathematical models that represent to the essential systems in the real nuclear power plant, for what is possible to reproduce common faults and transitory characteristic of the nuclear industry with a behavior sufficiently attached to the reality. In this work is analyzed the response of the system before a turbine shot. After the accident in the nuclear power plant of Three Mile Island (US) they have been carried out improvements in the design of the reactor PWR and their safety systems. To know the reach and the limitations of the program, the events that gave place to this accident will be reproduced in the simulator VVER-1000. With base to the results of the simulation we will conclude that so reliable is the response of the safety system of this reactor. (Author)

  10. CORONA project -contribution to VVER nuclear education and training

    International Nuclear Information System (INIS)

    Ilieva, M.; Miteva, R.; Takov, T.

    2016-01-01

    CORONA Project is established to stimulate the transnational mobility and lifelong learning amongst VVER end users. The project aims to provide a special purpose structure for training of specialists and to maintain the nuclear expertise by gathering the existing and generating new knowledge in the VVER area. CORONA Project consists of two parts: CORONA I (2011-2014) ''Establishment of a regional center of competence for VVER technology and Nuclear Applications'', co-financed by the Framework Program 7 of the European Union (EU) and CORONA II (2015-2018) ''Enhancement of training capabilities in VVER technology through establishment of VVER training academy'', co-financed by HORIZON 2020, EURATOM 2014-2015. The selected form of the CORONA Academy, together with the online availability of the training opportunities will allow trainees from different locations to access the needed knowledge on demand. The project will target also new-comers in VVER community like Vietnam, Turkey, Belarus, etc. (authors)

  11. Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr Nuclear Power Plant on basket criticality

    International Nuclear Information System (INIS)

    Rezaeian, M.; Kamali, J.

    2017-01-01

    Dual-purpose casks can be utilized for dry interim storage and transportation of the highly radioactive spent fuel assemblies (SFAs) of Bushehr Nuclear Power Plant (NPP). Criticality safety analysis was carried out using the MCNP code for the cask containing 12, 18, or 19 SFAs. The basket materials of borated stainless steel and Boral (Al-B_4C) were investigated, and the minimum required receptacle pitch of the basket was determined. - Highlights: • Criticality safety analysis for a dual purpose cask was carried out. • The basket material of borated stainless steel and Boral were investigated. • Minimum receptacle pitch was determined for 12, 18, or 19 VVER 1000 spent fuel assemblies.

  12. Improving nuclear safety of VVER-440 units

    International Nuclear Information System (INIS)

    Nochev, T.; Sabinov, S.

    2001-01-01

    In this paper authors deals with improvement of nuclear safety of WWER-440 units in Kozloduy NPP. Main directions for improving nuclear safety of WWER-440 units were: - to expand number of the design accident; - to increase reliability of equipment important for the safety; - to decrease the probability of initiating events; - improvements the integrity of the primary circuit (application LBB concept, qualification of the pressure safety valves to avoid pressurized thermal shock); - improvement of the fire protection; - improvement of the operation including upgrading and improvement of operational documents, implementation of new system for training the operators and etc.; - reassessment of the seismic response of the plant. Main actions were made at NPP Kozloduy to increase nuclear safety of VVER-440 units. 1. Modernization of Emergency High Pressure Safety Injection System. The modernization includes dividing of independent channels with reservation of active elements. Pumps were exchanged with more effective and reliable ones. HPSIS was increased reliability in general through decrease number of active elements and exchanged with passive. 2. For the purpose of avoiding fast cooling at the primary circuit and obtaining thermal shock of reactor vessel, Main Safety Insulation Valves are installed at NPP Kozloduy. 3. Modernization of Emergency power supplies AC. Oil breakers VMP-10 are exchanged with gas FS-4. 4. Generator breakers are installed to decrease probability of loss power supply and blackout. They provide reliable power supply to the system important for the safety in case of failure on generator. 5. I and C system has been qualified and optimized. 6. Reassessments of Limiting Conditions of Operation and new scram signals have been introduced. 7. An operators-oriented Informational System has been developed. It includes ensuring and updating of equipment data, new informational support of operator and etc. 8. A new auxiliary independent system for

  13. Interactive nuclear plant analyzer for VVER-440 reactor

    International Nuclear Information System (INIS)

    Shier, W.; Horak, W.; Kennett, R.

    1992-05-01

    This document discusses an interactive nuclear plant analyzer (NPA) which has been developed for a VVER-440, Model 213 reactor for use in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis of various anticipated operational occurrences and accident scenarios. This NPA is operational on an IBM RISC-6000 workstation and utilizes the RELAP5/MOD2 computer code for the calculation of the VVER-440 reactor response to the interactive commands initiated by the NPA operator

  14. Simulation of a nuclear accident by an academic simulator of a VVER-1000 reactor; Simulacion de un accidente nuclear, mediante un simulador academico de un reactor VVER-1000

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez G, L. [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: laurahg42@gmail.com [UNAM, Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2014-10-15

    This work is planned to simulate a scenario in which the same conditions that caused the accident at the Fukushima Daichi nuclear power plant are present, using a simulator of a nuclear power plant with VVER-1000 reactor, a different type of technology to the NPP where the accident occurred, which used BWR reactors. The software where it will take place the simulation was created and distributed by the IAEA for academic purposes, which contains the essential systems that characterize this type of NPP. The simulator has tools for the analysis of the characteristic phenomena of a VVER-1000 reactor in the different systems together and planned training tasks. This makes possible to identify the function of each component and how connects to other systems, thus facilitating the visualization of possible failures and the consequences that they have on the general behavior of the reactor. To program the conditions in the simulator, is necessary to know and synthesize a series of events occurred in Fukushima in 2011 and the realized maneuvers to reduce the effects of the system failures. Being different technologies interpretation of the changes that would suffer the VVER systems in the scenario in question will be developed. The Fukushima accident was characterized by the power loss of regular supply and emergency of the cooling systems which resulted in an increase in reactor temperature and subsequent fusion of their nuclei. Is interesting to reproduce this type of failure in a VVER, and extrapolate the lack of power supply in the systems that comprise, as well as pumping systems for cooling, has a pressure regulating system which involves more variables in the balance of the system. (Author)

  15. Advanced designs of VVER reactor plant

    International Nuclear Information System (INIS)

    Mokhov, V.A.

    2010-01-01

    The history of VVER reactors, current challenges and approaches to the challenges are highlighted. The VVER-1200 reactor of 3+ generation for AES-2006 units are under construction at the Leningrad 2 nuclear power plant (LNPP-2). The main parameters are listed and details are presented of the vessel, steam generator, and improved fuel. The issue of the NPP safety is discussed. Additional topics include the MIR-1200 reactor unit, VVER-600, and VVER-SCP (Generation 4). (P.A.)

  16. Safety of VVER-440 reactors

    CERN Document Server

    Slugen, Vladimir

    2011-01-01

    Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety pri

  17. Interactive nuclear plant analyzer for the VVER-440 reactor

    International Nuclear Information System (INIS)

    Shier, W.; Kennett, R.

    1993-01-01

    An interactive nuclear plant analyzer (NPA) has been developed for a VVER-440 model 213 reactor for use in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis of various anticipated operational occurrences and accident scenarios. This NPA is operational on an IBM RISC-6000 workstation and utilizes the RELAP5/MOD2 computer code for the calculation of the VVER-440 reactor response to the interactive commands initiated by the NPA operator. Results of the interactive calculation can be through the user-defined, digital display of various plant parameters and through color changes that reflect changes in primary system fluid temperatures, fuel and clad temperatures, and the temperatures of other metal structures. In addition, changes in the status of various components and system can be initiated and/or displayed both numerically and graphically on the mask

  18. Simulation of a nuclear accident by an academic simulator of a VVER-1000 reactor

    International Nuclear Information System (INIS)

    Hernandez G, L.; Salazar S, E.

    2014-10-01

    This work is planned to simulate a scenario in which the same conditions that caused the accident at the Fukushima Daichi nuclear power plant are present, using a simulator of a nuclear power plant with VVER-1000 reactor, a different type of technology to the NPP where the accident occurred, which used BWR reactors. The software where it will take place the simulation was created and distributed by the IAEA for academic purposes, which contains the essential systems that characterize this type of NPP. The simulator has tools for the analysis of the characteristic phenomena of a VVER-1000 reactor in the different systems together and planned training tasks. This makes possible to identify the function of each component and how connects to other systems, thus facilitating the visualization of possible failures and the consequences that they have on the general behavior of the reactor. To program the conditions in the simulator, is necessary to know and synthesize a series of events occurred in Fukushima in 2011 and the realized maneuvers to reduce the effects of the system failures. Being different technologies interpretation of the changes that would suffer the VVER systems in the scenario in question will be developed. The Fukushima accident was characterized by the power loss of regular supply and emergency of the cooling systems which resulted in an increase in reactor temperature and subsequent fusion of their nuclei. Is interesting to reproduce this type of failure in a VVER, and extrapolate the lack of power supply in the systems that comprise, as well as pumping systems for cooling, has a pressure regulating system which involves more variables in the balance of the system. (Author)

  19. PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Gy. Ézsöl

    2012-01-01

    Full Text Available The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP. The facility was the first integral-type facility for VVERs. The PMK-2 was followed later by the PACTEL (for VVER-440, the ISB, and PSB for VVER-1000. Since the startup of the facility in 1985, 55 experiments have been performed primarily in international frameworks with the participation of experts from 29 European and overseas countries forming a scientific school to better understand VVER system behaviour and reach a high level of modelling of accident sequences. The ATHLET, CATHARE, and RELAP5 codes have been validated including both qualitative and quantitative assessments. The former was almost exclusively applied to the early phase of validation by integral experiments, while the quantitative assessments have been performed by the Fast Fourier Transform Based Method. Paper gives comprehensive information on the design features of PMK-2 facility with a special respect to the representativeness of phenomena, the experiments performed, and the results of the validation of ATHLET, CATHARE, and RELAP5 codes. Safety significance of the PMK-2 projects is also discussed.

  20. PMK-2, the First Integral Thermal-Hydraulics Tests for the Safety Evaluation of VVER-440/213 Nuclear Power Plants

    International Nuclear Information System (INIS)

    Ezsol, G.; Perneczky, L.; Szabados, L.; Toth, I.

    2012-01-01

    The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP. The facility was the first integral-type facility for VVERs. The PMK-2 was followed later by the PACTEL (for VVER-440), the ISB, and PSB for VVER-1000. Since the startup of the facility in 1985, 55 experiments have been performed primarily in international frameworks with the participation of experts from 29 European and overseas countries forming a scientific school to better understand VVER system behaviour and reach a high level of modelling of accident sequences. The ATHLET, CATHARE, and RELAP5 codes have been validated including both qualitative and quantitative assessments. The former was almost exclusively applied to the early phase of validation by integral experiments, while the quantitative assessments have been performed by the Fast Fourier Transform Based Method. Paper gives comprehensive information on the design features of PMK-2 facility with a special respect to the representativeness of phenomena, the experiments performed, and the results of the validation of ATHLET, CATHARE, and RELAP5 codes. Safety significance of the PMK-2 projects is also discussed

  1. Anchorage of equipment - requirements and verification methods with emphasis on equipment of existing and constructed VVER-type nuclear power plants

    International Nuclear Information System (INIS)

    Masopust, R.

    1999-01-01

    Criteria and verification methods which are recommended for use in the capacity evaluation of anchorage of safety-related equipment at WWER-type nuclear power plants are presented. Developed in compliance with the relevant basic standards documents specifically for anchorage of WWER-type equipment components, the criteria and methods cover different types of anchor bolts and other anchorage elements which are typical of existing, constructed, or reconstructed WWER-type nuclear power plants

  2. Erosion-corrosion entrainment of iron-containing compounds as a source of deposits in steam generators used at nuclear power plants equipped with VVER reactors

    Science.gov (United States)

    Tomarov, G. V.; Shipkov, A. A.

    2011-03-01

    The main stages and processes through which deposits are generated, migrate, and precipitate in the metal-secondary coolant system of power units at nuclear power plants are analyzed and determined. It is shown that substances produced by the mechanism of general erosion-corrosion are the main source of the ionic-colloid form of iron, which is the main component of deposits in a steam generator. Ways for controlling the formation of deposits in a nuclear power plant's steam generator are proposed together with methods for estimating their efficiency.

  3. Rolls-Royce successful modernization of safety-critical Instrumentation and Control (I and C) equipment at the Dukovany VVER 440/213 Nuclear Power Plant, based on SPINLINE 3 platform

    International Nuclear Information System (INIS)

    Rebreyend, P.; Burel, J.P.; Spoc, J.; Karasek, A.

    2010-01-01

    Rolls-Royce has provided on-time delivery of a substantial safety-critical I and C overhaul for four Nuclear reactors operated by Czech Republic utility, CEZ a.s. This nine-year project is considered to be one of the largest I and C modernization projects in the world. The Dukovany VVER 440 I and C modernization project and its key success factors are profiled in this paper. The project is in the final stages with the last unit to be completed in 2009. Beginning in September 2000, the project is in compliance with the initial schedule. Rolls-Royce has been designing and manufacturing I and C solutions dedicated to the implementation of safety and safety-related functions in nuclear power plants (NPPs) for more than 30 years. Though the early solutions were non-software-based, since 1984 software-based solutions for safety I and C functions have been deployed in operating NPPs across France and 15 other countries. The Rolls-Royce platform is suitable for implementation of safety I and C functions in new NPPs, as well as in the modernization of safety equipment in existing plants. CEZ a.s. is a major electricity supplier for the national grid. At Dukovany, CEZ a.s. operates four units of VVER-440/213-type reactors producing one quarter of CEZ a.s. electricity production. The first of these units was connected to the grid in 1985. Since the year 2000, the nine-year modernization program has been underway at Dukovany, at a cost of more than 200 million Euros. The equipment replacement was implemented during regular, planned outages of the original equipment and systems. After an international bidding phase, CEZ a.s. awarded a contract to Skoda JS for general engineering and project management. Individual subcontracts were then signed between Skoda JS and a consortium between Rolls-Royce and Areva for modernization of the safety systems, including the Reactor Protection System (RPS), the Reactor Control System (RCS), and the Post-Accident Monitoring System (PAMS). Two

  4. Overview of VVER water chemistry

    International Nuclear Information System (INIS)

    Ganesh, S.; Selvaraj, S.; Balasubramanian, M.R.; Selvavinayagam, P.; Sundar, R.S.

    2007-01-01

    Kudankulam Nuclear Power project is having twin units of 1000MWe of VVER type. This paper highlights the different analytical techniques that are followed to maintain the system chemistry within the technical specifications. This paper also briefs the different chemicals that are added to the systems and how they are monitored. Basic differences with respect to chemistry between a PHWR and VVER are also highlighted in this paper. (author)

  5. Status report: Nuclear fuel operating experience in implementing the program for power generation increase at VVER NPPs of JSC concern Rosenergoatom

    International Nuclear Information System (INIS)

    Ryabinin, Y.

    2015-01-01

    The power uprate program of operating WWER-1000 plants was performed by Rosenergoatom using FA-2M and FAA-PLUS for 18-month fuel cycles. Their operation was justified at 104% of the rated power, and extension to 18-month fuel cycles was carried out at WWER-1000 units (except for Kalinin NPP-1). The analysis of actual performance data confirmed the efficiency of the actions implemented, and issues addressed related to the introduction of new fuel type, extended fuel cycles and spent nuclear fuel storage and removal

  6. FP 6 EU - COVERS. Coordination action - VVER safety research

    International Nuclear Information System (INIS)

    Vasa, I.

    2008-01-01

    In this work research program of the European Union FP 6 - COVERS coordinated by the NRI Rez is presented. COVERS is designed to improve professional and communication environment in the specific area covering all aspects of safe and reliable operation of nuclear power plants with VVER-440 and VVER-1000 reactors. Project Consortium is composed of 26 research and development, engineering and technical support organisations of European VVER-operating and other EU and non-EU countries.

  7. Three-dimensional reactor dynamics code for VVER type nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kyrki-Rajamaeki, R. [VTT Energy, Espoo (Finland)

    1995-10-01

    A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.).

  8. Three-dimensional reactor dynamics code for VVER type nuclear reactors

    International Nuclear Information System (INIS)

    Kyrki-Rajamaeki, R.

    1995-10-01

    A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.)

  9. In-core nuclear fuel management optimization of VVER1000 using perturbation theory

    International Nuclear Information System (INIS)

    Hosseini, Mohammad; Vosoughi, Naser

    2011-01-01

    In-core nuclear fuel management is one of the most important concerns in the design of nuclear reactors. The two main goals in core fuel loading pattern design optimization are maximizing the core effective multiplication factor in order to extract the maximum energy, and keeping the local power peaking factor lower than a predetermined value to maintain fuel integrity. Because of the numerous possible patterns of the fuel assemblies in the reactor core, finding the best configuration is so important and complex. Different methods for optimization of fuel loading pattern in the core have been introduced so far. In this study, a software is programmed in C ⧣ language to find an order of the fuel loading pattern of the VVER-1000 reactor core using the perturbation theory. Our optimization method is based on minimizing the radial power peaking factor. The optimization process lunches by considering the initial loading pattern and the specifications of the fuel assemblies which are given as the input of the software. It shall be noticed that the designed algorithm is performed by just shuffling the fuel assemblies. The obtained results by employing the mentioned method on a typical reactor reveal that this method has a high precision in achieving a pattern with an allowable radial power peaking factor. (author)

  10. Evaluating the consequences of loss of flow accident for a typical VVER-1000 nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mirvakili, S.M.; Safaei, S. [Shiraz Univ., Shiraz (Iran, Islamic Republic of). Dept. of Nuclear Engineering, School of Mechanical Engineering; Faghihi, F. [Shiraz Univ., Shiraz (Iran, Islamic Republic of). Safety Research Center

    2010-07-01

    The loss of coolant flow in a nuclear reactor can result from a mechanical or electrical failure of the coolant pump. If the reactor is not tripped promptly, the immediate effect is a rapid increase in coolant temperature, decrease in minimum departure from nucleate boiling ratio (DNBR) and fuel damage. This study evaluated the shaft seizure of a reactor coolant pump in a VVER-1000 nuclear reactor. The locked rotor results in rapid reduction of flow through the affected reactor coolant loop and in turn leads to an increase in the primary coolant temperature and pressure. The analysis was conducted with regard for superimposing loss of power to the power plant at the initial accident moment. The required transient functions of flow, pressure and power were obtained using system transient calculations applied in COBRA-EN computer code in order to calculate the overall core thermal-hydraulic parameters such as temperature, critical heat flux and DNBR. The study showed that the critical period for the locked rotor accident is the first few seconds during which the maximum values of pressure and temperature are reached. 10 refs., 1 tab., 3 figs.

  11. Nuclear safety evaluation of the VVER 440, Type 213

    International Nuclear Information System (INIS)

    Urbancik, L.

    1997-01-01

    The supervisory activities of the State Office for Nuclear Safety at the Dukovany nuclear power plant are described. No event resulting in an inpermissible radioactivity leak into the environment occurred at the plant in 1996. From among the 76 failures and events having occurred, only 4 were classified as level 1 on the International Nuclear Event Scale. Changes in the technology of radioactive waste bituminization were proposed. The Interim Spent Fuel Storage Facility at the Dukovany site was in test operation in 1996. Selected physical parameters of this facility were monitored. Seven international transports of spent fuel were accomplished in 1996. The dose rates in the surroundings of the Dukovany plant are monitored constantly by a teledosimetric system operated by the nuclear power plant. Periodical sampling and radionuclide activity measurements in the environment are also performed. (M.D.)

  12. Operation of Nuclear Fuel Based on Reprocessed Uranium for VVER-type Reactors in Competitive Nuclear Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Troyanov, V.; Molchanov, V.; Tuzov, A. [TVEL Corporation, 49 Kashirskoe shosse, Moscow 115409 (Russian Federation); Semchenkov, Yu.; Lizorkin, M. [RRC ' Kurchatov Institute' (Russian Federation); Vasilchenko, I.; Lushin, V. [OKB ' Gidropress' (Russian Federation)

    2009-06-15

    Current nuclear fuel cycle of Russian nuclear power involves reprocessed low-enriched uranium in nuclear fuel production for some NPP units with VVER-type LWR. This paper discusses design and performance characteristics of commercial nuclear fuel based on natural and reprocessed uranium. It presents the review of results of commercial operation of nuclear fuel based on reprocessed uranium on Russian NPPs-unit No.2 of Kola NPP and unit No.2 of Kalinin NPP. The results of calculation and experimental validation of safe fuel operation including necessary isotope composition conformed to regulation requirements and results of pilot fuel operation are also considered. Meeting the customer requirements the possibility of high burn-up achieving was demonstrated. In addition the paper compares the characteristics of nuclear fuel cycles with maximum length based on reprocessed and natural uranium considering relevant 5% enrichment limitation and necessity of {sup 236}U compensation. The expedience of uranium-235 enrichment increasing over 5% is discussed with the aim to implement longer fuel cycles. (authors)

  13. VVER-1000 backfitting programs

    International Nuclear Information System (INIS)

    Zabka, H.; Milhem, J.L.

    1998-01-01

    Russia, Ukraine, and Bulgaria have nineteen nuclear generating units of the VVER-1000/V-320 (1000 MWe PWR) type in operation. Most of these plants were built in the eighties. Their design is based on Soviet standards of the seventies. In the early eighties and, in particular, after the Chernobyl accident, new safety principles and supplementary specific standards were introduced. However, they were taken into account only to a limited extent in the design and construction of the VVER-1000/V-320 plants. A number of nuclear power plants, whose construction was stopped after the political changes in the countries of the former USSR, now are to be completed with the financial assistance of the Commission of the European Union and other Western organizations, respectively. This Western support is dependent on the condition that these plants attain a level of engineered safeguards comparable to that of PWR plants currently in operation in Western Europe. (orig.) [de

  14. Burnup Estimation of Rhodium Self-Powered Neutron Detector Emitter in VVER Reactor Core Using Monte Carlo Simulations

    OpenAIRE

    Khrutchinsky, А. А.; Kuten, S. A.; Babichev, L. F.

    2011-01-01

    Estimation of burn-up in a rhodium-103 emitter of self-powered neutron detector in VVER-1000 reactor core has been performed using Monte Carlo simulations within approximation of a constant neutron flux.

  15. A new optimization method based on cellular automata for VVER-1000 nuclear reactor loading pattern

    International Nuclear Information System (INIS)

    Fadaei, Amir Hosein; Setayeshi, Saeed

    2009-01-01

    This paper presents a new and innovative optimization technique, which uses cellular automata for solving multi-objective optimization problems. Due to its ability in simulating the local information while taking neighboring effects into account, the cellular automata technique is a powerful tool for optimization. The fuel-loading pattern in nuclear reactor cores is a major optimization problem. Due to the immensity of the search space in fuel management optimization problems, finding the optimum solution requires a huge amount of calculations in the classical method. The cellular automata models, based on local information, can reduce the computations significantly. In this study, reducing the power peaking factor, while increasing the initial excess reactivity inside the reactor core of VVER-1000, which are two apparently contradictory objectives, are considered as the objective functions. The result is an optimum configuration, which is in agreement with the pattern proposed by the designer. In order to gain confidence in the reliability of this method, the aforementioned problem was also solved using neural network and simulated annealing, and the results and procedures were compared.

  16. Model of nuclear reactor type VVER-1000/V-320 built by computer code ATHLET-CD

    International Nuclear Information System (INIS)

    Georgiev, Yoto; Filipov, Kalin; Velev, Vladimir

    2014-01-01

    A model of nuclear reactor type VVER-1000 V-320 developed for computer code ATHLET-CD2.1A is presented. Validation of the has been made, in the analysis of the station blackout scenario with LOCA on fourth cold leg is shown. As the calculation has been completed, the results are checked through comparison with the results from the computer codes ATHLET-2.1A, ASTEC-2.1 and RELAP5mod3.2

  17. Top-Level Software for VVER-1000 In-core Monitoring System under Implementation of Expanded Nuclear Fuel Diversification Program in Ukraine

    International Nuclear Information System (INIS)

    Khalimonchuk, V.A.

    2015-01-01

    The paper considers the possibility and expediency of developing mathematical software for VVER-1000 ICMS in Ukraine. This mathematical software is among the most important conditions for implementation of the expanded nuclear fuel diversification program. The top-level software is to be developed based on SSTC own studies in the development of codes for power distribution recovery, which were successfully used previously for RBMK-1000 safety analysis

  18. Nuclear fuel for VVER reactors. Actual state and trends

    International Nuclear Information System (INIS)

    Molchanov, V.

    2009-01-01

    The implementation of 2nd generation of FA with the following performance characteristics: 1) Average FP failure factor during operation is less than 1x10 -6 ; 2) Fuel burn-up: up to 60 GWxd/tHM; 3) 5-year fuel cycle; 4) Unit thermal power uprate up to 110% N nom ; 5) Load Follow Mode (97,5±2,5% and 100-75-100% N nom ) is presented. A new generation of FA (TVSA and TVS-2) is developed, implemented and successfully operated at Russian, Ukrainian and Bulgarian NPPs providing: Safe and reliable operation cycle of 6 years; Assembly burn-up - up to 60 GWxd/tHM; Load Follow Mode. For satisfaction of customer needs regarding nuclear fuel performance the following development of FA design is under way: Power uprate up to 104% N nom and Fuel cycles length up to 18 months

  19. Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Carbajo, J.J.

    2005-05-27

    The purpose of this report is to quantify the differences between mixed oxide (MOX) and low-enriched uranium (LEU) fuels and to assess in reasonable detail the potential impacts of MOX fuel use in VVER-1000 nuclear power plants in Russia. This report is a generic tool to assist in the identification of plant modifications that may be required to accommodate receiving, storing, handling, irradiating, and disposing of MOX fuel in VVER-1000 reactors. The report is based on information from work performed by Russian and U.S. institutions. The report quantifies each issue, and the differences between LEU and MOX fuels are described as accurately as possible, given the current sources of data.

  20. System analysis of nuclear safety of VVER reactor with MOX fuel

    Energy Technology Data Exchange (ETDEWEB)

    Klimov, A.D.; Zharkov, V.P.; Suslov, I.R. [Russia, Moscow Malaya Krasnoselskaya St. (Russian Federation); Boyarinov, V.F.; Kevrolev, V.V.; Tchibinyaev, A.V.; Tsibulskiy, V.F. [RRC KI, Russia, Moscow (Russian Federation); Kochurov, B.P. [ITEP, Russia, Moscow (Russian Federation); Giovanni, B. [NFPSC, FRAMATOME (France)

    2005-07-01

    The report presents a short summary of the results achieved in the ISTC (International Science and Technology Center) project 'System analysis of nuclear safety of VVER reactor with MOX fuel' (April 2005). The studies within the project are of a systematic character and include the solutions of 15 tasks. The report gives an overview of the major blocks of these tasks: neutron transport equation solution; calculations of isotopic vectors, analysis of the impact of uncertainties on predicted reactor functionals. The calculation methods, the verification results and the corresponding codes are briefly described. (authors)

  1. Ukrainian Nuclear Society International Conference 'Modernization of the NPP with VVER reactor' (abstracts)

    International Nuclear Information System (INIS)

    Bar'yakhtar, V.G.

    1999-01-01

    Abstracts of the papers presented at International conference of the Ukrainian Nuclear Society 'Modernization of the NPP with VVER reactor'. The following problems are considered: improving the NPP's safety and reliability; reactor modernization, the lifetime prolongation; increasing of the reactor operating characteristics; methods of capacity factor increasing: refueling control, maintenance control; technical and economical aspects of NPP modernization; modernization of the automated control system of the fuel process at the NPP's; technical features and methods for the continued radiation and technology control at the NPP's; training, increasing the staff qualification and NPP modernization

  2. Shaping of the axial power density distribution in the core to minimize the vapor volume fraction at the outlet of the VVER-1200 fuel assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Savander, V. I.; Shumskiy, B. E., E-mail: borisshumskij@yandex.ru [National Research Nuclear University MEPhI (Russian Federation); Pinegin, A. A. [National Research Center Kurchatov Institute (Russian Federation)

    2016-12-15

    The possibility of decreasing the vapor fraction at the VVER-1200 fuel assembly outlet by shaping the axial power density field is considered. The power density field was shaped by axial redistribution of the concentration of the burnable gadolinium poison in the Gd-containing fuel rods. The mathematical modeling of the VVER-1200 core was performed using the NOSTRA computer code.

  3. Nuclear Power

    International Nuclear Information System (INIS)

    Douglas-Hamilton, J.; Home Robertson, J.; Beith, A.J.

    1987-01-01

    In this debate the Government's policy on nuclear power is discussed. Government policy is that nuclear power is the safest and cleanest way of generating electricity and is cheap. Other political parties who do not endorse a nuclear energy policy are considered not to be acting in the people's best interests. The debate ranged over the risks from nuclear power, the UK safety record, safety regulations, and the environmental effects of nuclear power. The Torness nuclear power plant was mentioned specifically. The energy policy of the opposition parties is strongly criticised. The debate lasted just over an hour and is reported verbatim. (UK)

  4. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2005-01-01

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  5. Study of long-term loss of all AC power supply sources for VVER-1000/V320 in connection with application of new engineering safety features for SAMG

    International Nuclear Information System (INIS)

    Borisov, Evgeni; Grigorov, Dobrin; Mancheva, Kaliopa

    2013-01-01

    Highlights: • In this study we presented analysis for a new SAMG approach. • The approach is applicable for all PWR reactors from 2nd generation. • We investigated two scenarios with total black out. • The RELAP/MOD 3.2 computer code is used in performing the analyses. - Abstract: This paper presents the results of analysis for application of a new Severe Accident Management Guideline (SAMG) approach which is specifically applied for VVER-1000/B320 reactor installations. In general, this innovative approach is fully applicable for all the pressurized water reactors from second generation. The purposes of the analysis for the new SAMG approach application are as follows: • To represent suggestions for new engineering safety features application for SAMG strategies. • To assess the applicability of the new engineering safety features and means for SAMG strategies in case of loss of all off-site power supply sources for VVER-1000/B320 reactor installations. • To represent important operator actions and to analyse the effectiveness of these actions for accidents management in compliance with the new approach. • The RELAP5/MOD3.3 computer code has been used in performing the analyses in a VVER-1000 Nuclear Power Plant (NPP) model. The input data deck for the analysis is optimized, verified and validated

  6. SCORPIO-VVER core monitoring and surveillance system with advanced capabilities

    International Nuclear Information System (INIS)

    Molnar, J.; Vocka, R.

    2010-01-01

    In this work authors present 12 years of operation experience of core monitoring and surveillance system with advanced capabilities on nuclear power plants on 6 unit of VVER-440 type of reactors at two different NPPs. The original version of the SCORPIO (Surveillance of reactor CORe by PIcture On-line display) system was developed for the western type of PWR reactors. The first version of the SCORPIO-VVER Core Monitoring System for Dukovany NPP (VVER-440 type of reactor, Czech Republic) was developed in 1998. For SCORPIO-VVER implementation at Bohunice NPP in Slovakia (2001) the system was enhanced with startup module KRITEX.

  7. Nuclear power

    International Nuclear Information System (INIS)

    Porter, Arthur.

    1980-01-01

    This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

  8. Nuclear power

    International Nuclear Information System (INIS)

    1987-01-01

    ''Nuclear Power'' describes how a reactor works and examines the different designs including Magnox, AGR, RBMK and PWR. It charts the growth of nuclear generation in the world and its contributions to world energy resources. (author)

  9. Nuclear power

    International Nuclear Information System (INIS)

    King, P.

    1990-01-01

    Written from the basis of neutrality, neither for nor against nuclear power this book considers whether there are special features of nuclear power which mean that its development should be either promoted or restrained by the State. The author makes it dear that there are no easy answers to the questions raised by the intervention of nuclear power but calls for openness in the nuclear decision making process. First, the need for energy is considered; most people agree that energy is the power to progress. Then the historicalzed background to the current position of nuclear power is given. Further chapters consider the fuel cycle, environmental impacts including carbon dioxide emission and the greenhouse effect, the costs, safety and risks and waste disposal. No conclusion either for or against nuclear power is made. The various shades of opinion are outlined and the arguments presented so that readers can come to their own conclusions. (UK)

  10. The Paks Nuclear Power Station

    International Nuclear Information System (INIS)

    Erdosi, N.; Szabo, L.

    1978-01-01

    As the first stage in the construction of the Paks Nuclear Power Station, two units of 440 MW(e) each will be built. They are operated with two coolant loops each. The reactor units are VVER 440 type water-moderated PWR type heterogeneous power reactors designed in the Soviet Union and manufactured in Czechoslovakia. Each unit operates two Soviet-made K-220-44 steam turbines and Hungarian-made generators of an effective output of 220 MW. The output of the transformer units - also of Hungarian made - is 270 MVA. The radiation protection system of the nuclear power station is described. Protection against system failures is accomplished by specially designed equipment and security measures especially within the primary circuit. Some data on the power station under construction are given. (R.P.)

  11. Nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The committee concludes that the nature of the proliferation problem is such that even stopping nuclear power completely could not stop proliferation completely. Countries can acquire nuclear weapons by means independent of commercial nuclear power. It is reasonable to suppose if a country is strongly motivated to acquire nuclear weapons, it will have them by 2010, or soon thereafter, no matter how nuclear power is managed in the meantime. Unilateral and international diplomatic measures to reduce the motivations that lead to proliferation should be high on the foreign policy agenda of the United States. A mimimum antiproliferation prescription for the management of nuclear power is to try to raise the political barriers against proliferation through misuse of nuclear power by strengthening the Non-Proliferation Treaty, and to seek to raise the technological barriers by placing fuel-cycle operations involving weapons-usable material under international control. Any such measures should be considered tactics to slow the spread of nuclear weapons and thus earn time for the exercise of statesmanship. The committee concludes the following about technical factors that should be considered in formulating nuclear policy: (1) rate of growth of electricity use is a primary factor; (2) growth of conventional nuclear power will be limited by producibility of domestic uranium sources; (3) greater contribution of nuclear power beyond 400 GWe past the year 2000 can only be supported by advanced reactor systems; and (4) several different breeder reactors could serve in principle as candidates for an indefinitely sustainable source of energy

  12. Nuclear power in the Ukraine: Problems and prospects

    International Nuclear Information System (INIS)

    Nigmatullin, N.R.

    1995-01-01

    Nuclear power production in the Ukraine started in 1977 with the startup of the first 1000-MW power-generating unit at the Chernobyl nuclear power plant. During the period from 1977 to 1989 sixteen power-generating units with a total electric capacity of 14,880 MW were put into operation at five nuclear power plants: ten VVER-1000, two VVER-440, and four RBMK-1000. As a result of the accident in 1986 in the fourth power-generating unit and the fire in 1991 in the second power-generating unit of the Chernobyl nuclear power plant, these units are no longer operating. Therefore the total installed nuclear power plant capacity is 12,880 MW. Moreover, the construction of three more power-generating units with VVER-1000 reactors is almost completed at three nuclear power plants - Zaporozh'e, Roven, and Khmel'nitsk. These units are not in operation because of the moratorium announced by the Supreme Council of Ukraine. In connection with the Council's decision, the Chernobyl nuclear power plant should have been shut down in 1993

  13. Results of VVER fuel rods tests in the MIR.M1 reactor under power cycling conditions

    International Nuclear Information System (INIS)

    Burukin, A.; Izhutov, A.; Ovchinnikov, V.; Kalygin, V.; Markov, D.; Pimenov, Y.; Novikov, V.; Medvedev, A.; Nesterov, B.

    2011-01-01

    The paper presents the main results of the 50 ... 60 MWd/kgU burnup VVER fuel rods tests performed in the MIR.M1 reactor loop facilities under power cycling. The non-destructive PIE results are presented as well. A series of experiments was performed, including overall measurement of fuel rod parameters test, in one of which 300 cycles were done. Irradiation under power cycling conditions and PIE of high-burnup VVER fuel rods showed the following: 1) all fuel rods claddings preserved their integrity under irradiation at linear heat rate (LHR) higher than the NPP operating one; 2) experimental data were obtained on the axial and radial cladding strain and fission gas release (FGR) from 50 ... 60 MWd/kgU burnup VVER-440 and VVER-1000 fuel rods as well as on the kinetics of the change in these parameters and fuel temperature under the power cycling; 3) non-destructive PIE results are in a satisfactory correlation with the data obtained by means of in-pile measurement gages during irradiation. (authors)

  14. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2003-01-01

    This chapter discuss on nuclear power and its advantages. The concept of nucleus fission, fusion, electric generation are discussed in this chapter. Nuclear power has big potential to become alternative energy to substitute current conventional energy from coal, oil and gas

  15. Nuclear power

    International Nuclear Information System (INIS)

    Bupp, I.C.

    1991-01-01

    Is a nuclear power renaissance likely to occur in the United States? This paper investigates the many driving forces that will determine the answer to that question. This analysis reveals some frequently overlooked truths about the current state of nuclear technology: An examination of the issues also produces some noteworthy insights concerning government regulations and related technologies. Public opinion will play a major role in the unfolding story of the nuclear power renaissance. Some observers are betting that psychological, sociological, and political considerations will hod sway over public attitudes. Others wager that economic and technical concerns will prevail. The implications for the nuclear power renaissance are striking

  16. Feasibility and usefulness of reconstructing obsolete power blocks of VVER-440 reactors

    International Nuclear Information System (INIS)

    Kirichenko, A.M.; Krushenik, S.D.; Sigal, M.V.; Kustov, V.P.

    1993-01-01

    At the present time, in Russia and in the East European countries there are atomic power stations with first-generation VVER-440 reactors built according to specification which no longer satisfy the more rigorous modern safety standards. Among these power stations are, in particular, the Novovoronezh and the Armenian Atomic Power Station and two blocks of the Kola Atomic Power Station. The search for technical solutions for modernizing these power blocks is complicated because two conditions which are hard to reconcile must be fulfilled: an acceptable safety level must be obtained and the rebuilding must be economically justifiable (particularly since the time of operation of a power block until its standard service life is over is short). Research work undertaken in the All-Union Scientific Research Institute of Atomic Power Stations has shown that one way of overcoming these difficulties may involve changing the operating conditions of the reactor assembly to a less demanding mode of operation. This solution implies an economically justified minimum of structural improvements, provides the required safety level, and prolongs the service life of the power block. The reduction of the thermal power, and consequently, the necessary transfer of a power block to another option

  17. Innovative instrumentation for VVERs based in non-invasive techniques

    International Nuclear Information System (INIS)

    Jeanneau, H.; Favennec, J.M.; Tournu, E.; Germain, J.L.

    2000-01-01

    Nuclear power plants such as VVERs can greatly benefit from innovative instrumentation to improve plant safety and efficiency. In recent years innovative instrumentation has been developed for PWRs with the aim of providing additional measurements of physical parameters on the primary and secondary circuits: the addition of new instrumentation is made possible by using non-invasive techniques such as ultrasonics and radiation detection. These innovations can be adapted for upgrading VVERs presently in operation and also in future VVERs. The following innovative instrumentation for the control, monitoring or testing at VVERs is described: 1. instrumentation for more accurate primary side direct measurements (for a better monitoring of the primary circuit); 2. instrumentation to monitor radioactivity leaks (for a safer plant); 3. instrumentation-related systems to improve the plant efficiency (for a cheaper kWh)

  18. Special features of embrittlement of welded joints in shells of VVER-type reactors

    International Nuclear Information System (INIS)

    Kasatkin, O.G.

    1999-01-01

    At present, the atomic power engineering of Russia and Ukraine is based on water-water energy reactors of the VVER-440 and VVER-1000 type, with the electric power of 440 and 1000 MW, respectively. The majority of the VVER-440 reactors are installed in Russia, and VVER-1000 reactors operate in Ukraine. The reactors' shell (RS) is produced from cylindrical shells and a dished end welded together by circular joints under a flux. The RS of the VVER-440 reactor is produced from 15Kh3MFA steel, and the VVER-1000 reactors are produced from 15Kh2NMFA steel. The shell of the VVER-1000 reactor has an internal austenite coating. The condition of the RS metal is determined mainly by the critical brittleness temperature T b at which the impact toughness of specimens with a sharp notch reaches 60 J/cm 2 . The energy reactors, working in western countries, are characterised by a service life of 40 years and discussion is being carried out to extend this lifetime to 60 years. The design service life of the domestic reactors varies from 30 (RS VVER-440) to 40 (RS VVER-1000) years. According to investigations, the service life of the shells of these reactors is restricted by the properties of welded joints which are characterised by higher susceptibility to embrittlement than that of the parent metal, especially due to a higher content in the weld of phosphorus (RS VVER-440) or nickel (RS VVER-1000). Therefore, some experts believe that the actual service life of the RS is shorter than the design life. The accurate evaluation of the service life of welded joints in the RS is very important for the safety of service and also in the economic aspects, because the unjustified decrease of the permissible service life and premature shutdown of units of the nuclear power station result in huge losses

  19. Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuel

    International Nuclear Information System (INIS)

    Ansarifar, G.R.; Ebrahimian, M.

    2016-01-01

    Highlights: • The change in neutronic parameters to the use of nanofluid as coolant is presented. • Nanoparticle deposition on fuel clad is investigated. • Radial and axial local power peaking factors are presented. • ZrO 2 and Al 2 O 3 have the lowest rate of K eff drop off. - Abstract: Nowadays, many efforts have been made to improve the efficiency of nuclear power plants. One of which is use of the dual cooled annular fuel which is an internally and externally cooled annular fuel with many advantages in heat transfer characteristics. Another is the use of nanoparticle/water (nanofluid) as coolant. In this paper, by combining these two methods, the change in neutronic parameters of the VVER-1000 nuclear reactor core with dual cooled annular fuel attributable to the use of nanoparticle/water (nanofluid) as coolant is presented. Optimization of type and volume fraction of nanoparticles in water that affect the safety enhancement of core primary parameters is intended in this study. Reactivity change, radial and axial local power peaking factors (LPPF), and the consequence of nanoparticle deposition on fuel clad are investigated. As a result of changing the effective multiplication factor and PPF calculations for six types of nanoparticles which have been studied extensively for their heat transfer properties including Alumina, Aluminum, Copper oxide, Copper, Titania, and Zirconia with different volume fractions, it can be concluded that at low concentration (0.03 volume fraction), Zirconia and Alumina are the optimum nanoparticles for normal operation. The maximum radial and axial PPF are found to be invariant to the type of nanofluid at low volume fractions. With an increase in nanoparticle deposition thickness on the outer and inner clad, a flux and K eff depression occurred and ZrO 2 and Al 2 O 3 have the lowest rate of drop off.

  20. Determination of power density in VVER-1000 Mock-Up in LR-0 reactor

    Directory of Open Access Journals (Sweden)

    Košál Michal

    2017-01-01

    Full Text Available The pin power density is an important quantity which has to be monitored during the reactor operation, for two main reasons. Firstly, it is part of the limits and conditions of safe operation and, secondly, it is source term in neutron transport calculations used for the adequate assessing of the state of core structures and pressure vessel material. It is often calculated using deterministic codes which may have problems with an adequate definition of boundary conditions in subcritical regions. This may lead to overestimation of real situation, and therefore the validation of the utility codes contributes not only to better fuel utilization, but also to more precise description of radiation situation in structural components of core. Current paper presents methods developed at LR-0 reactor, as well as selected results for pin power density measurement in peripheral regions of VVER-1000 mock-up. The presented data show that the results of a utility diffusion code at core boundary overestimate the measurement. This situation, however satisfactory safe, may lead to unduly conservative approach in the determination of radiation damage of core structures.

  1. Effectiveness of the neutron-shield nanocomposites for a dual-purpose cask of Bushehr's Water–Water Energetic Reactor (VVER 1000 nuclear-power-plant spent fuels

    Directory of Open Access Journals (Sweden)

    Mahdi Rezaeian

    2017-10-01

    Full Text Available In order to perform dry interim storage and transportation of the spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP code. The dose rate for the dual-purpose cask utilizing the recently developed materials of epoxy/clay/B4C and epoxy/clay/B4C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of epoxy/clay/B4C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.

  2. Nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Hodgson, P.

    1985-01-01

    The question 'Do we really need nuclear power' is tackled within the context of Christian beliefs. First, an estimate is made of the energy requirements in the future and whether it can be got in conventional ways. The dangers of all the ways of supplying energy (eg coal mining, oil and gas production) are considered scientifically. Also the cost of each source and its environmental effects are debated. The consequences of developing a new energy source, as well as the consequences of not developing it, are considered. Decisions must also take into account a belief about the ultimate purpose of life, the relation of men to each other and to nature. Each issue is raised and questions for discussion are posed. On the whole the book comes down in favour of nuclear power.

  3. Experience on KKNPP VVER 1000 MWe water chemistry

    International Nuclear Information System (INIS)

    Ganesh, S.; Selvaraj, S.; Balasubramanian, M.R.; Selvavinayagam, P.; Pillai, Suresh Kumar

    2015-01-01

    Kudankulam Nuclear Power Project consists of pressurized water reactor (VVER) 2 x 1000 MWe constructed in collaboration with Russian Federation at Kudankulam in Tirunelveli District, Tamilnadu. Unit - 1 attained criticality on July 13 th 2013 and the unit was synchronized to grid on 22 nd October 2013. This paper highlights experience gained on water chemistry regime for primary and secondary circuit. (author)

  4. Qualification of the nuclear reactor core model DYN3D coupled to the thermohydraulic system code ATHLET, applied as an advanced tool for accident analysis of VVER-type reactors. Final report

    International Nuclear Information System (INIS)

    Grundmann, U.; Kliem, S.; Krepper, E.; Mittag, S; Rohde, U.; Schaefer, F.; Seidel, A.

    1998-03-01

    The nuclear reactor core model DYN3D with 3D neutron kinetics has been coupled to the thermohydraulic system code ATHLET. In the report, activities on qualification of the coupled code complex ATHLET-DYN3D as a validated tool for the accident analysis of russian VVER type reactors are described. That includes: - Contributions to the validation of the single codes ATHLET and DYN3D by the analysis of experiments on natural circulation behaviour in thermohydraulic test facilities and solution of benchmark tasks on reactivity initiated transients, - the acquisition and evaluation of measurement data on transients in nuclear power plants, the validation of ATHLET-DYN3D by calculating an accident with delayed scram and a pump trip in VVER plants, - the complementary improvement of the code DYN3D by extension of the neutron physical data base, implementation of an improved coolant mixing model, consideration of decay heat release and xenon transients, - the analysis of steam leak scenarios for VVER-440 type reactors with failure of different safety systems, investigation of different model options. The analyses showed, that with realistic coolant mixing modelling in the downcomer and the lower plenum, recriticality of the scramed reactor due to overcooling can be reached. The application of the code complex ATHLET-DYN3D in Czech Republic, Bulgaria and the Ukraine has been started. Future work comprises the verification of ATHLET-DYN3D with a DYN3D version for the square fuel element geometry of western PWR. (orig.) [de

  5. French-Finnish colloquium on safety of French and Russian type nuclear power plants

    International Nuclear Information System (INIS)

    Lukka, M.; Jaervinen, M.; Minkkinen, P.; Ukkola, A.; Levomaeki, L.

    1994-01-01

    The French-Finnish Colloquium on Safety of French and Russian Type Nuclear Power Plants was held in June, 14th - 16th, 1994, in Lappeenranta, Finland. The main topics of the colloquium were: VVER and RBMK reactors; Industrial safety studies for VVER's in FRAMATOME; Structural safety analysis of Ignalina NPP; Thermalhydraulic system (BETHSY) and analytical experiments for French NPP; Test facilities simulating VVER plants during accidents; PACTEL - facility for VVER thermal hydraulics; High burn-up fuel and reactivity accidents; Overview of severe accident research at Nuclear Protection and Safety Institute of CEA; Research of severe accidents in Finland; Review of main activities concerning computer codes used for VVER thermal-hydraulic safety analysis in OKB Gidropress; CATHARE code; APROS computer code, new developments; TRIO and TOLBIAC computer codes; ESTET and N3S softwares; HEXTRAN - 3D reactor dynamics code for VVER accident analysis; An overview the boron dilution issue in PWRs; Boron mixing transients in a 900 MW PWR vessel for a reactor start-up operation; and Problem of boric acid dilution in IVO

  6. The influence of changes in the VVER-1000 fuel assembly shape during operation on the power density distribution

    Energy Technology Data Exchange (ETDEWEB)

    Shishkov, L. K., E-mail: Shishkov-LK@nrcki.ru; Gorodkov, S. S.; Mikailov, E. F.; Sukhino-Homenko, E. A.; Sumarokova, A. S., E-mail: Sumarokova-AS@nrcki.ru [National Research Center Kurchatov Institute (Russian Federation)

    2016-12-15

    A new approach to calculation of the coefficients of sensitivity of the fuel pin power to deviations in gap sizes between fuel assemblies of the VVER-1000 reactor during its operation is proposed. It is shown that the calculations by the MCU code should be performed for a full-size model of the core to take the interference of the gap influence into account. In order to reduce the conservatism of calculations, the coolant density and coolant temperature feedbacks should be taken into account, as well as the fuel burnup.

  7. NNSA / IAEA VVER reactor safety workshops. May 2002 - April 2003. Executive summary

    International Nuclear Information System (INIS)

    Evans, M.; Petri, M. C.

    2003-01-01

    Over the past year, the U.S. National Nuclear Security Administration (NNSA) has sponsored four workshops to compare the probabilistic risk assessments (PRAs) of Soviet-designed VVER power plants. The ''International Workshop on Safety of First-Generation VVER-440 Nuclear Power Plants'' was held on May 20-25, 2002, in Piestany, Slovakia. A short follow-on workshop was held in Bratislava, Slovakia, on November 5-6, 2002, to complete the work begun in May. Piestany was the location also for the ''International Workshop on Safety of Second-Generation VVER-440 Nuclear Power Plants'' (September 9-14, 2002) and the ''International Workshop on Safety of VVER-1000 Nuclear Power Plants'' (April 7-12, 2003). The four workshops were held in cooperation with the International Atomic Energy Agency (IAEA), the Nuclear Regulatory Authority of Slovakia (UJD), the Center for Nuclear Safety in Central and Eastern Europe (CENS), and Argonne National Laboratory (ANL). The objectives of the workshops were to identify the impact of the improvements on the core damage frequency; the contribution to the PRA results of different assumptions about events that can occur at the plants; and to understand, identify, and prioritize potential improvements in hardware and plant operation of VVER nuclear power plants. These objectives were achieved based on insights gained from recent PRAs completed by the plants and their technical support organizations. Nine first-generation VVER-440 plants (nominally of the VVER-440/230 design) are currently operating in Armenia, Bulgaria, Russia, and Slovakia. Sixteen VVER-440/213 plants are currently operating in the Czech Republic, Hungary, Russia, Slovakia, and Ukraine. Twenty-three VVER-1000 plants are currently operating in Bulgaria, the Czech Republic, Russia, and Ukraine. Eleven addition plants are in the advanced stages of construction in various parts of the world. The workshops reviewed the current configuration and safety status of each plant

  8. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    Vaughen, V.C.A.

    1983-01-01

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

  9. Nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

    Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

  10. Radiolysis of the VVER-1000 reactor coolant: An experimental study and mathematical modeling

    International Nuclear Information System (INIS)

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

    1995-01-01

    Variations in the composition of the coolant for the primary circuit of a VVER-1000 reactor of the Kalinin nuclear power plant upon transition from power-level operation to shutdown was studied experimentally. The data obtained were used for verification of the MORAVA-H2 program developed earlier for simulation of the coolant state in pressurized-water power reactors

  11. Nuclear power

    International Nuclear Information System (INIS)

    d'Easum, Lille.

    1976-03-01

    An environmentalist's criticism of nuclear energy is given, on a layman's level. Such subjects as conflict of interest in controlling bodies, low-level radiation, reactor safety, liability insurance, thermal pollution, economics, heavy water production, export of nuclear technology, and the history of the anti-nuclear movement are discussed in a sensationalistic tone. (E.C.B.)

  12. Nuclear power economic database

    International Nuclear Information System (INIS)

    Ding Xiaoming; Li Lin; Zhao Shiping

    1996-01-01

    Nuclear power economic database (NPEDB), based on ORACLE V6.0, consists of three parts, i.e., economic data base of nuclear power station, economic data base of nuclear fuel cycle and economic database of nuclear power planning and nuclear environment. Economic database of nuclear power station includes data of general economics, technique, capital cost and benefit, etc. Economic database of nuclear fuel cycle includes data of technique and nuclear fuel price. Economic database of nuclear power planning and nuclear environment includes data of energy history, forecast, energy balance, electric power and energy facilities

  13. Nuclear power in Asia

    Energy Technology Data Exchange (ETDEWEB)

    Hagen, Ronald E.

    1998-08-01

    Contains Executive Summary and Chapters on: Nuclear Energy in the Asian context; Types of nuclear power reactors used in Asia; A survey of nuclear power by country; The economics of nuclear power; Fuels, fuel cycles and reprocessing; Environmental issues and waste disposal; The weapons issues and nuclear power; Conclusions. (Author)

  14. Vver-1000 Mox core computational benchmark

    International Nuclear Information System (INIS)

    2006-01-01

    The NEA Nuclear Science Committee has established an Expert Group that deals with the status and trends of reactor physics, fuel performance and fuel cycle issues related to disposing of weapons-grade plutonium in mixed-oxide fuel. The objectives of the group are to provide NEA member countries with up-to-date information on, and to develop consensus regarding, core and fuel cycle issues associated with burning weapons-grade plutonium in thermal water reactors (PWR, BWR, VVER-1000, CANDU) and fast reactors (BN-600). These issues concern core physics, fuel performance and reliability, and the capability and flexibility of thermal water reactors and fast reactors to dispose of weapons-grade plutonium in standard fuel cycles. The activities of the NEA Expert Group on Reactor-based Plutonium Disposition are carried out in close co-operation (jointly, in most cases) with the NEA Working Party on Scientific Issues in Reactor Systems (WPRS). A prominent part of these activities include benchmark studies. At the time of preparation of this report, the following benchmarks were completed or in progress: VENUS-2 MOX Core Benchmarks: carried out jointly with the WPRS (formerly the WPPR) (completed); VVER-1000 LEU and MOX Benchmark (completed); KRITZ-2 Benchmarks: carried out jointly with the WPRS (formerly the WPPR) (completed); Hollow and Solid MOX Fuel Behaviour Benchmark (completed); PRIMO MOX Fuel Performance Benchmark (ongoing); VENUS-2 MOX-fuelled Reactor Dosimetry Calculation (ongoing); VVER-1000 In-core Self-powered Neutron Detector Calculational Benchmark (started); MOX Fuel Rod Behaviour in Fast Power Pulse Conditions (started); Benchmark on the VENUS Plutonium Recycling Experiments Configuration 7 (started). This report describes the detailed results of the benchmark investigating the physics of a whole VVER-1000 reactor core using two-thirds low-enriched uranium (LEU) and one-third MOX fuel. It contributes to the computer code certification process and to the

  15. Design and implementation of the control system for nuclear plant VVER-1000. Instrumentation (program technical complexes)

    International Nuclear Information System (INIS)

    Siora, A.; Tokarev, V.; Bakhmach, E.

    2004-01-01

    Program-technical complexes (PTC) are designed as control and protection systems in water-moderated atomic reactors, including emergency and preventive systems, automatic control, unloading, reactor capacity limitation and accelerated preventive protection systems. Utilization of programmable logic integrated circuits from world leading manufacturers makes the complexes simple in structure, compact, with low energy demands and mutually independent for key and supporting functions The results of PTC assessment and implementation in Ukraine are outlined. Opportunities for a future development of RADIJ company in the area of control and protection systems for VVER reactors are also discussed

  16. Water chemistry experiences with VVERs at Kudankulam

    International Nuclear Information System (INIS)

    Rout, D.; Upadhyaya, T.C.; Ravindranath; Selvinayagam, P.; Sundar, R.S.

    2015-01-01

    Kudankulam Nuclear Power Project - 1 and 2 (Kudankulam NPP - 1 and 2) are pressurised water cooled VVERs of 1000 MWe each. Kudankulam NPP Unit - 1 is presently on its first cycle of operation and Kudankulam NPP Unit - 2 is on the advanced stage of commissioning with the successful completion of hot run related Functional tests. Water Chemistry aspects during various phases of commissioning of Kudankulam NPP Unit - 1 such as Hot Run, Boric acid flushing, initial fuel Loading (IFL), First approach to Criticality (FAC) are discussed. The main objectives of the use of controlled primary water chemistry programme during the hot functional tests are reviewed. The importance of the relevant water chemistry parameters were ensured to have the quality of the passive layer formed on the primary coolant system surfaces. The operational experiences during the 1 st cycle of operation of primary water chemistry, radioactivity transport and build-up are presented. The operational experience of some VVER units in the field of the primary water chemistry, radioactivity transport and build-up are presented as a comparison to VVER at Kudankulam NPP. The effects of the initial passivated layer formed on metal surfaces during hot run, activated corrosion products levels in the primary coolant under controlled water chemistry regime and the contamination/radiation situation are discussed. This report also includes the water chemistry related issues of secondary water systems. (author)

  17. Nuclear power: 2006 world report - evaluation

    International Nuclear Information System (INIS)

    Anon.

    2007-01-01

    Last year, 2006, 437 nuclear power plants were available for power supply in 31 countries, 7 plants less than in 2005. One unit was commissioned for the first time, 8 nuclear power plants were decommissioned for good in 2006. At a cumulated gross power of 389,488 MWe and a cumulated net power of 370,441 MWe, respectively, worldwide nuclear generating capacity has reached a high level so far. Nine different reactor lines are operated in commercial plants: PWR, PWR-VVER, BWR, CANDU, D 2 O PWR, GCR, AGR, LWGR, and LMFBR. Light water reactors (PWR and BWR) continue to top the list with 358 plants. By the end of the year, 10 countries operated 29 nuclear power plants with an aggregate gross power of 25,367 MWe and an aggregate net power of 23,953 MWe, respectively. Of these, 21 are light water reactors, 5 are CANDU-type reactors, 2 are fast breeder and 1 a LWGR. 123 commercial reactors with an aggregate power in excess of 5 MWe have so far been decommissioned in 19 countries. Most of them are prototype plants of low power. About 70% of the nuclear power plants in operation, namely 304 plants, were commissioned in the eighties and nineties. The energy availability and operating availability factors of the nuclear power plants again reached peak levels: 82% for energy availability, and 83% for operating availability. The 4 nuclear power plants in Finland continue to be in the lead worldwide with a cumulated average operating capacity factor of 94%. (orig.)

  18. Nuclear power. 2008 world report - evaluation

    International Nuclear Information System (INIS)

    Anon.

    2010-01-01

    In 2008, 438 nuclear power plants were available for power supply in 31 countries, 1 plant less than in 2007. No unit was commissioned for the first time, 1 nuclear power plant was decommissioned for good in 2008. At a cumulated gross power of 392,597 MWe and a cumulated net power of 372,170 MWe, respectively, worldwide nuclear generating capacity has reached a high level. Nine different reactor lines are operated in commercial plants: PWR, PWR-VVER, BWR, CANDU, D2O PWR, GCR, AGR, LWGR, and LMFBR. Light water reactors (PWR and BWR) continue to top the list with 358 plants. By the end of 2008, in 14 countries 43 nuclear power plants with an aggregate gross power of 39,211 MWe and an aggregate net power of 36,953 MWe were under construction. Of these, 37 are light water reactors, 3 are CANDU-type reactors, 2 are fast breeder and 1 D2O-PWR. 124 commercial reactors with an aggregate power in excess of 5 MWe have so far been decommissioned in 19 countries. Most of them are prototype plants of low power. About 70% of the nuclear power plants in operation, namely 304 plants, were commissioned in the eighties and nineties. The energy availability and operating availability factors of the nuclear power plants reached good levels: 80.80% for operating availability and 80,00% for energy availability. The four nuclear power plants in Finland continuecontinue to be in the lead worldwide with a cumulated average operating capacity factor of 91,60%. (orig.)

  19. Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon

    Directory of Open Access Journals (Sweden)

    Soroush Heidari Sangestani

    2018-01-01

    Full Text Available This article aims to simulate the sudden and fast pressure drop of VVER-1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations should be solved concurrently by means of DRAGON 4 and DONJON 4 coupling codes. The results of the developed package are compared with WIMS/CITATION and final safety analysis report of Bushehr VVER-1000 reactor (FSAR. Afterwards, time dependent thermal-hydraulic equations are answered by employing Single Heated Channel by Sectionalized Compressible Fluid method. Then, the obtained results were validated by the same transient simulation in a pressurized water reactor core. Then, thermal-hydraulic and neutronic modules are coupled concurrently by use of producing group constants regarding the thermal feedback effect. Results were compared to the mentioned transient simulation in RELAP5 computer code, which show that mass flux drop is sensed at the end of channel in several milliseconds which causes heat flux drop too. The thermal feedback resulted in production of some perturbations in the changes of these parameters. The achieved results for this very fast pressure drop represent accurate calculations of thermoneutronic parameters fast changes.

  20. Analysis of VVER-1000 large and small break LOCA experiments with RELAP5/MOD3.2

    International Nuclear Information System (INIS)

    Rychkov, M.; Chikkanagoudar, U.; Sehgal, B.R.

    2004-01-01

    A RELAP5 model for the analysis of the PSB-VVER test facility was developed by EREC in Russia. The PSB-VVER is a large-scale integral test facility to model the VVER-1000 type NPP. The volume and power scale in this test facility is 1:300 and the elevation scale is 1:1, which corresponds to the elevation mark of the reactor prototype. At the Division of Nuclear Safety, we have modified the PSB-VVER facility's RELAP5 model in order to analyze two of the transient tests performed on the PSB-VVER facility, which serve as the validation matrix described by NEA/CSNI. The objective of the work conducted was to validate the results obtained from RELAP5's calculation with the supplied experimental data from the PSB-VVER test facility. Two accident scenarios have been calculated and analyzed. After being verified against the '11% UP LOCA' test data, the RELAP5/MOD3.2 model was used for a so-called 'blind' transient calculation of the test '2*25% HL LOCA' and the results obtained were compared with the experimental data provided after the calculation. From the results of the qualitative and quantitative comparison of the 2 test calculations and the experimental data, we can state that the RELAP5/MOD3.2 code gives a satisfactory modeling of the PSB-VVER facility' thermal hydraulic phenomena

  1. Control of selected VVER components life time SKODA JS a.s. experience

    International Nuclear Information System (INIS)

    Zdebor, J.; Pribulla, E.

    2005-01-01

    Experience from the operation of nuclear power plants with type VVER reactors has shown that the life time management of a number of nuclear reactor components is technically as well as with respect to safety substantiated even at the time which exceeds their originally designed life time. To accept such solution it was necessary to develop and implement a number of programs based on which it was possible to evaluate the actual condition of monitored equipment. It is a condition allowing to adopt solution concerning the possibility of their further operation. Experience from the manufacture of 21 sets of reactor equipment for VVER 440 and 3 sets VVER 1000 has been gathered in SKODA JS a.s. which have been completed by experience from service activities performed at operated nuclear power plants. Analyses of manufacturing data and in-service inspection results completed by a lot of laboratory tests have become the basis for the development of selected VVER components life time management programs. The paper focuses on the life time management of those VVER components which SKODA JS a.s. has most experience with. (authors)

  2. Nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    The Single Channel Trip System for the Dungeness B AGRs in the United Kingdom has enabled Nuclear Electric to enhance the performance of each of the twin reactors progressively towards the design figure of 660MW. The unique self-testing dynamic nature of the microprocessor-based ISAT system was one of the key factors in satisfying the UK Regulator that the system met the demanding requirements of the Dungeness B application, and current operational and maintenance experience is very encouraging. Systems based on the ISAT principle have application in reactor protection systems throughout the world. (Author)

  3. Technology of repair of selected equipment in the power plant type VVER 440

    Energy Technology Data Exchange (ETDEWEB)

    Barborka, J.; Magula, V. [Welding Research Inst. (WRI), Bratislava (Slovakia)

    1998-11-01

    This article is divided in two parts: The first part is studying the effect of individual parameters by the usual and pulsed welding of 15CH2MFA steel. It can be concluded that by use of mechanized or automatic TIG process in PC position with addition of a cold wire with high nickel content the desired quality of repair welded joints of a pressure vessel of VVER 440 reactor can be achieved. Based on the results of the second laboratory study of the renovation technology applied for the rotary surfaces of pressure-tight cover and spindle of the main closing armature type DN 500 it can be concluded, that the developed technology for surfacing the sealing surfaces by TIG process with addition of a high-nickel cold wire the functional capability of the mentioned parts can be fully restored.

  4. Technology of repair of selected equipment in the power plant type VVER 440

    International Nuclear Information System (INIS)

    Barborka, J.; Magula, V.

    1998-01-01

    This article is divided in two parts: The first part is studying the effect of individual parameters by the usual and pulsed welding of 15CH2MFA steel. It can be concluded that by use of mechanized or automatic TIG process in PC position with addition of a cold wire with high nickel content the desired quality of repair welded joints of a pressure vessel of VVER 440 reactor can be achieved. Based on the results of the second laboratory study of the renovation technology applied for the rotary surfaces of pressure-tight cover and spindle of the main closing armature type DN 500 it can be concluded, that the developed technology for surfacing the sealing surfaces by TIG process with addition of a high-nickel cold wire the functional capability of the mentioned parts can be fully restored

  5. Nuclear power in Canada

    International Nuclear Information System (INIS)

    1980-01-01

    The Canadian Nuclear Association believes that the CANDU nuclear power generation system can play a major role in achieving energy self-sufficiency in Canada. The benefits of nuclear power, factors affecting projections of electric power demand, risks and benefits relative to other conventional and non-conventional energy sources, power economics, and uranium supply are discussed from a Canadian perspective. (LL)

  6. Investigation of station blackout scenario in VVER440/v230 with RELAP5 computer code

    Energy Technology Data Exchange (ETDEWEB)

    Gencheva, Rositsa Veselinova, E-mail: roseh@mail.bg; Stefanova, Antoaneta Emilova, E-mail: antoanet@inrne.bas.bg; Groudev, Pavlin Petkov, E-mail: pavlinpg@inrne.bas.bg

    2015-12-15

    Highlights: • We have modeled SBO in VVER440. • RELAP5/MOD3 computer code has been used. • Base case calculation has been done. • Fail case calculation has been done. • Operator and alternative operator actions have been investigated. - Abstract: During the development of symptom-based emergency operating procedures (SB-EOPs) for VVER440/v230 units at Kozloduy Nuclear Power Plant (NPP) a number of analyses have been performed using the RELAP5/MOD3 (Carlson et al., 1990). Some of them investigate the response of VVER440/v230 during the station blackout (SBO). The main purpose of the analyses presented in this paper is to identify the behavior of important VVER440 parameters in case of total station blackout. The RELAP5/MOD3 has been used to simulate the SBO in VVER440 NPP model (Fletcher and Schultz, 1995). This model was developed at the Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences (INRNE-BAS), Sofia, for analyses of operational occurrences, abnormal events and design based scenarios. The model provides a significant analytical capability for specialists working in the field of NPP safety.

  7. Primary water chemistry for NPP with VVER-TOI

    International Nuclear Information System (INIS)

    Susakin, S.N.; Brykov, S.I.; Zadonsky, N.V.; Bystrova, O.S.

    2012-09-01

    Nowadays within the framework of development of the nuclear power industry in Russia the VVER-TOI reactor is under designing (Standard optimized design). The given design provides for improvement of operation safety level, of technical-economic, operational and load-follow characteristics, and for the raise of competitive capacity of reactor plant and NPP as a whole. In VVER-TOI reactor plant design the primary water chemistry has been improved considering operation experience of VVER reactor plants and a possibility of RP operation under load-follow modes from the viewpoint of meeting the following requirements: - suppression of generation of oxidizing radiolytic products under power operation; - assurance of corrosion resistance of structural materials of equipment and pipelines throughout the NPP design service life; - minimization of deposits on surfaces of the reactor core fuel rods and on heat exchange surface of steam generators; - minimization of accumulation of activated corrosion products; - minimization of the amount of radioactive processing waste. In meeting these requirements an important role is devoted to suppression of generation of oxidizing radiolytic products owing to accumulation of hydrogen in the primary coolant. At NPP with VVER-1000 reactor the ammonia-potassium water chemistry is used wherein the hydrogen accumulation is provided at the expense of ammonia proportioning. Usage of ammonia leads to generation of additional amount of radioactive processing waste and to increased irregularity of maintaining the water chemistry under the daily load-follow modes. In VVER TOI design the primary water chemistry is improved by replacing the proportioning of ammonia with the proportioning of gaseous hydrogen. Different process schemes were considered that provide for a possibility of hydrogen accumulation and maintaining owing to direct proportioning of gaseous hydrogen. The obtained results showed that transition to the potassium water chemistry

  8. Power program and nuclear power

    International Nuclear Information System (INIS)

    Chernilin, Yu.F.

    1990-01-01

    Main points of the USSR power program and the role of nuclear power in fuel and power complex of the country are considered. Data on dynamics of economic indices of electric power generation at nuclear power plants during 1980-1988 and forecasts till 2000 are presented. It is shown that real cost of 1 kW/h of electric power is equal to 1.3-1.8 cop., and total reduced cost is equal to 1.8-2.4 cop

  9. Nuclear power of Korea

    International Nuclear Information System (INIS)

    Chun Bee-Ho

    2011-01-01

    National nuclear is presented. Nuclear energy safety after Fukushima, international cooperation in nuclear energy is discussed. Nuclear projects with the United Arab Emirates have been developed to build 4 nuclear power plants in the UAE - APR 1400. At the Korea-Bulgaria Industrial Committee Meeting in Sofia (March 2011) Korean side proposed Nuclear Safety Training Program in Korea for Bulgarian government officials and experts transfer of know-how and profound expertise on world-class nuclear technology and nuclear safety

  10. China and nuclear power

    International Nuclear Information System (INIS)

    Fouquoire-Brillet, E.

    1999-01-01

    This book presents the history of nuclear power development in China from the first research works started in the 1950's for the manufacturing of nuclear weapons to the recent development of nuclear power plants. This study tries to answer the main questions raised by the attitude of China with respect to the civil and military nuclear programs. (J.S.)

  11. Nuclear power revisited

    International Nuclear Information System (INIS)

    Grear, B.

    2008-01-01

    Modern development of nuclear power technology and the established framework of international agreements and conventions are responding to the major political, economic and environmental issues - high capital costs, the risks posed by nuclear wastes and accidents, and the proliferation of nuclear weaponry - that until recently hindered the expansion of nuclear power.

  12. Test facility of the VVER-440 condensation-type pressure suppression system

    International Nuclear Information System (INIS)

    Wolff, H.; Arndt, S.

    2004-01-01

    Since the early nineties, GRS has supported regulatory authorities in Central and Eastern Europe in performing safety assessments of nuclear power plants. Especially studies of the condensation-type pressure suppression system of VVER-440/V-213-type plants have been important in this respect. Major steps in demonstrating complete functioning of the condensation-type pressure suppression system under accident conditions by experiments run in the Russian large scale test facility, BC V-213, have been completed in the past two years within the framework of various international experimental programs. The test results were used to validate specifically for power plants with VVER-400/V-213 reactors the COCOSYS GRS computer code, which is used in the safety assessments. The results of recalculations of the C02 EREC test, which simulates a break of a main steam pipe, demonstrate the present state of validation of COCOSYS for VVER condensation-type pressure suppression systems. (orig.) [de

  13. Nuclear power in perspective

    International Nuclear Information System (INIS)

    Addinall, E.; Ellington, H.

    1982-01-01

    The subject is covered in chapters: (the nature of nuclear power) the atomic nucleus - a potential source of energy; how nuclear reactors work; the nuclear fuel cycle; radioactivity - its nature and biological effects; (why we need nuclear power) use of energy in the non-communist world -the changing pattern since 1950; use of energy - possible future scenarios; how our future energy needs might be met; (a possible long term nuclear strategy) the history of nuclear power; a possible nuclear power strategy for the Western World; (social and environmental considerations) the hazards to workers in the nuclear power industry; the hazards to the general public (nuclear power industry; reactor operation; transport of radioactive materials; fuel reprocessing; radioactive waste disposal; genetic hazards); the threat to democratic freedom and world peace. (U.K.)

  14. Safety classification of items in Tianwan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sun Yongbin

    2005-01-01

    The principle of integrality, moderation and equilibrium should be considered in the safety classification of items in nuclear power plant. The basic ways for safety classification of items is to classify the safety function based on the effect of the outside enclosure damage of the items (parts) on the safety. Tianwan Nuclear Power Plant adopts Russian VVER-1000/428 type reactor, it safety classification mainly refers to Russian Guidelines and standards. The safety classification of the electric equipment refers to IEEE-308(80) standard, including 1E and Non 1E classification. The safety classification of the instrumentation and control equipment refers to GB/T 15474-1995 standard, including safety 1E, safety-related SR and NC non-safety classification. The safety classification of Tianwan Nuclear Power Plant has to be approved by NNSA and satisfy Chinese Nuclear Safety Guidelines. (authors)

  15. Nuclear power and Imatran Voima in the future

    International Nuclear Information System (INIS)

    Numminen, K.

    1995-01-01

    As the owner of the Loviisa NPS with two VVER-440 units, Imatran Voima (IVO) has worked with nuclear power for more than twenty years. After the negative decision of the Finnish Parliament in 1993 there are no possibilities to build nuclear power in Finland in the near future. However, the preparation work for increasing the produced power of all four operating NPP's of Finland is going on. The emphasis in the work with new nuclear energy is on the supporting programs in Eastern Europe and the preparation of a building contract of a new NPS to China together with the Russians. With a new decision of the Finnish Parliament, the nuclear option could still be an important part of the future energy strategy of Finland. (orig.)

  16. The safety of nuclear power plants in Eastern Europe

    International Nuclear Information System (INIS)

    Hoehn, J.; Niehaus, F.

    1997-01-01

    Nuclear power plant operators and nuclear organizations from the West and from the East cooperate at many levels. The G7 and G24 nations have taken it upon themselves to improve the safety of Eastern nuclear power plants. The European Union has launched support programs, i.e. Technical Assistance to the Commonwealth of Independent States (Tacis) and Pologne-Hangrie: Aide a la Reconstruction Economique (Phare), and founded the European Bank for Reconstruction and Development. The countries of Central and Eastern Europe operate nuclear power plants equipped with VVER-type pressurized water reactors and those equipped with RBMK-type reactors. The safety of these two types of plants is judged very differently. Among the VVER plants, a distinction is made between the older and the more recent 440 MWe lines and the 1000 MWe line. Especially the RBMK plants (Chernobyl-type plants) differ greatly as a function of location and year of construction. Even though they do not meet Western safety standards and at best can be backfitted up to a certain level, it must yet be assumed that they will remain in operation to the end of their projected service lives for economic reasons. (orig.) [de

  17. Simulation of VVER MCCI reactor test case with ASTEC V2/MEDICIS computer code

    International Nuclear Information System (INIS)

    Stefanova, A.; Grudev, P.; Gencheva, R.

    2011-01-01

    This paper presents an application of the ASTEC v2, module MEDICIS for simulation of VVER Molten core concrete interaction test (MCCI) case without water injection. The main purpose of performed calculation is verification and improvement of module MEDICIS/ASTECv2 for better simulation of core concrete interaction processes. The VVER-1000 reference nuclear power plant was chosen as SARNET2 benchmark MCCI test-case. The initial conditions for MCCI test are taken after SBO scenario calculated with ASTEC version 1.3R2 by INRNE. (authors)

  18. SCORPIO-VVER core monitoring and surveillance system with advanced capabilities

    International Nuclear Information System (INIS)

    Molnar, J.; Vocka, R.

    2009-01-01

    The SCORPIO-VVER system includes following features: 1) Validation of plant measurements and identification of sensor failures. 2) Optimum combination of measurements and calculations to obtain precise values of important parameters. 3) On-line 3D power distribution calculation with pin power reconstruction. 4) Limit checking and thermal margin calculation allowing for surveillance of VVER core limits such as DNBR, Sub-cooling margin, FdH and FQ peeking factors. 5) Integrated modules for monitoring fuel performance and coolant activity for identification of fuel failures. 6) Predictive capabilities and strategy planning, offering the possibility to check the consequences of operational manoeuvres in advance, prediction of critical parameters, etc. 7) Convenient monitoring of approach to criticality during reactor start-up. 8) Automated transition between cycles (fuel reload). The SCORPIO-VVER core monitoring system with its flexible and modular framework successfully responses to the plant operating needs and advances in nuclear fuel cycle strategies and fuel design. Modular framework allows for easy modifications of the system and implementation of new methods in physical modules. Even if the system is installed only on VVER-440 reactors, it could be adapted for VVER-1000 needs

  19. Analysis of emergency operating procedures effectiveness for core damage prevention using computer code RELAP for nuclear power plants with VVER-1000/B-320 in reference to primary to secondary circuit leak with external power loss and BRU-A stuck open failure

    International Nuclear Information System (INIS)

    Arkhangelski, L.; Sheveliov, D. V.

    1999-01-01

    This report presents analysis of development emergency operating procedures effectiveness for possible accident on nuclear power plant with WWER-1000 reactor type. Accident initiating event is the primary to secondary circuit leak caused by steam generator primary cover lift-up. In according to conservative assumptions the following additional failures were considered: dump valve BRU-A stuck open failure; loss of external power. The results of this work are represented as a comparative analysis of two possible ways of accident evolution: according to functioning automatic safety systems responses; according to accident management based on development emergency operating procedures with operator intervention. Developed emergency operating procedures assure the following significant goals to mitigate accident sequences: optimal use of ECCS water inventory; severe core damage prevention; mitigation of environment radioactive contamination. (authors)

  20. Nuclear power prospects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-09-15

    A survey of the nuclear power needs of the less-developed countries and a study of the technology and economics of small and medium scale power reactors are envisioned by the General Conference. Agency makes its services available to Member States to assist them for their future nuclear power plans, and in particular in studying the technical and economic aspects of their power programs. The Agency also undertakes general studies on the economics of nuclear power, including the collection and analysis of cost data, in order to assist Member States in comparing and forecasting nuclear power costs in relation to their specific situations

  1. Dictionary of nuclear power

    International Nuclear Information System (INIS)

    Koelzer, W.

    2012-06-01

    The actualized version (June 2012) of the dictionary on nuclear power includes all actualizations and new inputs since the last version of 2001. The original publication dates from 1980. The dictionary includes definitions, terms, measuring units and helpful information on the actual knowledge concerning nuclear power, nuclear fuel cycle, nuclear facilities, radioactive waste management, nuclear physics, reactor physics, isotope production, biological radiation effects, and radiation protection.

  2. Dictionary of nuclear power

    International Nuclear Information System (INIS)

    Koelzer, W.

    2012-04-01

    The actualized version (April 2012) of the dictionary on nuclear power includes all actualizations and new inputs since the last version of 2001. The original publication dates from 1980. The dictionary includes definitions, terms, measuring units and helpful information on the actual knowledge concerning nuclear power, nuclear facilities, and radiation protection.

  3. Nuclear power status 1999

    International Nuclear Information System (INIS)

    2000-01-01

    The document gives statistical information on nuclear power plants status in the world in 1999, including the number of reactors in operation or under construction, the electricity supplied by nuclear power reactors and the respective percentage of electricity produced by nuclear energy in 1999, and the total operating experience to 31 December 1999, by country

  4. Severe accident management development program for VVER-1000 and VVER-440/213 based on the westinghouse owners group approach

    International Nuclear Information System (INIS)

    Felix, E.; Dessars, N.

    2003-01-01

    The development of the Westinghouse Owners Group Severe Accident Management Guidelines (WOG SAMG) between 1991 and 1994 was initiated in response to the U.S. Nuclear Regulatory Commission (NRC) requirement for addressing the regulatory severe accident concerns. Hence, the WOG SAMG is designed to interface with other existing procedures at the plant and is used in accident sequences that have progressed to the point where these other procedures are not applicable any longer, i.e. following core damage. The primary purpose of the WOG SAMG is to reach a controlled stable state, which can be declared when fission product releases are controlled, challenges to the confinement fission product boundary have been mitigated, and adequate heat removal is provided to the core and the containment. Although the WOG SAMG is a generic severe accident management guidance developed for use by the entirety of the operating Westinghouse PWR plants, provisions have been made in their development to address specific features of individual plants such as confinement type and the feasibility of reactor cavity flooding. Similarly, the generic SAMG does not address unique plant features and equipment, but rather allows for consideration of plant specific features and strategies. This adaptable approach has led to several SAMG development programs for VVER-1000 and VVER-440 type of power plants, under Westinghouse' s lead. The first of these programs carried out to completion was for Temelin NPP - VVER-1000 - in the first quarter of 2003. Other ongoing programs aim at providing a similar work for VVER-440 design, namely Dukovany, Mochovce and Bohunice NPPs. The challenge of adapting the existing generic WOG material to plants other than PWRs mainly arises for VVER-440 because of important differences in confinement design, making it more vulnerable to ex-vessel phenomena such as hydrogen burn. Also, for both eastern designs, cavity flooding strategy requires special consideration and

  5. Safety improvements made at the Loviisa nuclear power plant to reduce fire risks originating from the turbine generators

    International Nuclear Information System (INIS)

    Virolainen, T.; Marttila, J.; Aulamo, H.

    1998-01-01

    Comprehensive upgrading measures have been completed for the Loviisa Nuclear Power Plant (modified VVER440/V213). These were carried out from the start of the design phase and during operation to ensure safe plant shutdown in the event of a large turbine generator oil fire. These modifications were made mainly on a deterministic basis according to specific risk studies and fire analyses. As part of the probabilistic safety assessment, a fire risk analysis was made that confirmed the importance of these upgrading measures. In fact, they should be considered as design basis modifications for all VVER440 plants. (author)

  6. Nuclear power publications

    International Nuclear Information System (INIS)

    1982-01-01

    This booklet lists 69 publications on nuclear energy available free from some of the main organisations concerned with its development and operation in the UK. Headings are: general information; the need for nuclear energy; the nuclear industry; nuclear power stations; fuel cycle; safety; waste management. (U.K.)

  7. Nuclear power development

    International Nuclear Information System (INIS)

    Nealey, S.

    1990-01-01

    The objective of this study is to examine factors and prospects for a resumption in growth of nuclear power in the United States over the next decade. The focus of analysis on the likelihood that current efforts in the United States to develop improved and safer nuclear power reactors will provide a sound technical basis for improved acceptance of nuclear power, and contribute to a social/political climate more conducive to a resumption of nuclear power growth. The acceptability of nuclear power and advanced reactors to five social/political sectors in the U.S. is examined. Three sectors highly relevant to the prospects for a restart of nuclear power plant construction are the financial sector involved in financing nuclear power plant construction, the federal nuclear regulatory sector, and the national political sector. For this analysis, the general public are divided into two groups: those who are knowledgeable about and involved in nuclear power issues, the involved public, and the much larger body of the general public that is relatively uninvolved in the controversy over nuclear power

  8. Nuclear power flies high

    International Nuclear Information System (INIS)

    Friedman, S.T.

    1983-01-01

    Nuclear power in aircraft, rockets and satellites is discussed. No nuclear-powered rockets or aircraft have ever flown, but ground tests were successful. Nuclear reactors are used in the Soviet Cosmos serles of satellites, but only one American satellite, the SNAP-10A, contained a reactor. Radioisotope thermoelectric generators, many of which use plutonium 238, have powered more than 20 satellites launched into deep space by the U.S.A

  9. Worldwide nuclear power

    International Nuclear Information System (INIS)

    Royen, J.

    1981-01-01

    Worldwide nuclear power (WNP) is a companion volume to UPDATE. Our objective in the publication of WNP is to provide factual information on nuclear power programs and policies in foreign countries to U.S. policymakers in the Federal Government who are instrumental in defining the direction of nuclear power in the U.S. WNP is prepared by the Office of the Assistant Secretary for Nuclear Energy from reports obtained from foreign Embassies in Washington, U.S. Embassies overseas, foreign and domestic publications, participation in international studies, and personal communications. Domestic nuclear data is included only where its presence is needed to provide easy and immediate comparisons with foreign data

  10. Nuclear power controversy

    International Nuclear Information System (INIS)

    Murphy, A.W.

    1976-01-01

    Arthur W. Murphy in the introductory chapter cites the issues, pro and con, concerning nuclear power. In assessing the present stance, he first looks back to the last American Assembly on nuclear power, held October 1957 and notes its accomplishments. He summarizes the six papers of this book, which focus on nuclear power to the end of this century. Chapter I, Safety Aspects of Nuclear Energy, by David Bodansky and Fred Schmidt, deals with the technical aspects of reactor safety as well as waste storage and plutonium diversion. Chapter 2, The Economics of Electric Power Generation--1975-2000, by R. Michael Murray, Jr., focuses specifically on coal-fired and nuclear plants. Chapter 3, How Can We Get the Nuclear Job Done, by Fritz Heimann, identifies actions that must take place to develop nuclear power in the U.S. and who should build the reprocessing plants. Chapter 4, by Arthur Murphy, Nuclear Power Plant Regulation, discusses the USNRC operation and the Price-Anderson Act specifically. Chapter 5, Nuclear Exports and Nonproliferation Strategy, by John G. Palfrey, treats the international aspects of the problem with primary emphasis upon the situation of the U.S. as an exporter of technology. Chapter 6, by George Kistiakowsky, Nuclear Power: How Much Is Too Much, expresses doubt about the nuclear effort, at least in the short run

  11. Ecological radiation protection criteria for nuclear power

    International Nuclear Information System (INIS)

    Kryshev, I.I.

    1993-01-01

    By now a large quantity of radioactive hazards of all sizes and shapes has accumulated in Russia. They include RBMK, VVER, and BN (fast-neutron) nuclear power plants, nuclear fuel processing plants, radioactive waste dumps, ships with nuclear power units, etc. In order to evaluate the radioecological situation correctly, the characteristics of the radioactive contamination must be compiled in these areas with some system of criteria which will provide an acceptable level of ecological safety. Currently health criteria for radiation protection are, which are oriented to man's radiation protection, predominate. Here the concept of a thresholdless linear dose-response dependence, which has been confirmed experimentally only at rather high doses (above 1 Gy), is taken as the theoretical basis for evaluating and normalizing radiation effects. According to one opinion, protecting people against radiation is sufficient to protect other types of organisms, although they are not necessarily of the same species. However, from the viewpoint of ecology, this approach is incorrect, because it does not consider radiation dose differences between man and other living organisms. The article discusses dose-response dependences for various organisms, biological effects of ionizing radiation, and appropriate radiation protection criteria

  12. Nuclear power in Korea

    International Nuclear Information System (INIS)

    Rim, C.S.

    1990-01-01

    Before addressing the issue of public and utility acceptance of nuclear power in Korea, let me briefly explain the Korean nuclear power program and development plan for a passively safe nuclear power plant in Korea. At present, there are eight PWRs and one CANDU in operation; two PWRs are under construction, and contract negotiations are underway for one more CANDU and two more PWRs, which are scheduled to be completed by 1997,1998 and 1999, respectively. According to a recent forecast for electricity demand in Korea, about fifty additional nuclear power plants with a generating capacity of 1000MWe are required by the year 2030. Until around 2006, Korean standardized nuclear power plants with evolutionary features such as those in the ALWR program are to be built, and a new type of nuclear power plant with passive safety features is expected to be constructed after 2006. The Korean government is making a serious effort to increase public understanding of the safety of nuclear power plants and radioactive waste storage and disposal. In addition, the Korean government has recently introduced a program of benefits for residents near nuclear power plants. By this program, common facilities such as community centers and new roads are constructed, and scholarships are given to the local students. Nuclear power is accepted positively by the utility and reasonably well by the public in Korea

  13. Role of nuclear power

    International Nuclear Information System (INIS)

    Eklund, S.

    1982-01-01

    A survey of world nuclear installations, the operating experiences of power reactors, and estimates of future nuclear growth leads to the conclusion that nuclear power's share of world electric power supply will grow slowly, but steadily during this decade. This growth will lead advanced countries to use the commercial breeder by the end of the century. Nuclear power is economically viable for most industrialized and many developing countries if public acceptance problems can be resolved. A restructuring of operational safety and regulations must occur first, as well as a resolution of the safeguards and technology transfer issue. 7 figures, 7 tables

  14. Nuclear power in Asia

    International Nuclear Information System (INIS)

    2007-01-01

    The Australian Uranium Association reports that Asia is the only region in the world where electricity generating capacity and specifically nuclear power is growing significantly. In East and South Asia, there are over 109 nuclear power reactors in operation, 18 under construction and plans to build about a further 100. The greatest growth in nuclear generation is expected in China, Japan, South Korea and India. As a member of the SE Asian community, Australia cannot afford to ignore the existence and growth of nuclear power generation on its door step, even if it has not, up to now, needed to utilise this power source

  15. Nuclear power in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Rim, C S [Radioactive Waste Management Centre, Korea Atomic Energy Research Institute, Taejon, Choong-Nam (Korea, Republic of)

    1990-07-01

    Before addressing the issue of public and utility acceptance of nuclear power in Korea, let me briefly explain the Korean nuclear power program and development plan for a passively safe nuclear power plant in Korea. At present, there are eight PWRs and one CANDU in operation; two PWRs are under construction, and contract negotiations are underway for one more CANDU and two more PWRs, which are scheduled to be completed by 1997,1998 and 1999, respectively. According to a recent forecast for electricity demand in Korea, about fifty additional nuclear power plants with a generating capacity of 1000MWe are required by the year 2030. Until around 2006, Korean standardized nuclear power plants with evolutionary features such as those in the ALWR program are to be built, and a new type of nuclear power plant with passive safety features is expected to be constructed after 2006. The Korean government is making a serious effort to increase public understanding of the safety of nuclear power plants and radioactive waste storage and disposal. In addition, the Korean government has recently introduced a program of benefits for residents near nuclear power plants. By this program, common facilities such as community centers and new roads are constructed, and scholarships are given to the local students. Nuclear power is accepted positively by the utility and reasonably well by the public in Korea.

  16. Development of nuclear power

    International Nuclear Information System (INIS)

    1960-01-01

    The discussion on the development of nuclear power took place on 28 September 1960 in Vienna. In his opening remarks, Director General Cole referred to the widespread opinion that 'the prospect of cheap electricity derived from nuclear energy offers the most exciting prospect for improving the lot of mankind of all of the opportunities for uses of atomic energy'. He then introduced the four speakers and the moderator of the discussion, Mr. H. de Laboulaye, IAEA Deputy Director General for Technical Operations. n the first part of the discussion the experts addressed themselves in turn to four topics put forward by the moderator. These were: the present technical status of nuclear power, the present costs of nuclear power, prospects for future reductions in the cost of nuclear power, and applications of nuclear power in less-developed areas

  17. Nuclear power debate

    International Nuclear Information System (INIS)

    Hunwick, Richard

    2005-01-01

    A recent resurgence of interest in Australia in the nuclear power option has been largely attributed to growing concerns over climate change. But what are the real pros and cons of nuclear power? Have advances in technology solved the sector's key challenges? Do the economics stack up for Australia where there is so much coal, gas and renewable resources? Is the greenhouse footprint' of nuclear power low enough to justify its use? During May and June, the AIE hosted a series of Branch events on nuclear power across Sydney, Adelaide and Perth. In the interest of balance, and at risk of being a little bit repetitive, here we draw together four items that resulted from these events and that reflect the opposing views on nuclear power in Australia. Nuclear Power for Australia: Irrelevant or Inevitable? - a summary of the presentations to the symposium held by Sydney Branch on 8 June 2005. Nuclear Reactors Waste the Planet - text from the flyer distributed by The Greens at their protest gathering outside the symposium venue on 8 June 2005. The Case For Nuclear Power - an edited transcript of Ian Hore-Lacy's presentation to Adelaide Branch on 19 May 2005 and to Perth Branch on 28 June 2005. The Case Against Nuclear Power - an article submitted to Energy News by Robin Chappie subsequent to Mr Hore-Lacy's presentation to Perth Branch

  18. 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

  19. The nuclear power decisions

    International Nuclear Information System (INIS)

    Williams, R.

    1980-01-01

    Nuclear power has now become highly controversial and there is violent disagreement about how far this technology can and should contribute to the Western energy economy. More so than any other energy resource, nuclear power has the capacity to provide much of our energy needs but the risk is now seen to be very large indeed. This book discusses the major British decisions in the civil nuclear field, and the way they were made, between 1953 and 1978. That is, it spans the period between the decision to construct Calder Hall - claimed as the world's first nuclear power station - and the Windscale Inquiry - claimed as the world's most thorough study of a nuclear project. For the period up to 1974 this involves a study of the internal processes of British central government - what the author terms 'private' politics to distinguish them from the very 'public' or open politics which have characterised the period since 1974. The private issues include the technical selection of nuclear reactors, the economic arguments about nuclear power and the political clashes between institutions and individuals. The public issues concern nuclear safety and the environment and the rights and opportunities for individuals and groups to protest about nuclear development. The book demonstrates that British civil nuclear power decision making has had many shortcomings and concludes that it was hampered by outdated political and administrative attitudes and machinery and that some of the central issues in the nuclear debate were misunderstood by the decision makers themselves. (author)

  20. Financing nuclear power

    International Nuclear Information System (INIS)

    Sheriffah Noor Khamseah Al-Idid Syed Ahmad Idid

    2009-01-01

    Global energy security and climate change concerns sparked by escalating oil prices, high population growth and the rapid pace of industrialization are fueling the current interest and investments in nuclear power. Globally, a significant number policy makers and energy industry leaders have identified nuclear power as a favorable alternative energy option, and are presently evaluating either a new or an expanded role for nuclear power. The International Atomic Energy Agency (IAEA) has reported that as of October 2008, 14 countries have plans to construct 38 new nuclear reactors and about 100 more nuclear power plants have been written into the development plans of governments for the next three decades. Hence as new build is expected to escalate, issues of financing will become increasingly significant. Energy supply, including nuclear power, considered as a premium by government from the socio-economic and strategic perspective has traditionally been a sector financed and owned by the government. In the case for nuclear power, the conventional methods of financing include financing by the government or energy entity (utility or oil company) providing part of the funds from its own resources with support from the government. As national financing is, as in many cases, insufficient to fully finance the nuclear power plants, additional financing is sourced from international sources of financing including, amongst others, Export Credit Agencies (ECAs) and Multilateral Development Institutions. However, arising from the changing dynamics of economics, financing and business model as well as increasing concerns regarding environmental degradation , transformations in methods of financing this energy sector has been observed. This paper aims to briefly present on financing aspects of nuclear power as well as offer some examples of the changing dynamics of financing nuclear power which is reflected by the evolution of ownership and management of nuclear power plants

  1. Nuclear power status 1998

    International Nuclear Information System (INIS)

    1999-01-01

    The document gives general statistical information (by country) about electricity produced by nuclear power plants in the world in 1998, and in a table the number of nuclear reactors in operation, under construction, nuclear electricity supplied in 1998, and total operating experience as of 31 December 1998

  2. Nuclear Power Plants. Revised.

    Science.gov (United States)

    Lyerly, Ray L.; Mitchell, Walter, III

    This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. Among the topics discussed are: Why Use Nuclear Power?; From Atoms to Electricity; Reactor Types; Typical Plant Design Features; The Cost of Nuclear Power; Plants in the United States; Developments in Foreign…

  3. Balakovo nuclear power station

    International Nuclear Information System (INIS)

    1996-01-01

    A key means of improving the safety and reliability of nuclear power plants is through effective training of plant personnel. The goal of this paper is to show the progress of the training at the Balakovo Nuclear Power Plant, and the important role that international cooperation programs have played in that progress

  4. Nuclear power economics

    International Nuclear Information System (INIS)

    Moynet, G.

    1987-01-01

    The economical comparison of nuclear power plants with coal-fired plants in some countries or areas are analyzed. It is not difficult to show that nuclear power will have a significant and expanding role to play in providing economic electricity in the coming decades. (Liu)

  5. Nuclear power: Pt. 3

    International Nuclear Information System (INIS)

    Van Wyk, A.

    1985-01-01

    The use of nuclear power in warfare is viewed from the point of use usefullness, essentiality and demolition. The effects of a H-bomb explosion are discussed as well as the use of nuclear power in warfare, with a Christian ethical background

  6. Consideration of nuclear power

    International Nuclear Information System (INIS)

    Smart, I.

    1982-01-01

    Mr. Smart notes that the optimistic promise of nuclear energy for developing countries has not been met, but feels that nuclear power can still provide a growing share of energy during the transition from oil dependence. He observes that cost-benefit analyses vary for each country, but good planning and management can give nuclear power a positive future for those developing countries which can establish a need for it; have access to the economic, technological, and human resources necessary to develop and operate it; and can make nuclear power compatible with the social, economic, and cultural structure. 11 references

  7. Nuclear power in crisis

    International Nuclear Information System (INIS)

    Blowers, Andrew.; Pepper, David.

    1987-01-01

    Six themes run through this book: nuclear decision making and democratic accountability, nuclear bias and a narrow-based energy policy, scientific discredit and popular expertise, fusing science with social values, managerial competence and the geography of nuclear power. These are covered in thirteen chapters (all indexed separately) grouped into four parts -the political and planning context, nuclear waste, risk and impact - the social dimension and the future of nuclear power. It considers aspects in France, the United States and the United Kingdom with particular references to the Sizewell-B inquiry and the Sellafield reprocessing plant. (UK)

  8. Nuclear power plant outages

    International Nuclear Information System (INIS)

    1998-01-01

    The Finnish Radiation and Nuclear Safety Authority (STUK) controls nuclear power plant safety in Finland. In addition to controlling the design, construction and operation of nuclear power plants, STUK also controls refuelling and repair outages at the plants. According to section 9 of the Nuclear Energy Act (990/87), it shall be the licence-holder's obligation to ensure the safety of the use of nuclear energy. Requirements applicable to the licence-holder as regards the assurance of outage safety are presented in this guide. STUK's regulatory control activities pertaining to outages are also described

  9. Nuclear power plants

    International Nuclear Information System (INIS)

    Margulova, T.Ch.

    1976-01-01

    The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

  10. Nuclear power in Europe

    International Nuclear Information System (INIS)

    Perera, J.

    2000-01-01

    Currently nuclear power accounts for more than 25% of total electricity production in Europe (including Eastern Europe and the former Soviet Union) However, significant new construction is planned in Central and Eastern Europe only, apart from some in France and, possibly in Finland. Many countries in Western Europe have put nuclear construction plans on hold and several have cancelled their nuclear programs. This report looks at the history of nuclear power and its current status in both Eastern and Western Europe. It provides an outline of nuclear fuel cycle facilities, from uranium procurement to final waste disposal. Economic and environmental issues are discussed, as well as the prospect of increased East-West trade and cooperation in the new poso-cold war world. Detailed profiles are provided of all the countries in Western Europe with significant nuclear power programs, as well as profiles of major energy and nuclear companies

  11. Mobile nuclear power systems

    International Nuclear Information System (INIS)

    Andersson, B.

    1988-11-01

    This report is meant to present a general survey of the mobile nuclear power systems and not a detailed review of their technical accomplishments. It is based in published material mainly up to 1987. Mobile nuclear power systems are of two fundamentally different kinds: nuclear reactors and isotopic generators. In the reactors the energy comes from nuclear fission and in the isotopic generators from the radioactive decay of suitable isotopes. The reactors are primarily used as power sourves on board nuclear submarines and other warships but have also been used in the space and in remote places. Their thermal power has ranged from 30 kWth (in a satellite) to 175 MWth (on board an aircraft carrier). Isotopic generators are suitable only for small power demands and have been used on board satellites and spaceprobes, automatic weatherstations, lighthouses and marine installations for navigation and observation. (author)

  12. Presenting a model of repair and preventing maintenance of Bushehr nuclear power plants analyzing the data of similar nuclear power plants

    International Nuclear Information System (INIS)

    Parikhan, Hammidreza

    1997-01-01

    Due to the increase application of nuclear energy for producing electricity, special attention must be paid to their maintenance activities in general and preventive maintenance in particular. It has been shown that a well established preventive maintenance programme will enhance the reliability and availability of nuclear power plants. A model of preventive maintenance for Buhehr nuclear power plant which is due to be completed by 2001 is developed. The prescribed model is based on past experiences of VVER nuclear power plants around the world. The utilized data is provided by International Atomic Energy Agency (IAEA) in Vienna, Austria. The data and past experiences reveal such important information as availability, energy loss, types of failures, duration of failure, etc. A strategy for designing a database is established. These data are then analyzed by statistical methods such as Pareto analysis, t-test, K-S test, analysis of variance, etc. The results of our analysis reveal important information in regard to establishment of a well-defined preventive maintenance programme in Buhshehr nuclear power plant. The results show that certain equipment such turbo-generator and control-rods play an important role in the maintenance of a VVER nuclear power plant. Other findings are discussed in great detail

  13. Nuclear power development

    International Nuclear Information System (INIS)

    Povolny, M.

    1980-01-01

    The development and uses of nuclear power in Czechoslovakia and other countries are briefly outlined. In the first stage, the Czechoslovak nuclear programme was oriented to the WWER 440 type reactor while the second stage of the nuclear power plant construction is oriented to the WWER 10O0 type reactor. It is envisaged that 12 WWER 440 type reactors and four to five WWER 1000 type reactors will be commissioned till 1990. (J.P.)

  14. The nuclear power station

    International Nuclear Information System (INIS)

    Plettner, B.

    1987-04-01

    The processes taking place in a nuclear power plant and the dangers arising from a nuclear power station are described. The means and methods of controlling, monitoring, and protecting the plant and things that can go wrong are presented. There is also a short discourse on the research carried out in the USA and Germany, aimed at assessing the risks of utilising nuclear energy by means of the incident tree analysis and probability calculations. (DG) [de

  15. Nuclear power in Spain

    International Nuclear Information System (INIS)

    1979-01-01

    the plans of the Spanish Government to reduce their dependence on oil over the next ten years by a considerable increase in nuclear generating capacity are outlined. Data on the type, generating power, location and commissioning data of a number of nuclear power stations in Spain are tabulated. The use of foreign companies for the design and construction of the nuclear stations and the national organisations responsible for different aspects of the programme are considered. (UK)

  16. Nuclear power in space

    International Nuclear Information System (INIS)

    Aftergood, S.; Hafemeister, D.W.; Prilutsky, O.F.; Rodionov, S.N.; Primack, J.R.

    1991-01-01

    Nuclear reactors have provided energy for satellites-with nearly disastrous results. Now the US government is proposing to build nuclear-powered boosters to launch Star Wars defenses. These authors represent scientific groups that are opposed to the use of nuclear power in near space. The authors feel that the best course for space-borne reactors is to ban them from Earth orbit and use them in deep space

  17. Nuclear power experience

    International Nuclear Information System (INIS)

    Daglish, J.

    1982-01-01

    A report is given of a recent international conference convened by the IAEA to consider the technical and economic experience acquired by the nuclear industry during the past 30 years. Quotations are given from a number of contributors. Most authors shared the opinion that nuclear power should play a major role in meeting future energy needs and it was considered that the conference had contributed to make nuclear power more viable. (U.K.)

  18. Equivalent thermal conductivity of the storage basket with spent nuclear fuel of VVER-1000 reactors

    International Nuclear Information System (INIS)

    Alyokhina, Svitlana; Kostikov, Andriy

    2014-01-01

    Due to limitation of computation resources and/or computation time many thermal problems require to use simplified geometrical models with equivalent thermal properties. A new method for definition of equivalent thermal conductivity of spent nuclear fuel storage casks is proposed. It is based on solving the inverse heat conduction problem. For the proposed method two approaches for equivalent thermal conductivity definition were considered. In the first approach a simplified model in conjugate formulation is used, in the second approach a simplified model of solid body which allows an analytical solution is used. For safety ensuring during all time of spent nuclear fuel storage the equivalent thermal conductivity was calculated for different storage years. The calculated equivalent thermal conductivities can be used in thermal researches for dry spent nuclear fuel storage safety.

  19. Governance of nuclear power

    International Nuclear Information System (INIS)

    Allison, G.; Carnesale, A.; Zigman, P.; DeRosa, F.

    1981-01-01

    Utility decisions on whether to invest in nuclear power plants are complicated by uncertainties over future power demand, regulatory changes, public perceptions of nuclear power, and capital costs. A review of the issues and obstacles confronting nuclear power also covers the factors affecting national policies, focusing on three institutional questions: regulating the industry, regulating the regulators, and regulatory procedures. The specific recommendations made to improve safety, cost, and public acceptance will still not eliminate uncertainties unless the suggested fundamental changes are made. 29 references

  20. Development of an automated system of nuclear materials accounting for nuclear power stations with water-cooled, water-moderated reactors

    International Nuclear Information System (INIS)

    Babaev, N.S.

    1981-06-01

    The results of work carried out under IAEA Contract No. 2336/RB are described (subject: an automated system of nuclear materials accounting for nuclear power stations with water-cooled, water-moderated (VVER) reactors). The basic principles of an accounting system for this type of nuclear power plant are outlined. The general structure and individual units of the information computer program used to achieve automated accounting are described and instructions are given on the use of the program. A detailed example of its application (on a simulated nuclear power plant) is examined

  1. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    International Nuclear Information System (INIS)

    GREENE, G.A.; GUPPY, J.G.

    1998-01-01

    This is the final report on the INSP project entitled, ''Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology

  2. MEASUREMENTS OF THE CONFINEMENT LEAKTIGHTNESS AT THE KOLA NUCLEAR POWER STATION (UNIT 2) IN RUSSIA

    Energy Technology Data Exchange (ETDEWEB)

    GREENE,G.A.; GUPPY,J.G.

    1998-08-01

    This is the final report on the INSP project entitled, ``Kola Confinement Leaktightness'' conducted by BNL under the authorization of Project Work Plan WBS 1.2.2.1. This project was initiated in February 1993 to assist the Russians to reduce risks associated with the continued operation of older Soviet-designed nuclear power plants, specifically the Kola VVER-440/230 Units 1 and 2, through upgrades in the confinement performance to reduce the uncontrolled leakage rate. The major technical objective of this-project was to improve the leaktightness of the Kola NPP VVER confinement boundaries, through the application of a variety of sealants to penetrations, doors and hatches, seams and surfaces, to the extent that current technology permitted. A related objective was the transfer, through training of Russian staff, of the materials application procedures to the staff of the Kola NPP. This project was part of an overall approach to minimizing uncontrolled releases from the Kola NPP VVER440/230s in the event of a serious accident, and to thereby significantly mitigate the consequences of such an accident. The US provided materials, application technology, and applications equipment for application of sealant materials, surface coatings, potting materials and gaskets, to improve the confinement leaktightness of the Kola VVER-440/23Os. The US provided for training of Russian personnel in the applications technology.

  3. Nuclear power under strain

    International Nuclear Information System (INIS)

    1978-08-01

    The German citizen faces the complex problem of nuclear power industry with slight feeling of uncertainty. The topics in question can only be briefly dealt with in this context, e.g.: 1. Only nuclear energy can compensate the energy shortage. 2. Coal and nuclear energy. 3. Keeping the risk small. 4. Safety test series. 5. Status and tendencies of nuclear energy planning in the East and West. (GL) [de

  4. Worldwide nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    Worldwide Nuclear Power (WNP) is a companion volume to Update. Our objective in the publication of WNP is to provide factual information on nuclear power programs and policies in foreign countries to U.S. policymakers in the Federal Government. Facts about the status of nuclear activities abroad should be available to those who are instrumental in defining the direction of nuclear power in the U.S. WNP is prepared by the Office of Nuclear Energy from reports obtained from foreign embassies in Washington, U.S. Embassies overseas, foreign and domestic publications, participation in international studies, and personal communications. It consists of two types of information, tabular and narrative. Domestic nuclear data is included only where its presence is needed to provide easy and immediate comparisons with foreign data. In general, complete U.S. information will be found in Update

  5. Nuclear power statistics 1985

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1986-06-01

    In this report an attempt is made to collect literature data on nuclear power production and to present it on graphical form. Data is given not only for 1985, but for a number of years so that the trends in the development of nuclear power can be seen. The global capacity of nuclear power plants in operation and those in operation, under construction, or on order is considered. Further the average capacity factor for nuclear plants of a specific type and for various geographical areas is given. The contribution of nuclear power to the total electricity production is considered for a number of countries and areas. Finally, the accumulated years of commercial operation for the various reactor types up to the end of 1985 is presented. (author)

  6. Study on safety analysis of VVER-1200/V491 in scenario of Loss of Coolant Accidents along with partly failure of ECCS using RELAP5 code

    International Nuclear Information System (INIS)

    Hoang Minh Giang; Ha Thi Anh Dao; Hoang Tan Hung; Bui Thi Hoa; Nguyen Thi Tu Oanh; Dinh Anh Tuan; Pham Tuan Nam

    2017-01-01

    The advanced VVER-1200/V491 reactor designed with passive safety systems to deal with design extension conditions is primarily selected as priority candidate for Ninh Thuan 1 nuclear power plant project. So that, in order to enhance competence of nuclear safety and toward participation on review Safety Analysis Report (SAR) of Ninh Thuan nuclear Power project the study on safety analysis of VVER-1200/V491 in scenario of Loss of Coolant Accidents along with partly failure of ECCS is implemented. As requirement of the study, the input deck file of VVER-1200/V491 for RELAP5 and analysis report for some special case of LOCAs along with partly failure of ECCS are issued. (author)

  7. Nuclear power: European report

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    In 2004, nuclear power plants were operated and/or built in eighteen European countries. Thirteen of these countries are members of EU-25. Five of the ten countries joining the European Union on May 1, 2004 operate nuclear power stations. A total of 206 power reactors with a gross power of 181,941 MWe and a net power of 172,699 MWe were in operation at the end of the year. In 2004, one nuclear power plant was commissioned in Russia (Kalinin 3), two (Kmelnitzki 2 and Rowno 4) in Ukraine. Five nuclear power plants were decommissioned in Europe in the course of 2004. As announced in 2000, the Chapelcross 1 to Chapelcross 4 plants in Britain were shut down for economic reasons. In Lithuania, the Ignalina 1 unit was disconnected from the power grid, as had been demanded by the EU Commission within the framework of the negotiations about the country's accession to the EU. As a result of ongoing technical optimization in some plants, involving increases in reactor power or generator power as well as commissioning of plants of higher capacity, nuclear generating capacity increased by approx. 1.5 GW. In late 2004, four nuclear generating units were under construction in Finland (1), Romania (1), and Russia (2). 150 nuclear power plants were operated in thirteen states of the European Union (EU-25), which is sixteen more than the year before as a consequence of the accession of new countries. They had an aggregate gross power of 137,943 MWe and a net power of 131,267 MWe, generating approx. 983 billion gross kWh of electricity in 2003, thus again contributing some 32% to the public electricity supply in the EU-25. In largest share of nuclear power in electricity generation is found in Lithuania (80%), followed by 78% in France, 57% in the Slovak Republic, 56% in Belgium, and 46% in Ukraine. In several countries not operating nuclear power plants of their own, such as Italy, Portugal, and Austria, nuclear power makes considerable contributions to public electricity supply as

  8. The nuclear power cycle

    International Nuclear Information System (INIS)

    2004-01-01

    Fifty years after the first nuclear reactor come on-line, nuclear power is fourth among the world's primary energy sources, after oil, coal and gas. In 2002, there were 441 reactors in operation worldwide. The United States led the world with 104 reactors and an installed capacity of 100,000 MWe, or more than one fourth of global capacity. Electricity from nuclear energy represents 78% of the production in France, 57% in Belgium, 46% in Sweden, 40% in Switzerland, 39% in South Korea, 34% in Japan, 30% in Germany, 30% in Finland, 26% in Spain, 22% in Great Britain, 20% in the United States and 16% in Russia. Worldwide, 32 reactors are under construction, including 21 in Asia. This information document presents the Areva activities in the nuclear power cycle: the nuclear fuel, the nuclear reactors, the spent fuel reprocessing and recycling and nuclear cleanup and dismantling. (A.L.B.)

  9. Commercial nuclear power 1990

    International Nuclear Information System (INIS)

    1990-01-01

    This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs

  10. Nuclear power in India

    International Nuclear Information System (INIS)

    Bose, D.K.

    1980-01-01

    India has now nine years of experience with her in nuclear power generation. The system has been acclaimed on various grounds by the authority concerned with its organization in the country. The present paper intends to examine critically the claim for economic superiority of the nuclear power over the thermal power which is asserted often by the spokesmen for the former. Information about the cost of nuclear power that is available to researchers in India is very meagre. Whatever appears in official publications is hardly adequate for working out reasonable estimates for scrutiny. One is therefore left to depend on the public statements made by dignitaries from time to time to form an idea about the economics of nuclear power. Due to gaps in information we are constrained to rely on the foreign literature and make careful guesses about possible costs applicable to India

  11. LDC nuclear power: Brazil

    International Nuclear Information System (INIS)

    Johnson, V.

    1982-01-01

    Brazil has been expanding its nuclear power since 1975, following the Bonn-Brasilia sales agreement and the 1974 denial of US enriched uranium, in an effort to develop an energy mix that will reduce dependence and vulnerability to a single energy source or supplier. An overview of the nuclear program goes on to describe domestic non-nuclear alternatives, none of which has an adequate base. The country's need for transfers of capital, technology, and raw materials raises questions about the advisability of an aggressive nuclear program in pursuit of great power status. 33 references

  12. Nuclear power - the future

    International Nuclear Information System (INIS)

    Hann, J.

    1991-01-01

    It is asserted by the author that nuclear power is the only available resource - indeed the only solution to an ever-increasing demand for energy in the United Kingdom over the next 50-100 years. It must be the cornerstone of a practical integrated energy policy, covering that sort of time-scale. In fact, it is going to be a strategic necessity. In this paper the background to establishing a policy is sketched. An explanation is given of what the nuclear industry is doing so as to ensure that the nuclear option is very definitely retained as a result of the 1994 Review of nuclear power in the UK. (author)

  13. VVER-440 control rod follower induced local power peaking computational benchmark: MCNP and KARATE solutions

    International Nuclear Information System (INIS)

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

    2009-01-01

    In this paper the linear pin power calculation in the KARATE-440 code system are presented. The calculation results show that: 1) The coupler mathematical benchmark was solved by the KARATE code system using the same methods and approximations as in case of NPP applications. 2) Without Hf plate in the fuel pin row next to the problematic coupler section pronounced local power peak arises. 4) Though the underprediction of the peak by KARATE-SADR is 4%, it is in accordance with the applied uncertainty of KARATE-SADR. 5) The application of Hf plate solves the problem.

  14. Backfitting of Nuclear Power Plant Bohunice V1 in Slovakia

    International Nuclear Information System (INIS)

    Ferenc, M.

    1999-01-01

    Nuclear power plants in the Slovak Republic generate almost 55 % of electricity. The operating organization and the Nuclear Regulatory Authority of the Slovak Republic pay a great attention to safe and reliable operation of four units with VVER 440 reactors at Bohunices site and one in Mochovce side. Engineering and design organizations in cooperation with well known international companies prepare evaluation of safety conditions, safety analyses and projects for the implementation of modifications to upgrade the nuclear safety of the units in operation. A gradual safety upgrading (reconstruction) of the V-1 Bohunice plant has been in progress, a modernization of the V-2 Bohunice plant is being prepared. Simultaneously the commissioning of Unit 2 at the Mochovce plant is being implemented.(author)

  15. Nuclear power generation

    International Nuclear Information System (INIS)

    Hirao, Katumi; Sato, Akira; Kaimori, Kimihiro; Kumano, Tetsuji

    2001-01-01

    Nuclear power generation for commercial use in Japan has passed 35 years since beginning of operation in the Tokai Nuclear Power Station in 1966, and has 51 machines of reactor and about 44.92 MW of total output of equipment scale in the 21st century. However, an environment around nuclear energy becomes severer at present, and then so many subjects to be overcome are remained such as increased unreliability of the public on nuclear energy at a chance of critical accident of the JCO uranium processing facility, delay of pull-thermal plan, requirement for power generation cost down against liberalization of electric power, highly aging countermeasure of power plant begun its operation as its Genesis, and so on. Under such conditions, in order that nuclear power generation in Japan survives as one of basic electric source in future, it is necessary not only to pursue safety and reliability of the plant reliable to the public, but also to intend to upgrade its operation and maintenance by positively adopting good examples on operational management method on abroad and to endeavor further upgrading of application ratio of equipments and reduction of generation cost. Here were outlined on operation conditions of nuclear power stations in Japan, and introduced on upgrading of their operational management and maintenance management. (G.K.)

  16. Development of nuclear power

    International Nuclear Information System (INIS)

    1962-01-01

    An extensive discussion of problems concerning the development of nuclear power took place at the fifth regular session of the IAEA General Conference in September-October 1961. Not only were there many references in plenary meetings to the nuclear power plans of Member States, but there was also a more specific and detailed debate on the subject, especially on nuclear power costs, in the Program, Technical and Budget Committee of the Conference. The Conference had before it a report from the Board of Governors on the studies made by the Agency on the economics of nuclear power. In addition, it had been presented with two detailed documents, one containing a review of present-day costs of nuclear power and the other containing technical and economic information on several small and medium-sized power reactors in the United States. The Conference was also informed of the report on methods of estimating nuclear power costs, prepared with the assistance of a panel of experts convened by the Agency, which was reviewed in the July 1961 issue of this Bulletin

  17. Development of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-01-15

    An extensive discussion of problems concerning the development of nuclear power took place at the fifth regular session of the IAEA General Conference in September-October 1961. Not only were there many references in plenary meetings to the nuclear power plans of Member States, but there was also a more specific and detailed debate on the subject, especially on nuclear power costs, in the Program, Technical and Budget Committee of the Conference. The Conference had before it a report from the Board of Governors on the studies made by the Agency on the economics of nuclear power. In addition, it had been presented with two detailed documents, one containing a review of present-day costs of nuclear power and the other containing technical and economic information on several small and medium-sized power reactors in the United States. The Conference was also informed of the report on methods of estimating nuclear power costs, prepared with the assistance of a panel of experts convened by the Agency, which was reviewed in the July 1961 issue of this Bulletin

  18. 600 MW nuclear power database

    International Nuclear Information System (INIS)

    Cao Ruiding; Chen Guorong; Chen Xianfeng; Zhang Yishu

    1996-01-01

    600 MW Nuclear power database, based on ORACLE 6.0, consists of three parts, i.e. nuclear power plant database, nuclear power position database and nuclear power equipment database. In the database, there are a great deal of technique data and picture of nuclear power, provided by engineering designing units and individual. The database can give help to the designers of nuclear power

  19. Nuclear power experience

    International Nuclear Information System (INIS)

    1983-01-01

    The International Conference on Nuclear Power Experience, organized by the International Atomic Energy Agency, was held at the Hofburg Conference Center, Vienna, Austria, from 13 to 17 September 1982. Almost 1200 participants and observers from 63 countries and 20 organizations attended the conference. The 239 papers presented were grouped under the following seven main topics: planning and development of nuclear power programmes; technical and economic experience of nuclear power production; the nuclear fuel cycle; nuclear safety experience; advanced systems; international safeguards; international co-operation. The proceedings are published in six volumes. The sixth volume contains a complete Contents of Volume 1 to 5, a List of Participants, Authors and Transliteration Indexes, a Subject Index and an Index of Papers by Number

  20. The nuclear power generation

    International Nuclear Information System (INIS)

    Serres, R.

    1999-01-01

    The French nuclear generating industry is highly competitive. The installations have an average age of fifteen years and are half way through their expected life. Nuclear power accounts for 70% of the profits of the French generating company, EDF. Nuclear generation has a minimal effect on the atmosphere and France has a level of CO 2 emissions, thought to be the main cause of the greenhouse effect, half that of Europe as a whole. The air in France is purer than in neighbouring countries, mainly because 75% of all electrical power is generated in nuclear plants and 15% in hydroelectric stations. The operations and maintenance of French nuclear power plants in the service and distribution companies out of a total of 100 000 employees in all, 90 % of whom are based in mainland France. (authors)

  1. Canada's nuclear power programme

    International Nuclear Information System (INIS)

    Peden, W.

    1976-01-01

    Although Canada has developed the CANDU type reactor, and has an ambitious programme of nuclear power plant construction, there has been virtually no nuclear controversy. This progress was seen as a means to bring Canada out of the 'resource cow' era, and onto a more equal footing with technologically elite nations. However the Indian nuclear explosion test, waste storage problems, contamination problems arising from use of uranium ore processing waste as land fill and subsidised sale of nuclear power plants to Argentina and South Korea have initiated public and parliamentary interest. Some economists have also maintained that Canada is approaching over-supply of nuclear power and over-investment in plant. Canada has no official overall energy production plan and alternative sources have not been evaluated. (JIW)

  2. Without nuclear power

    International Nuclear Information System (INIS)

    1987-01-01

    The arguments put forward by the SPD point to the following: Backing out of nuclear power is a must, because of the awful quality of the hazards involved; because there can be no real separation guaranteed between civil and military utilisation of nuclear energy; for reasons of international responsibility; because we must not pass the buck on to the next generation; because social compatibility must be achieved; because the story of the 'cheap' nuclear generation of electricity is a fairy tale; because nuclear power pushes back coal as an energy source; because current ecological conditions call for abandonment of nuclear power, and economic arguments do not really contradict them. A reform of our energy system has to fulfill four requirements: Conserve energy; reduce and avoid environmental pollution; use renewable energy sources as the main sources; leave to the next generation the chance of choosing their own way of life. (HSCH) [de

  3. Nuclear power and safety

    International Nuclear Information System (INIS)

    Saunders, P.; Tasker, A.

    1991-01-01

    Nuclear power currently provides about a fifth of both Britain's and the world's electricity. It is the largest single source of electricity in Western Europe; in France three quarters of electricity is generated by nuclear power stations. This booklet is about the safety of those plants. It approaches the subject by outlining the basic principles and approaches behind nuclear safety, describing the protective barriers and safety systems that are designed to prevent the escape of radioactive material, and summarising the regulations that govern the construction and operation of nuclear power stations. The aim is to provide a general understanding of the subject by explaining the general principles of the Advanced Gas Cooled Reactor and setting out the UKAEA strategy for nuclear safety, the objective being always to minimize risk. (author)

  4. Nuclear Power in Korea

    International Nuclear Information System (INIS)

    Ha, Duk-Sang

    2009-01-01

    Full text: Korea's nuclear power program has been promoted by step-by-step approach; the first stage was 1970's when it depended on the foreign contractors' technology and the second was 1980's when it accumulated lots of technology and experience by jointly implementing the project. Lastly in the third stage in 1990's, Korea successfully achieved the nuclear power technological self-reliance and developed its standard nuclear power plant, so-called Optimized Power Reactor 1000 (OPR 1000). Following the development of OPR 1000, Korea has continued to upgrade the design, known as the Advanced Power Reactor 1400 (APR 1400) and APR+. Korea is one of the countries which continuously developed the nuclear power plant projects during the last 30 years while the other advanced countries ceased the project, and therefore, significant reduction of project cost and construction schedule were possible which benefits from the repetition of construction project. And now, its nuclear industry infrastructure possesses the strong competitiveness in this field.The electricity produced from the nuclear power is 150,958 MWh in 2008, which covers approximately 36% of the total electricity demand in Korea, while the installed capacity of nuclear power is 17,716 MW which is 24% of the total installed capacity. We are currently operating 20 units of nuclear power plants in Korea, and also are constructing 8 additional units (9,600 MW). Korea's nuclear power plants have displayed their excellent operating performance; the average plant capacity factor was 93.4% in 2008, which are about 15% higher than the world average of 77.8%. Moreover, the number of unplanned trips per unit was only 0.35 in 2008, which is the world top class performance. Also currently we are operating four CANDU nuclear units in Korea which are the same reactor type and capacity as the Cernavoda Units. They have been showing the excellent operating performance, of which capacity in 2008 is 92.8%. All the Korean

  5. The future of nuclear power

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1987-01-01

    Present conditions and future prospects for the nuclear power industry in the United States are discussed. The presentation includes a review of trends in electrical production, the safety of coal as compared to nuclear generating plants, the dangers of radiation, the economics of nuclear power, the high cost of nuclear power in the United States, and the public fear of nuclear power. 20 refs

  6. Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system

    Energy Technology Data Exchange (ETDEWEB)

    Gurin, Andrey V. [National Research Centre ' ' Kurchatov Institute' ' , Moscow (Russian Federation); Alekseev, P.N.

    2017-09-15

    This paper presents a study of scenarios of transition to a closed fuel cycle in the system of nuclear power, built basing on resource availability requirements at the stage of full life-cycle reactors. Conventionally, there are three main scenarios for the development of nuclear energy: with VVER reactors operating in an open fuel cycle; with VVER reactors operating in a closed fuel cycle; and co-operating VVER and BN, operating in a closed fuel cycle. For the considered scenarios, a quantitative estimation of change in time of material balances were performed, including spent fuel balance, balance of plutonium, reprocessed and depleted uranium, radioactive waste, and the analysis of the fuel component of the cost of electricity.

  7. Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system

    International Nuclear Information System (INIS)

    Gurin, Andrey V.; Alekseev, P.N.

    2017-01-01

    This paper presents a study of scenarios of transition to a closed fuel cycle in the system of nuclear power, built basing on resource availability requirements at the stage of full life-cycle reactors. Conventionally, there are three main scenarios for the development of nuclear energy: with VVER reactors operating in an open fuel cycle; with VVER reactors operating in a closed fuel cycle; and co-operating VVER and BN, operating in a closed fuel cycle. For the considered scenarios, a quantitative estimation of change in time of material balances were performed, including spent fuel balance, balance of plutonium, reprocessed and depleted uranium, radioactive waste, and the analysis of the fuel component of the cost of electricity.

  8. Nuclear power industry, 1981

    International Nuclear Information System (INIS)

    1981-12-01

    The intent of this publication is to provide a single volume of resource material that offers a timely, comprehensive view of the nuclear option. Chapter 1 discusses the development of commercial nuclear power from a historical perspective, reviewing the factors and events that have and will influence its progress. Chapters 2 through 5 discuss in detail the nuclear powerplant and its supporting fuel cycle, including various aspects of each element from fuel supply to waste management. Additional dimension is brought to the discussion by Chapters 6 and 7, which cover the Federal regulation of nuclear power and the nuclear export industry. This vast body of thoroughly documented information offers the reader a useful tool in evaluating the record and potential of nuclear energy in the United States

  9. Safety and nuclear power

    International Nuclear Information System (INIS)

    Gittus, John; Gunning, Angela.

    1988-01-01

    Representatives of the supporters and opponents of civil nuclear power put forward the arguments they feel the public should consider when making up their mind about the nuclear industry. The main argument in favour of nuclear power is about the low risk in comparison with other risks and the amount of radiation received on average by the population in the United Kingdom from different sources. The aim is to show that the nuclear industry is fully committed to the cause of safety and this has resulted in a healthy workforce and a safe environment for the public. The arguments against are that the nuclear industry is deceitful, secretive and politically motivated and thus its arguments about safety, risks, etc, cannot be trusted. The question of safety is considered further - in particular the perceptions, definitions and responsibility. The economic case for nuclear electricity is not accepted. (U.K.)

  10. Nuclear power training courses

    International Nuclear Information System (INIS)

    1977-01-01

    The training of technical manpower for nuclear power projects in developing countries is now a significant part of the IAEA Technical Assistance Programme. Two basic courses are the cornerstones of the Agency's training programme for nuclear power: a course in planning and implementation, and a course in construction and operation management. These two courses are independent of each other. They are designed to train personnel for two distinct phases of project implementation. The nuclear power project training programme has proven to be successful. A considerable number of highly qualified professionals from developing countries have been given the opportunity to learn through direct contact with experts who have had first-hand experience. It is recognized that the courses are not a substitute for on-the-job training, but their purpose is achieved if they have resulted in the transfer of practical, reliable information and have helped developing countries to prepare themselves for the planning, construction and operation management of nuclear power stations

  11. Nuclear power plant construction

    International Nuclear Information System (INIS)

    Lima Moreira, Y.M. de.

    1979-01-01

    The legal aspects of nuclear power plant construction in Brazil, derived from governamental political guidelines, are presented. Their evolution, as a consequence of tecnology development is related. (A.L.S.L.) [pt

  12. Nuclear power plant siting

    International Nuclear Information System (INIS)

    Sulkiewicz, M.; Navratil, J.

    The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

  13. Nuclear power in Pakistan

    International Nuclear Information System (INIS)

    Siddiqui, Z.H.; Qureshi, I.H.

    2005-01-01

    Pakistan started its nuclear power program by installing a 137 M We Canadian Deuterium Reactor (Candu) at Karachi in 1971 which became operational in 1972. The post-contract technical support for the Karachi Nuclear Power Plant (KANUPP) was withdrawn by Canada in 196 as a consequence of Indian nuclear device test in 1974. In spite of various difficulties PAEC resolved to continue to operate KANUPP and started a process for the indigenous fabrication of spare parts and nuclear fuel. The first fuel bundle fabricated in Pakistan was loaded in the core in 1980. Since then KANUPP has been operating on the indigenously fabricated fuel. The plant computer systems and the most critical instrumentation and Control system were also replaced with up-to date technology. In 2002 KANUPP completed its original design life of 30 year. A program for the life extension of the plant had already been started. The second nuclear power plant of 300 M We pressurized water reactor purchased from China was installed in Chashma in 1997, which started commercial operations in 2001. Another unit of 300 M We will be installed at Chashma in near future. These nuclear power plants have been operating under IAEA safeguards agreements. PAEC through the long-term performance of the two power plants has demonstrated its competence to safely and successfully operate and maintain nuclear power plants. Pakistan foresees an increasingly important and significant share of nuclear power in the energy sector. The Government has recently allocated a share of 8000 MWe for nuclear energy in the total energy scenario of Pakistan by the year 2025. (author)

  14. The Korean nuclear power program

    International Nuclear Information System (INIS)

    Choi, Chang Tong

    1996-01-01

    Although the world nuclear power industry may appear to be in decline, continued nuclear power demand in Korea indicates future opportunities for growth and prosperity in this country. Korea has one of the world's most vigorous nuclear power programs. Korea has been an active promoter of nuclear power generation since 1978, when the country introduced nuclear power as a source of electricity. Korea now takes pride in the outstanding performance of its nuclear power plants, and has established a grand nuclear power scheme. This paper is aimed at introducing the nuclear power program of Korea, including technological development, international cooperation, and CANDU status in Korea. (author). 2 tabs

  15. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This report presents historical data on commercial nuclear power in the United States, with projections of domestic nuclear capacity and generation through the year 2020. The report also gives country-specific projections of nuclear capacity and generation through the year 2010 for other countries in the world outside centrally planned economic areas (WOCA). Information is also presented regarding operable reactors and those under construction in countries with centrally planned economies. 39 tabs

  16. [Nuclear News -- Power

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    The topics discussed in this section are: (1) NU(Northeast Utilities) receives largest court fine levied for false records. (2) ComEd nuclear fleet has best-ever performance. (3) Perry and Beaver Valley now run by First Energy Nuclear. (4) Slight reactor power increases may save dollars; (5) Nuclear plants shares to change hands. (6) Y2K nonsafety-related work scheduled for completion. (7) New NRC plan for reviewing plant license transfers with foreign ownership.

  17. Nuclear power and acceptation

    International Nuclear Information System (INIS)

    Speelman, J.E.

    1990-01-01

    In 1989 a workshop was held organized by the IAEA and the Argonne National Laboratory. The purpose was to investigate under which circumstances a large-scale extension of nuclear power can be accepted. Besides the important technical information, the care for the environment determined the atmosphere during the workshop. The opinion dominated that nuclear power can contribute in tackling the environment problems, but that the social and political climate this almost makes impossible. (author). 7 refs.; 1 fig.; 1 tab

  18. Discounting and nuclear power

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1984-01-01

    The paper describes the practice of discounting and its applicability to nuclear power, and the choice of discount rates. Opportunity cost of capital; risk; social time preference; intergenerational equity; non-monetary aspects; and discounting and nuclear energy; are all discussed. (U.K.)

  19. Nuclear power and leukaemia

    International Nuclear Information System (INIS)

    Grimston, M.

    1991-03-01

    This booklet describes the nature of leukaemia, disease incidence in the UK and the possible causes. Epidemiological studies observing rates of leukaemia near nuclear power stations in the UK and other parts of the world are discussed. Possible causes of leukaemia excesses near nuclear establishments include radioactive discharges into the environment, paternal radiation exposure and viral causes. (UK)

  20. No to nuclear power

    International Nuclear Information System (INIS)

    2006-01-01

    Kim Beazley has again stated a Labor Government would not pursue nuclear power because the economics 'simply don't stack up'. 'We have significant gas, coal and renewable energy reserves and do not have a solution for the disposal of low-level nuclear waste, let alone waste from nuclear power stations.' The Opposition Leader said developing nuclear power now would have ramifications for Australia's security. 'Such a move could result in our regional neighbours fearing we will use it militarily.' Instead, Labor would focus on the practical measures that 'deliver economic and environmental stability while protecting our national security'. Mr Beazley's comments on nuclear power came in the same week as Prime Minister John Howard declined the request of Indian Prime Minister Manmohan Singh for uranium exports, although seemingly not ruling out a policy change at some stage. The Prime Ministers held talks in New Delhi over whether Australia would sell uranium to India without it signing the Nuclear Non-Proliferation Treaty. An agreement reached during a visit by US President George W. Bush gives India access to long-denied nuclear technology and guaranteed fuel in exchange for allowing international inspection of some civilian nuclear facilities. Copyright (2006) Crown Content Pty Ltd

  1. Nuclear Power Plant Technician

    Science.gov (United States)

    Randall, George A.

    1975-01-01

    The author recognizes a body of basic knowledge in nuclear power plant technoogy that can be taught in school programs, and lists the various courses, aiming to fill the anticipated need for nuclear-trained manpower--persons holding an associate degree in engineering technology. (Author/BP)

  2. Nuclear power for beginners

    International Nuclear Information System (INIS)

    Croall, S.; Sempler, K.

    1978-01-01

    A 'comic strip' account of nuclear power, covering weapons and weapons proliferation, reactor accidents involving human errors, radiation hazards, radioactive waste management and the fuel cycle, fast breeder reactors and plutonium, security, public relations and sociological aspects, energy consumption patterns, energy conservation and alternative energy sources, environmental aspects and anti-nuclear activities. (U.K.)

  3. Progress by nuclear power

    International Nuclear Information System (INIS)

    Creamer, A.

    1980-01-01

    United States scientist Petr Beckmann predicts that there will eventually be nuclear power stations in the Transvaal in South Africa. This will take place for two reasons: to decrease pollution problems and to ensure economic advancement. He also refers to the the toxicity of nuclear wastes and coal wastes

  4. World status - nuclear power

    International Nuclear Information System (INIS)

    Holmes, A.

    1984-01-01

    The problems of nuclear power are not so much anti-nuclear public opinion, but more the decrease of electricity consumption growth rate and the high cost of building reactors. Because of these factors, forecasts of world nuclear capacity have had to be reduced considerably over the last three years. The performance of reactors is considered. The CANDU reactor remains the world's best performer and overall tends to out-perform larger reactors. The nuclear plant due to come on line in 1984 are listed by country; this shows that nuclear capacity will increase substantially over a short period. At a time of stagnant demand this will make nuclear energy an important factor in the world energy balance. Nuclear power stations in operation and under construction in 1983 are listed and major developments in commercial nuclear power in 1983 are taken country by country. In most, the report is the same; national reactor ordering cut back because the expected increase in energy demand has not happened. Also the cost-benefit of nuclear over other forms of energy is no longer as favourable. The export opportunities have also declined as many of the less developed countries are unable to afford reactors. (U.K.)

  5. Nuclear power costs

    International Nuclear Information System (INIS)

    1963-01-01

    A report prepared by the IAEA Secretariat and presented to the seventh session of the Agency's General Conference says that information on nuclear power costs is now rapidly moving from the domain of uncertain estimates to that of tested factual data. As more and more nuclear power stations are being built and put into operation, more information on the actual costs incurred is becoming available. This is the fourth report on nuclear power costs to be submitted to the IAEA General Conference. The report last year gave cost information on 38 nuclear power projects, 17 of which have already gone into operation. Certain significant changes in the data given last year are included-in the present report; besides, information is given on seven new plants. The report is divided into two parts, the first on recent developments and current trends in nuclear power costs and the second on the use of the cost data for economic comparisons. Both stress the fact that the margin of uncertainty in the basic data has lately been drastically reduced. At the same time, it is pointed out, some degree of uncertainty is inherent in the assumptions made in arriving at over-all generating cost figures, especially when - as is usually the case - a nuclear plant is part of an integrated power system

  6. Nuclear power in space

    International Nuclear Information System (INIS)

    Anghaie, S.

    2007-01-01

    The development of space nuclear power and propulsion in the United States started in 1955 with the initiation of the ROVER project. The first step in the ROVER program was the KIWI project that included the development and testing of 8 non-flyable ultrahigh temperature nuclear test reactors during 1955-1964. The KIWI project was precursor to the PHOEBUS carbon-based fuel reactor project that resulted in ground testing of three high power reactors during 1965-1968 with the last reactor operated at 4,100 MW. During the same time period a parallel program was pursued to develop a nuclear thermal rocket based on cermet fuel technology. The third component of the ROVER program was the Nuclear Engine for Rocket Vehicle Applications (NERVA) that was initiated in 1961 with the primary goal of designing the first generation of nuclear rocket engine based on the KIWI project experience. The fourth component of the ROVER program was the Reactor In-Flight Test (RIFT) project that was intended to design, fabricate, and flight test a NERVA powered upper stage engine for the Saturn-class lunch vehicle. During the ROVER program era, the Unites States ventured in a comprehensive space nuclear program that included design and testing of several compact reactors and space suitable power conversion systems, and the development of a few light weight heat rejection systems. Contrary to its sister ROVER program, the space nuclear power program resulted in the first ever deployment and in-space operation of the nuclear powered SNAP-10A in 1965. The USSR space nuclear program started in early 70's and resulted in deployment of two 6 kWe TOPAZ reactors into space and ground testing of the prototype of a relatively small nuclear rocket engine in 1984. The US ambition for the development and deployment of space nuclear powered systems was resurrected in mid 1980's and intermittently continued to date with the initiation of several research programs that included the SP-100, Space Exploration

  7. Nuclear power for beginners

    International Nuclear Information System (INIS)

    Croall, S.; Sempler, K.

    1979-01-01

    Witty, critically, and with expert knowledge, 'Atomic power for beginners' describes the development of nuclear power for military purposes and its 'peaceful uses' against the will of the population. Atomic power, the civil baby of the bomb is not only a danger to our lives - it is enemy to all life as all hard technologies are on which economic systems preoccupied with growth put their hopes. Therefore, 'Atomic power for beginners' does not stop at nuclear engineering but proceeds to investigate its consequences, nationally and with a view to the Third World. And since the consequences are so fatal and it is not enough to say no to nuclear power, it gives some thoughts to a better future - with soft technology and alternative production. (orig.) 891 HP/orig. 892 MKO [de

  8. Nuclear power for tomorrow

    International Nuclear Information System (INIS)

    Csik, B.J.; Konstantinov, L.V.; Dastidar, P.

    1989-09-01

    The evolution of nuclear power has established this energy source as a viable mature technology, producing at comparative costs more than 16% of the electricity generated world-wide. After outlining the current status of nuclear power, extreme future scenarios are presented, corresponding respectively to maximum penetration limited by technical-economic characteristics, and nuclear phase-out at medium term. The situation is complex and country specific. The relative perception of the importance of different factors and the compensation of advantages vs. disadvantages, or risk vs. benefits, has predominant influence. In order to proceed with an objective and realistic estimate of the future role of nuclear power worldwide, the fundamental factors indicated below pro nuclear power and against are assessed, including expected trends regarding their evolution: Nuclear safety risk; reduction to levels of high improbability but not zero risk. Reliable source of energy; improvements towards uniform standards of excellence. Economic competitiveness vs. alternatives; stabilization and possible reduction of costs. Financing needs and constraints; availability according to requirements. Environmental effects; comparative analysis with alternatives. Public and political acceptance; emphasis on reason and facts over emotions. Conservation of fossil energy resources; gradual deterioration but no dramatic crisis. Energy supply assurance; continuing concerns. Infrastructure requirements and availability; improvements in many countries due to overall development. Non-proliferation in military uses; separation of issues from nuclear power. IAEA forecasts to the year 2005 are based on current projects, national plans and policies and on prevailing trends. Nuclear electricity generation is expected to reach about 18% of total worldwide electricity generation, with 500 to 580 GW(e) installed capacity. On a longer term, to 2030, a stabilized role and place among available viable

  9. Enhancement of Training Capabilities in VVER Technology Through Establishment of VVER Training Academy

    International Nuclear Information System (INIS)

    Ilieva, M.; Miteva, R.

    2015-01-01

    Education and training (E&T) have always been key factor to the sustainability of the nuclear industry. With regard to E&T it is still the challenge to raise the interest of qualified young people of studies and professions related to nuclear technologies. CORONA Project is established to provide a special purpose structure for training and for gathering the existing and generating new knowledge in the VVER area as well as to contribute to transnational mobility and lifelong learning amongst VVER operating countries. CORONA Project consists of two parts: CORONA I (2011–2014) “Establishment of a regional centre of competence for VVER technology and Nuclear Applications”, co-financed by the EC Framework Programme 7 and CORONA II “Enhancement of training capabilities in VVER technology through establishment of VVER training academy”, co-financed by the EURATOM 2014-2015 Working programme of HORIZON 2020. The project is focused on development of training schemes for VVER nuclear professionals, subcontractors, students and for non-nuclear specialists working in support of nuclear applications as civil engineers, physical protection employees, government employees, secondary school teachers, journalists. Safety culture and soft skills training are incorporated as an integral part of all training schemes because they require continuous consideration. It is vital for the acceptance of nuclear energy by the public and for the safe performance of the nuclear installations. CORONA II project is to proceed with the development of state-of-the-art virtual training centre — CORONA Academy. This objective will be realised through networking between universities, research organizations, regulatory bodies, industry and any other organizations involved in the application of nuclear science, ionising radiation and nuclear safety. It will bring together the most experienced trainers and will allow trainees from different locations to access the needed knowledge on demand

  10. Nuclear power development status in Russia and China

    International Nuclear Information System (INIS)

    Hara, Taito

    2016-01-01

    Russia and China have clear policy for the export of nuclear reactors, and both countries conduct negotiations with the initiative of the government. In Russia, Atomenergoprom, which controls civilian nuclear power sector, is in charge, and in China, CNNC, CGN, and SPI are in charge. As for the development of new type reactors, Russian type VVER-1200 is led by NIAEP and Atomproekt, and China type CAP 1400 and Hualong-1 are led by CNNC, CGN, and SPI. The next reactor export is considered to be an improved type of the third generation. Furthermore, both countries are proceeding with the construction and planning of a variety of the fourth generation reactors. As for the power generation and construction costs of domestic nuclear reactors in each country, three countries such as South Korea, China, and Russia hold a dominant position, keeping the costs significantly lower than those in Japan, the United States, and France. In Russia and China, the governments approve government support loans of approximately 5 to 9 billion dollars per reactor for exporting reactors. For developing countries, where financial resources are limited, this system is considered to be a powerful incentive for importing nuclear reactors in combination with BOO contract system that covers from construction to operation. Japan's nuclear reactor exports are planned for the UK, Vietnam, and Turkey. In addition, a nuclear power agreement with India has been agreed in principle, and the order receipt of Japanese power plant manufacturers is expected. (A.O.)

  11. Country nuclear power profiles

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The preparation of Country Nuclear Power Profiles was initiated within the framework of the IAEA`s programme for nuclear power plant performance assessment and feedback. It responded to a need for a database and a technical document containing a description of the energy and economic situation and the primary organizations involved in nuclear power in IAEA Member States. The task was included in the IAEA`s programmes for 1993/1994 and 1995/1996. In March 1993, the IAEA organized a Technical Committee meeting to discuss the establishment of country data ``profiles``, to define the information to be included in the profiles and to review the information already available in the IAEA. Two expert meetings were convened in November 1994 to provide guidance to the IAEA on the establishment of the country nuclear profiles, on the structure and content of the profiles, and on the preparation of the publication and the electronic database. In June 1995, an Advisory Group meeting provided the IAEA with comprehensive guidance on the establishment and dissemination of an information package on industrial and organizational aspects of nuclear power to be included in the profiles. The group of experts recommended that the profiles focus on the overall economic, energy and electricity situation in the country and on its nuclear power industrial structure and organizational framework. In its first release, the compilation would cover all countries with operating power plants by the end of 1995. It was also recommended to further promote information exchange on the lessons learned from the countries engaged in nuclear programmes. For the preparation of this publication, the IAEA received contributions from the 29 countries operating nuclear power plants and Italy. A database has been implemented and the profiles are supporting programmatic needs within the IAEA; it is expected that the database will be publicly accessible in the future. Refs, figs, tabs.

  12. Country nuclear power profiles

    International Nuclear Information System (INIS)

    1998-03-01

    The preparation of Country Nuclear Power Profiles was initiated within the framework of the IAEA's programme for nuclear power plant performance assessment and feedback. It responded to a need for a database and a technical document containing a description of the energy and economic situation and the primary organizations involved in nuclear power in IAEA Member States. The task was included in the IAEA's programmes for 1993/1994 and 1995/1996. In March 1993, the IAEA organized a Technical Committee meeting to discuss the establishment of country data ''profiles'', to define the information to be included in the profiles and to review the information already available in the IAEA. Two expert meetings were convened in November 1994 to provide guidance to the IAEA on the establishment of the country nuclear profiles, on the structure and content of the profiles, and on the preparation of the publication and the electronic database. In June 1995, an Advisory Group meeting provided the IAEA with comprehensive guidance on the establishment and dissemination of an information package on industrial and organizational aspects of nuclear power to be included in the profiles. The group of experts recommended that the profiles focus on the overall economic, energy and electricity situation in the country and on its nuclear power industrial structure and organizational framework. In its first release, the compilation would cover all countries with operating power plants by the end of 1995. It was also recommended to further promote information exchange on the lessons learned from the countries engaged in nuclear programmes. For the preparation of this publication, the IAEA received contributions from the 29 countries operating nuclear power plants and Italy. A database has been implemented and the profiles are supporting programmatic needs within the IAEA; it is expected that the database will be publicly accessible in the future

  13. SCORPIO - VVER core surveillance system

    International Nuclear Information System (INIS)

    Hornaes, A.; Bodal, T.; Sunde, S.

    1998-01-01

    The Institutt for energiteknikk has developed the core surveillance system SCORPIO, which has two parallel modes of operation: the Core Follow Mode and the Predictive Mode. The main motivation behind the development of SCORPIO is to make a practical tool for reactor operators, which can increase the quality and quantity of information presented on core status and dynamic behavior. This can first of all improve plant safety, as undesired core conditions are detected and prevented. Secondly, more flexible and efficient plant operation is made possible. The system has been implemented on western PWRs, but the basic concept is applicable to a wide range of reactors including VVERs. The main differences between VVERs and typical western PWRs with respect to core surveillance requirements are outlined. The development of a VVER version of SCORPIO has been done in co-operation with the Nuclear Research Institute Rez, and industry partners in the Czech Republic. The first system is installed at Dukovany NPP, where the Site Acceptance Test was completed 6. March 1998.(author)

  14. Economics of nuclear power

    International Nuclear Information System (INIS)

    Bupp, I.C.; Derian, J.C.; Donsimoni, M.P.; Treitel, R.

    1975-01-01

    Present trends in nuclear reactor costs are interpreted as the economic result of a fundamental debate regarding the social acceptability of nuclear power. Rising capital costs for nuclear power plants are evaluated through statistical analysis of time-related factors, characteristics of licensing and construction costs, physical characteristics of reactors, and geographic and site-related factors. Conclusions are drawn regarding the impact of social acceptability on reactor costs, engineering estimates of future costs, and the possibility of increased potential relative competitiveness for coal-fueled plants. 7 references. (U.S.)

  15. The reality of nuclear power

    International Nuclear Information System (INIS)

    Murphy, D.

    1979-01-01

    The following matters are discussed in relation to the nuclear power programmes in USA and elsewhere: siting of nuclear power plants in relation to a major geological fault; public attitudes to nuclear power; plutonium, radioactive wastes and transfrontier contamination; radiation and other hazards; economics of nuclear power; uranium supply; fast breeder reactors; insurance of nuclear facilities; diversion of nuclear materials and weapons proliferation; possibility of manufacture of nuclear weapons by developing countries; possibility of accidents on nuclear power plants in developing countries; radiation hazards from use of uranium ore tailings; sociological alternative to use of nuclear power. (U.K.)

  16. NUCLEAR POWER PLANT

    Science.gov (United States)

    Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

    1963-05-14

    A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

  17. Nuclear power prospects

    International Nuclear Information System (INIS)

    Staebler, K.

    1994-01-01

    The technical, economic and political prospects of nuclear power are described with regard to ecological aspects. The consensus talks, which failed in spite of the fact that they were stripped of emotional elements and in spite of major concessions on the part of the power industry, are discussed with a view to the political and social conditions. (orig.) [de

  18. The nuclear power alternative

    International Nuclear Information System (INIS)

    Blix, H.

    1989-04-01

    The Director General of the IAEA stressed the need for energy policies and other measures which would help to slow and eventually halt the present build-up of carbon dioxide, methane and other so-called greenhouse gases, which are held to cause global warming. He urged that nuclear power and various other sources of energy, none of which contribute to global warming, should not be seen as alternatives, but should all be used to counteract the greenhouse effect. He pointed out that the commercially used renewable energies, apart from hydropower, currently represent only 0.3% of the world's energy consumption and, by contrast, the 5% of the world's energy consumption coming from nuclear power is not insignificant. Dr. Blix noted that opposition for nuclear power stems from fear of accidents and concern about the nuclear wastes. But no generation of electricity, whether by coal, hydro, gas or nuclear power, is without some risk. He emphasized that safety can never be a static concept, and that many new measures are being taken by governments and by the IAEA to further strengthen the safety of nuclear power

  19. Future nuclear power generation

    International Nuclear Information System (INIS)

    Mosbah, D.S.; Nasreddine, M.

    2006-01-01

    The book includes an introduction then it speaks about the options to secure sources of energy, nuclear power option, nuclear plants to generate energy including light-water reactors (LWR), heavy-water reactors (HWR), advanced gas-cooled reactors (AGR), fast breeder reactors (FBR), development in the manufacture of reactors, fuel, uranium in the world, current status of nuclear power generation, economics of nuclear power, nuclear power and the environment and nuclear power in the Arab world. A conclusion at the end of the book suggests the increasing demand for energy in the industrialized countries and in a number of countries that enjoy special and economic growth such as China and India pushes the world to search for different energy sources to insure the urgent need for current and anticipated demand in the near and long-term future in light of pessimistic and optimistic outlook for energy in the future. This means that states do a scientific and objective analysis of the currently available data for the springboard to future plans to secure the energy required to support economy and welfare insurance.

  20. VVER Reactor Safety in Eastern Europe and Former Soviet Union

    Science.gov (United States)

    Papadopoulou, Demetra

    2012-02-01

    VVER Soviet-designed reactors that operate in Eastern Europe and former Soviet republics have heightened international concern for years due to major safety deficiencies. The governments of countries with VVER reactors have invested millions of dollars toward improving the safety of their nuclear power plants. Most of these reactors will continue to operate for the foreseeable future since they provide urgently-needed electrical power. Given this situation, this paper assesses the radiological consequences of a major nuclear accident in Eastern Europe. The paper also chronicles the efforts launched by the international nuclear community to improve the safety of the reactors and notes the progress made so far through extensive collaborative efforts in Armenia, Bulgaria, the Czech Republic, Hungary, Kazakhstan, Lithuania, Russia, Slovakia, and Ukraine to reduce the risks of nuclear accidents. Western scientific and technical staff collaborated with these countries to improve the safety of their reactor operations by strengthening the ability of the regulator to perform its oversight function, installing safety equipment and technologies, investing time in safety training, and working diligently to establish an enduring safety culture. Still, continued safety improvement efforts are necessary to ensure safe operating practices and achieve timely phase-out of older plants.

  1. Physics and nuclear power

    International Nuclear Information System (INIS)

    Buttery, N E

    2008-01-01

    Nuclear power owes its origin to physicists. Fission was demonstrated by physicists and chemists and the first nuclear reactor project was led by physicists. However as nuclear power was harnessed to produce electricity the role of the engineer became stronger. Modern nuclear power reactors bring together the skills of physicists, chemists, chemical engineers, electrical engineers, mechanical engineers and civil engineers. The paper illustrates this by considering the Sizewell B project and the role played by physicists in this. This covers not only the roles in design and analysis but in problem solving during the commissioning of first of a kind plant. Looking forward to the challenges to provide sustainable and environmentally acceptable energy sources for the future illustrates the need for a continuing synergy between physics and engineering. This will be discussed in the context of the challenges posed by Generation IV reactors

  2. Nuclear power in perspective

    International Nuclear Information System (INIS)

    Ringwood, A.E.

    1980-01-01

    The nuclear power debate hinges upon three major issues: radioactive waste disposal, reactor safety and proliferation. An alternative strategy for waste disposal is advocated which involves disposing of the radwaste (immobilized in SYNROC, a titanate ceramic waste form) in deep (4 km) drill-holes widely dispersed throughout the entire country. It is demonstrated that this strategy possesses major technical (safety) advantages over centralized, mined repositories. The comparative risks associated with coal-fired power generation and with the nuclear fuel cycle have been evaluated by many scientists, who conclude that nuclear power is far less hazardous. Considerable improvements in reactor design and safety are readily attainable. The nuclear industry should be obliged to meet these higher standards. The most hopeful means of limiting proliferation lies in international agreements, possibly combined with international monitoring and control of key segments of the fuel cycle, such as reprocessing

  3. LDC nuclear power: Egypt

    International Nuclear Information System (INIS)

    Selim, M.E.S.

    1982-01-01

    This chapter reviews the evolution of Egypt's nuclear program, the major factors that influenced the successive series of nuclear decisions, and the public debate over the far-reaching program attempted by the late President Anwar El-Sadat. Egypt's program is important, not only because it was the first Arab country to enter the nuclear age, but because it is an ambitious program that includes the installation of eight reactors at a time when many countries are reducing their commitment to nuclear power. Major obstacles remain in terms of human, organizational, and natural resource constraints. 68 references, 1 table

  4. Nuclear power economics

    Energy Technology Data Exchange (ETDEWEB)

    Emsley, Ian; Cobb, Jonathan [World Nuclear Association, London (United Kingdom)

    2017-04-15

    Many countries recognize the substantial role which nuclear power has played in providing energy security of supply, reducing import dependence and reducing greenhouse gas and polluting emissions. Nevertheless, as such considerations are far from being fully accounted for in liberalized or deregulated power markets, nuclear plants must demonstrate their viability in these markets on commercial criteria as well as their lifecycle advantages. Nuclear plants are operating more efficiently than in the past and unit operating costs are low relative to those of alternative generating technologies. The political risk facing the economic functioning of nuclear in a number of countries has increased with the imposition of nuclear-specific taxes that in some cases have deprived operators of the economic incentive to continue to operate existing plants.

  5. Nuclear power economics

    International Nuclear Information System (INIS)

    Emsley, Ian; Cobb, Jonathan

    2017-01-01

    Many countries recognize the substantial role which nuclear power has played in providing energy security of supply, reducing import dependence and reducing greenhouse gas and polluting emissions. Nevertheless, as such considerations are far from being fully accounted for in liberalized or deregulated power markets, nuclear plants must demonstrate their viability in these markets on commercial criteria as well as their lifecycle advantages. Nuclear plants are operating more efficiently than in the past and unit operating costs are low relative to those of alternative generating technologies. The political risk facing the economic functioning of nuclear in a number of countries has increased with the imposition of nuclear-specific taxes that in some cases have deprived operators of the economic incentive to continue to operate existing plants.

  6. Nuclear power in Japan

    International Nuclear Information System (INIS)

    Kishida, J.

    1990-01-01

    The Japanese movement against nuclear energy reached a climax in its upsurge in 1988 two years after the Chernobyl accident. At the outset of that year, this trend was triggered by the government acknowledgement that the Tokyo market was open to foods contaminated by the fallout from Chernobyl. Anti-nuclear activists played an agitating role and many housewives were persuaded to join them. Among many public opinion surveys conducted at that time by newspapers and broadcasting networks, I would like to give you some figures of results from the poll carried out by NHK: Sixty percent of respondents said that nuclear power 'should be promoted', either 'vigorously' 7 or 'carefully' 53%). Sixty-six percent doubted the 'safety of nuclear power', describing it as either 'very dangerous' 20%) or 'rather dangerous' (46%). Only 27% said it was 'safe'. In other words, those who acknowledged the need for nuclear power were almost equal in number with those who found it dangerous. What should these figures be taken to mean? I would take note of the fact that nearly two-thirds of valid responses were in favor of nuclear power even at the time when public opinion reacted most strongly to the impact of the Chernobyl accident. This apparently indicates that the majority of the Japanese people are of the opinion that they would 'promote nuclear power though it is dangerous' or that they would 'promote it, but with the understanding that it is dangerous'. But the anti-nuclear movement is continuing. It remains a headache for both the government and the electric utilities. But we can regard the anti-nuclear movement in Japan as not so serious as that faced by other industrial nations

  7. Nuclear power in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Kishida, J [Japan Research Institute, Ltd., Tokyo (Japan)

    1990-07-01

    The Japanese movement against nuclear energy reached a climax in its upsurge in 1988 two years after the Chernobyl accident. At the outset of that year, this trend was triggered by the government acknowledgement that the Tokyo market was open to foods contaminated by the fallout from Chernobyl. Anti-nuclear activists played an agitating role and many housewives were persuaded to join them. Among many public opinion surveys conducted at that time by newspapers and broadcasting networks, I would like to give you some figures of results from the poll carried out by NHK: Sixty percent of respondents said that nuclear power 'should be promoted', either 'vigorously' 7 or 'carefully' 53%). Sixty-six percent doubted the 'safety of nuclear power', describing it as either 'very dangerous' 20%) or 'rather dangerous' (46%). Only 27% said it was 'safe'. In other words, those who acknowledged the need for nuclear power were almost equal in number with those who found it dangerous. What should these figures be taken to mean? I would take note of the fact that nearly two-thirds of valid responses were in favor of nuclear power even at the time when public opinion reacted most strongly to the impact of the Chernobyl accident. This apparently indicates that the majority of the Japanese people are of the opinion that they would 'promote nuclear power though it is dangerous' or that they would 'promote it, but with the understanding that it is dangerous'. But the anti-nuclear movement is continuing. It remains a headache for both the government and the electric utilities. But we can regard the anti-nuclear movement in Japan as not so serious as that faced by other industrial nations.

  8. Steps to nuclear power

    International Nuclear Information System (INIS)

    1975-01-01

    The recent increase in oil prices will undoubtedly cause the pace at which nuclear power is introduced in developing countries to quicken in the next decade, with many new countries beginning to plan nuclear power programmes. The guidebook is intended for senior government officials, policy makers, economic and power planners, educationalists and economists. It assumes that the reader has relatively little knowledge of nuclear power systems or of nuclear physics but does have a general technical or management background. Nuclear power is described functionally from the point of view of an alternative energy source in power system expansion. The guidebook is based on an idealized approach. Variations on it are naturally possible and will doubtless be necessary in view of the different organizational structures that already exist in different countries. In particular, some countries may prefer an approach with a stronger involvement of their Atomic Energy Commission or Authority, for which this guidebook has foreseen mainly a regulatory and licensing role. It is intended to update this booklet as more experience becomes available. Supplementary guidebooks will be prepared on certain major topics, such as contracting for fuel supply and fuel cycle requirements, which the present book does not go into very deeply

  9. Nuclear power generating costs

    International Nuclear Information System (INIS)

    Srinivasan, M.R.; Kati, S.L.; Raman, R.; Nanjundeswaran, K.; Nadkarny, G.V.; Verma, R.S.; Mahadeva Rao, K.V.

    1983-01-01

    Indian experience pertaining to investment and generation costs of nuclear power stations is reviewed. The causes of investment cost increases are analysed and the increases are apportioned to escalation, design improvements and safety related adders. The paper brings out the fact that PHWR investment costs in India compare favourably with those experienced in developed countries in spite of the fact that the programme and the unit size are relatively much smaller in India. It brings out that in India at current prices a nuclear power station located over 800 km from coal reserves and operating at 75% capacity factor is competitive with thermal power at 60% capacity factor. (author)

  10. Commercial nuclear power 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-28

    This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

  11. Nuclear power industry

    International Nuclear Information System (INIS)

    1999-01-01

    This press dossier presented in Shanghai (China) in April 1999, describes first the activities of the Framatome group in the people's republic of China with a short presentation of the Daya Bay power plant and of the future Ling Ao project, and with a description of the technological cooperation with China in the nuclear domain (technology transfers, nuclear fuels) and in other industrial domains (mechanics, oil and gas, connectors, food and agriculture, paper industry etc..). The general activities of the Framatome group in the domain of energy (nuclear realizations in France, EPR project, export activities, nuclear services, nuclear fuels, nuclear equipments, industrial equipments) and of connectors engineering are presented in a second and third part with the 1998 performances. (J.S.)

  12. Abuse of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Hill, J [UKAEA

    1976-09-01

    This paper reproduces an address by Sir John Hill, Chairman of the United Kingdom Atomic Energy Authority, at a conference in London organised by the Financial Times in July 1976. Actions that, in the author's view, could be regarded as constituting abuse of nuclear power are first summarised, and the various aspects of the use and abuse of nuclear power are discussed. The author considers that achieving the maximum degree of acceptance of the Non-Proliferation Treaty is the most important political objective in nuclear power, but considers that nuclear terrorism would be abortive and that, so far as the UK is concerned, the present precautions are adequate and will remain so. It is considered that much abuse of nuclear power arises from the prevalence of its critics, particularly with reference to Pu hazards, the health of nuclear employees, and possible damage to the health of the public. The Pu problem is considered to be far more emotive than rational. The possibility of lung cancer and leukaemia is discussed. It is concluded that atomic energy is one of the best of industries in which to work, both from the health and interest points of view.

  13. Nuclear power plant safety

    International Nuclear Information System (INIS)

    Otway, H.J.

    1974-01-01

    Action at the international level will assume greater importance as the number of nuclear power plants increases, especially in the more densely populated parts of the world. Predictions of growth made prior to October 1973 [9] indicated that, by 1980, 14% of the electricity would be supplied by nuclear plants and by the year 2000 this figure would be about 50%. This will make the topic of international co-operation and standards of even greater importance. The IAEA has long been active in providing assistance to Member States in the siting design and operation of nuclear reactors. These activities have been pursued through advisory missions, the publication of codes of practice, guide books, technical reports and in arranging meetings to promote information exchange. During the early development of nuclear power, there was no well-established body of experience which would allow formulation of internationally acceptable safety criteria, except in a few special cases. Hence, nuclear power plant safety and reliability matters often received an ad hoc approach which necessarily entailed a lack of consistency in the criteria used and in the levels of safety required. It is clear that the continuation of an ad hoc approach to safety will prove inadequate in the context of a world-wide nuclear power industry, and the international trade which this implies. As in several other fields, the establishment of internationally acceptable safety standards and appropriate guides for use by regulatory bodies, utilities, designers and constructors, is becoming a necessity. The IAEA is presently planning the development of a comprehensive set of basic requirements for nuclear power plant safety, and the associated reliability requirements, which would be internationally acceptable, and could serve as a standard frame of reference for nuclear plant safety and reliability analyses

  14. Nuclear power in Germany

    International Nuclear Information System (INIS)

    Beckurts, K.H.

    1985-01-01

    On the occasion of the retirement of the Editor-in-chief of 'atomwirtschaft', the author gave a keynote speech on the development of nuclear power in the Federal Republic of Germany at the headquarters of the Handelsblatt Verlag in Duesseldorf on October 30, 1984. He subdivided the period under discussion into five phases, the first of which comprises the 'founding years' of 1955 to 1960. This was the time when activities in nuclear research and nuclear technology in Germany, which were permitted again in mid-1955, began with the establishment of the national research centers, the first Atomic Power Program, the promulgation of the Atomic Energy Act, the foundation of government organizations, including the Federal Ministry for Atomic Energy, etc. In the second phase, between 1960 and 1970, a solid foundation was laid for the industrial peaceful uses of nuclear power in the construction of the first LWR experimental nuclear power stations, the first successful export contracts, the beginnings of the first nuclear fuel cycle plants, such as the WAK reprocessing plant, the Asse experimental repository, the Almelo agreement on centrifuge enrichment. The third phase, between 1970 and 1975, was a period of euphoria, full of programs and forecasts of a tremendous boom in nuclear generating capacities, which were further enhanced by the 1973 oil squeeze. In 1973 and 1974, construction permits for ten nuclear power plants were applied for. The fourth phase, between 1975 and 1980, became a period of crisis. The fifth phase, the eighties, give rise to hope for a return to reason. (orig./UA) [de

  15. Nuclear power safety

    International Nuclear Information System (INIS)

    1991-11-01

    This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

  16. Nuclear power's burdened future

    International Nuclear Information System (INIS)

    Flavin, C.

    1987-01-01

    Although governments of the world's leading nations are reiterating their faith in nuclear power, Chernobyl has brought into focus the public's overwhelming feeling that the current generation of nuclear technology is simple not working. Despite the drastic slowdown, however, the global nuclear enterprise is large. As of mid-1986, the world had 366 nuclear power plants in operation, with a generating capacity of 255,670 MW. These facilities generate about 15% of the world's electricity, ranging from 65% in France to 31% in West Germany, 23% in Japan, 16% in the United States, 10% in the Soviet Union, and non in most developing nations. Nuclear development is clearly dominated by the most economically powerful and technologically advanced nations. The United States, France, the Soviet Union, Japan, and West Germany has 72% of the world's generating capacity and set the international nuclear pace. The reasons for scaling back nuclear programs are almost as diverse as the countries themselves. High costs, slowing electricity demand growth, technical problems, mismanagement, and political opposition have all had an effect. Yet these various factors actually form a complex web of inter-related problems. For example, rising costs usually represent some combination of technical problems and mismanagement, and political opposition often occurs because of safety concerns or rising costs. 13 references

  17. Nuclear power: Europa report

    International Nuclear Information System (INIS)

    Anon.

    2004-01-01

    Last year, 2003, nuclear power plants were available for energy supply, respectively, in 18 countries all over Europe. In 8 of the 15 member countries of the European Union (EU-15) nuclear power plants have been operation. In 7 of the 13 EU Candidate Countries (incl. Turkey) nuclear energy was used for power production. A total of 208 plants with an aggregate net capacity of 171 031 MWe and an aggregate gross capacity of 180 263 MWe were in operation at the end of 2003. No unit reached first criticality in 2003 or was connected to the grid. The unit Calder Hall 1 to Calder Hall 4 have been permanently shut down in Great Britain due to economical reasons and an earlier decision. In Germany the NPP Stade was closed. The utility E.ON has decided to shut down the plant due to the efforts of the liberalisation of the electricity markets. Last year, 8 plants were under construction in Romania (1), Russia (3), Slovakia (2 - suspended), and the Ukraine (2), that is only in East European Countries. The Finnish parliament approved plans for the construction of the country's fifth nuclear power reactor by a majority of 107 votes to 92. The consortium led by Framatome ANP was awarded the contract to build the new nuclear power plant (EPR, 1 600 MW) in Olkiluoto. In eight countries of the European Union 136 nuclear power plants have been operated with an aggregate gross capacity of 127 708 MWe and an aggregate net capacity of 121 709 MWe. Net electricity production in 2003 in the EU amounts to approx. 905 TWh gross, which means a share of about 33 per cent of the total production in the whole EU. Shares of nuclear power differ widely among the operator countries. They reach 80% in Lithuania, 78% in France, 57% in the Slovak Republic, 57% in Belgium, and 46% in the Ukraine. Nuclear power also provides a noticeable share in the electricity supply of countries, which operate no own nuclear power plants, e.g. Italy, Portugal, and Austria. (orig.)

  18. Nuclear power. Europe report

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    Last year, 2001, nuclear power plants were available for energy supply, respectively, in 18 countries all over Europe. In 8 of the 15 member countries of the European Union nuclear power plants have been in operation. In 7 of the 13 EU Candidate Countries nuclear energy was used for power production. A total of 216 plants with an aggregate net capacity of 171 802 MWe and an aggregate gross capacity of 181 212 MWe were in operation. One unit, i.e. Volgodonsk-1 in Russia went critical for the first time and started test operation after having been connected to the grid. Volgodonsk-1 adds about 1 000 MWe (gross) nd 953 MWe (net) to the electricity production capacity. The operator of the Muehlheim-Kaerlich NPP field an application to decommission and dismantle the plant; this plant was only 13 months in operation and has been shut down since 1988 for legal reasons. Last year, 10 plants were under construction in Romania (1), Russia (4), Slovakia (2), the Czech Republic (1) and the Ukraine (2), that is only in East European Countries. In eight countries of the European Union 143 nuclear power plants have been operated with an aggregate gross capacity of 128 758 MWe and an aggregate net capacity of 122 601 MWe. Net electricity production in 2001 in the EU amounts to approx. 880.3 TWh gross, which means a share of 33,1 per cent of the total production in the whole EU. Shares of nuclear power differ widely among the operator countries. The reach 75.6% in France, 74.2% in Lithuania, 58.2% in Belgium, 53.2% in the Slovak Republic, and 47.4% in the Ukraine. Nuclear power also provides a noticeable share in the electricity supply of countries, which operate no own nuclear power plants, e.g. Italy, Portugal, and Austria. On May 24th, 2002 the Finnish Parliament voted for the decision in principle to build a fifth nuclear power plant in the country. This launches the next stage in the nuclear power plant project. The electric output of the plant unit will be 1000-1600 MW

  19. France without nuclear power

    International Nuclear Information System (INIS)

    Barre, B.; Charmant, A.; Devezeaux, J.G.; Ladoux, N.; Vielle, M.

    1995-01-01

    As environmental issues (particularly questions associated with the greenhouse effect) become a matter of increasing current concern, the French nuclear power programme can, in retrospect, be seen to have had a highly positive impact upon emissions of atmospheric pollutants. The most spectacular effect of this programme was the reduction of carbon dioxide emissions from 530 million tonnes per annum in 1973 to 387 million tonnes per annum today. Obviously, this result cannot be considered in isolation from the economic consequences of the nuclear power programme, which have been highly significant.The most obvious consequence of nuclear power has been the production of cheap electricity, while a further consequence has been the stability of electricity prices resulting from the increasing self-sufficiency of France in energy supplies (from 22% in 1973 to 49.% in 1992). Moreover, French nuclear industry exports. In 1993, 61.7 TW·h from nuclear production were exported, which contributed F.Fr. 14.2 billion to the credit side of the balance of payment. For the same year, Framatome exports are assessed at about F.Fr. 2 billion, corresponding to manufacturing and erection of heavy components, and maintenance services. Cogema, the French nuclear fuel operator, sold nuclear materials and services for F.Fr. 9.3 billion. Thus, nuclear activities contributed more than F.Fr. 25 billion to the balance of payment. Therefore, a numerical assessment of the macroeconomic impact of the nuclear power programme is essential for any accurate evaluation of the environmental consequences of that programme. For this assessment, which is presented in the paper, the Micro-Melodie macroeconomic and energy supply model developed by the Commissariat a l'energie atomique has been used. (author). 6 refs, 4 figs, 1 tab

  20. Nuclear Power after Fukushima

    International Nuclear Information System (INIS)

    Bigot, B.

    2011-01-01

    On 11 March 2011 Japan suffered an earthquake of very high magnitude, followed by a tsunami that left thousands dead in the Sendai region, the main consequence of which was a major nuclear disaster at the Fukushima power station. The accident ranked at the highest level of severity on the international scale of nuclear events, making it the biggest since Chernobyl in 1986. It is still impossible to gauge the precise scope of the consequences of the disaster, but it has clearly given rise to the most intense renewed debates on the nuclear issue. Futuribles echoes this in the 'Forum' feature of this summer issue which is entirely devoted to energy questions. Bernard Bigot, chief executive officer of the technological research organization CEA, looks back on the Fukushima disaster and what it changes (or does not change) so far as the use of nuclear power is concerned, particularly in France. After recalling the lessons of earlier nuclear disasters, which led to the development of the third generation of power stations, he reminds us of the currently uncontested need to free ourselves from dependence on fossil fuels, which admittedly involves increased use of renewables, but can scarcely be envisaged without nuclear power. Lastly, where the Fukushima disaster is concerned, Bernard Bigot shows how it was, in his view, predominantly the product of a management error, from which lessons must be drawn to improve the safety conditions of existing or projected power stations and enable the staff responsible to deliver the right response as quickly as possible when an accident occurs. In this context and given France's high level of dependence on nuclear power, the level of use of this energy source ought not to be reduced on account of the events of March 2011. (author)

  1. France without nuclear power

    International Nuclear Information System (INIS)

    Charmant, A.; Devezeaux, J.G.; Ladoux, N.; Vielle, M.

    1991-01-01

    As coal production declined and France found herself in a condition of energy dependency, the country decided to turn to nuclear power and a major construction program was undertaken in 1970. The consequences of this step are examined in this article, by imagining where France would be without its nuclear power. At the end of the sixties, fuel-oil incontestably offered the cheapest way of producing electricity; but the first petroleum crisis was to upset the order of economic performance, and coal then became the more attractive fuel. The first part of this article therefore presents coal as an alternative to nuclear power, describing the coal scenario first and then comparing the relative costs of nuclear and coal investment strategies and operating costs (the item that differs most is the price of the fuel). The second part of the article analyzes the consequences this would have on the electrical power market, from the supply and demand point of view, and in terms of prices. The third part of the article discusses the macro-economic consequences of such a step: the drop in the level of energy dependency, increased costs and the disappearance of electricity exports. The article ends with an analysis of the environmental consequences, which are of greater and greater concern today. The advantage here falls very much in favor of nuclear power, if we judge by the lesser emissions of sulfur dioxide, nitrogen oxides and especially carbon dioxide. 22 refs.; 13 figs.; 10 tabs

  2. Reviewing nuclear power

    International Nuclear Information System (INIS)

    Robinson, Colin

    1990-01-01

    The UK government has proposed a review of the prospects for nuclear power as the Sizewell B pressurized water reactor project nears completion in 1994. However, a delay in the completion of Sizewell B or a change of government could put off the review for some years beyond the mid 1990s. Anticipating, though, that such a review will eventually take place, issues which it should consider are addressed. Three broad categories of possible benefit claimed for nuclear power are examined. These are that nuclear power contributes to the security of energy supply, that it provides protection against long run fossil fuel price increases and that it is a means of mitigating the greenhouse effect. Arguments are presented which cost doubt over the reality of these benefits. Even if these benefits could be demonstrated, they would have to be set against the financial, health and accident costs attendant on nuclear power. It is concluded that the case may be made that nuclear power imposes net costs on society that are not justified by the net benefits conferred. Some comments are made on how a government review, if and when it takes place, should be conducted. (UK)

  3. Dry spent fuel storage facility at Kozloduy Nuclear Power Plant

    International Nuclear Information System (INIS)

    Goehring, R.; Stoev, M.; Davis, N.; Thomas, E.

    2004-01-01

    The Dry Spent Fuel Storage Facility (DSF) is financed by the Kozloduy International Decommissioning Support Fund (KIDSF) which is managed by European Bank for Reconstruction and Development (EBRD). On behalf of the Employer, the Kozloduy Nuclear Power Plant, a Project Management Unit (KPMU) under lead of British Nuclear Group is managing the contract with a Joint Venture Consortium under lead of RWE NUKEM mbH. The scope of the contract includes design, manufacturing and construction, testing and commissioning of the new storage facility for 2800 VVER-440 spent fuel assemblies at the KNPP site (turn-key contract). The storage technology will be cask storage of CONSTOR type, a steel-concrete-steel container. The licensing process complies with the national Bulgarian regulations and international rules. (authors)

  4. Validation of containment thermal hydraulic computer codes for VVER reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jiri Macek; Lubomir Denk [Nuclear Research Institute Rez plc Thermal-Hydraulic Analyses Department CZ 250 68 Husinec-Rez (Czech Republic)

    2005-07-01

    Full text of publication follows: The Czech Republic operates 4 VVER-440 units, two VVER-1000 units are being finalized (one of them is undergoing commissioning). Thermal-hydraulics Department of the Nuclear Research Institute Rez performs accident analyses for these plants using a number of computer codes. To model the primary and secondary circuits behaviour the system codes ATHLET, CATHARE, RELAP, TRAC are applied. Containment and pressure-suppression system are modelled with COCOSYS and MELCOR codes, the reactor power calculations (point and space-neutron kinetics) are made with DYN3D, NESTLE and CDF codes (FLUENT, TRIO) are used for some specific problems.An integral part of the current Czech project 'New Energy Sources' is selection of a new nuclear source. Within this and the preceding projects financed by the Czech Ministry of Industry and Trade and the EU PHARE, the Department carries and has carried out the systematic validation of thermal-hydraulic and reactor physics computer codes applying data obtained on several experimental facilities as well as the real operational data. One of the important components of the VVER 440/213 NPP is its containment with pressure suppression system (bubble condenser). For safety analyses of this system, computer codes of the type MELCOR and COCOSYS are used in the Czech Republic. These codes were developed for containments of classic PWRs or BWRs. In order to apply these codes for VVER 440 systems, their validation on experimental facilities must be performed.The paper provides concise information on these activities of the NRI and its Thermal-hydraulics Department. The containment system of the VVER 440/213, its functions and approaches to solution of its safety is described with definition of acceptance criteria. A detailed example of the containment code validation on EREC Test facility (LOCA and MSLB) and the consequent utilisation of the results for a real NPP purposes is included. An approach to

  5. The politics of nuclear power

    International Nuclear Information System (INIS)

    Elliott, D.

    1978-01-01

    The contents of the book are: introduction; (part 1, the economy of nuclear power) nuclear power and the growth of state corporatism, ownership and control - the power of the multi-nationals, economic and political goals - profit or control, trade union policy and nuclear power; (part 2, nuclear power and employment) nuclear power and workers' health and safety, employment and trade union rights, jobs, energy and industrial strategy, the alternative energy option; (part 3, political strategies) the anti-nuclear movement, trade unions and nuclear power; further reading; UK organisations. (U.K.)

  6. Nuclear power and other energy

    International Nuclear Information System (INIS)

    Doederlein, J.M.

    1975-01-01

    A comparison is made between nuclear power plants, gas-fuelled thermal power plants and oil-fired thermal power plants with respect to health factors, economy, environment and resource exploitation, with special reference to the choice of power source to supplement Norwegian hydroelectric power. Resource considerations point clearly to nuclear power, but, while nuclear power has an overall economic advantage, the present economic situation makes its heavy capital investment a disadvantage. It is maintained that nuclear power represents a smaller environmental threat than oil or gas power. Finally, statistics are given showing that nuclear power involves smaller fatality risks for the population than many other hazards accepted without question. (JIW)

  7. PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation

    Energy Technology Data Exchange (ETDEWEB)

    Hadad, Kamal; Esmaeili-Sanjavanmareh, Mansour [Shiraz Univ., Shiraz (Iran, Islamic Republic of). Dept. of Nuclear Engineering

    2017-05-15

    PCTRAN capability to simulate a large break loss of coolant accident concurrent with the loss of offsite power in Bushehr Nuclear Power Plant is enhanced and investigated. Following the correction of the accident scenario for Bushehr nuclear power plant in PCTRAN, simulation results are compared with the final safety assessment report of that plant. As a result, the primary loop thermal hydraulics parameters including pressure, total flow rates, leakage flow rates and reactor power are in a good agreement with the reference data. Hot and cold leg temperature variations have the same trends as reference data but have a maximum of 80 C disagreement at the transient initiation. The reason for this disagreement is explained and its adjustment is discussed. Improvements of PCTRAN simulator are mainly due to enhancing user control for atmospheric steam dump valve, containment pressure and emergency core cooling systems which are thoroughly described in this paper.

  8. Nuclear power production costs

    International Nuclear Information System (INIS)

    Erramuspe, H.J.

    1988-01-01

    The economic competitiveness of nuclear power in different highly developed countries is shown, by reviewing various international studies made on the subject. Generation costs (historical values) of Atucha I and Embalse Nuclear Power Plants, which are of the type used in those countries, are also included. The results of an international study on the economic aspects of the back end of the nuclear fuel cycle are also reviewed. This study shows its relatively low incidence in the generation costs. The conclusion is that if in Argentina the same principles of economic racionality were followed, nuclear energy would be economically competitive in the future, as it is today. This is of great importance in view of its almost unavoidable character of alternative source of energy, and specially since we have to expect an important growth in the consumption of electricity, due to its low share in the total consumption of energy, and the low energy consumption per capita in Argentina. (Author) [es

  9. Environment and nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    Aimed at the general public this leaflet, one of a series prepared by AEA Technology, on behalf of the British Nuclear Industry Forum, seeks to put the case for generating electricity to meet United Kingdom and world demand using nuclear power. It examines the environmental problems linked to the use of fossil-fuels in power stations and other uses, such as the Greenhouse Effect. Problems associated with excess carbon dioxide emissions are also discussed, such as acid rain, the effects of deforestation and lead in petrol. The role of renewable energy sources is mentioned briefly. The leaflet also seeks to reassure on issues such as nuclear waste managements and the likelihood and effects of nuclear accidents. (UK)

  10. Thai Nuclear Power Program

    International Nuclear Information System (INIS)

    Namwong, Ratanachai

    2011-01-01

    The Electricity Generating Authority of Thailand (EGAT), the main power producer in Thailand, was first interested in nuclear power as an electricity option in 1967 when the electricity demand increased considerably for the first time as a result of the economic and industrial growth. Its viability had been assessed several times during the early seventies in relation to the changing factors. Finally in the late 1970s, the proceeding with nuclear option was suspended for a variety of reasons, for instance, public opposition, economic repercussion and the uncovering of the indigenous petroleum resources. Nonetheless, EGAT continued to maintain a core of nuclear expertise. During 1980s, faced with dwindling indigenous fossil fuel resources and restrictions on the use of further hydro as an energy source, EGAT had essentially reconsidered introducing nuclear power plants to provide a significant fraction to the long term future electricity demand. The studies on feasibility, siting and environmental impacts were conducted. However, the project was never implemented due to economics crisis in 1999 and strong opposition by environmentalists and activists groups. The 1986 Chernobyl disaster was an important cause. After a long dormant period, the nuclear power is now reviewed as one part of the solution for future energy supply in the country. Thailand currently relies on natural gas for 70 percent of its electricity, with the rest coming from oil, coal and hydro-power. One-third of the natural gas consumed in Thailand is imported, mainly from neighbouring Myanmar. According to Power Development Plan (PDP) 2007 rev.2, the total installed electricity capacity will increase from 28,530.3 MW in 2007 to 44,281 MW by the end of plan in 2021. Significantly increasing energy demand, concerns over climate change and dependence on overseas supplies of fossil fuels, all turn out in a favor of nuclear power. Under the current PDP (as revised in 2009), two 1,000- megawatt nuclear

  11. Sequence of decommissioning of the main equipment in a central type VVER 440 V-230

    International Nuclear Information System (INIS)

    Andres, E.; Garcia Ruiz, R.

    2014-01-01

    IBERDROLA Ingenieria y Construccion S.A.U., leader of consortium with Empresarios Agrupados and INDRA, has developed the Basic Engineering for the decommissioning of contaminated systems and building of a VVER 440 V-230 Nuclear Power Plant, establishing the sequence and methodology for the main equipment fragmentation. For that, it has been designed dry and wet cutting zones to be set up in the area where steam generators, main cooling pumps and pressurizer are located; these components will be dismantled previously. (Author)

  12. Nuclear Power Plants (Rev.)

    Energy Technology Data Exchange (ETDEWEB)

    Lyerly, Ray L.; Mitchell III, Walter [Southern Nuclear Engineering, Inc.

    1973-01-01

    Projected energy requirements for the future suggest that we must employ atomic energy to generate electric power or face depletion of our fossil-fuel resources—coal, oil, and gas. In short, both conservation and economic considerations will require us to use nuclear energy to generate the electricity that supports our civilization. Until we reach the time when nuclear power plants are as common as fossil-fueled or hydroelectric plants, many people will wonder how the nuclear plants work, how much they cost, where they are located, and what kinds of reactors they use. The purpose of this booklet is to answer these questions. In doing so, it will consider only central station plants, which are those that provide electric power for established utility systems.

  13. Pulsed nuclear power plant

    International Nuclear Information System (INIS)

    David, C.V.

    1986-01-01

    This patent describes a nuclear power plant. This power plant consists of: 1.) a cavity; 2.) a detonatable nuclear device in a central region of the cavity; 3.) a working fluid inside of the cavity; 4.) a method to denote a nuclear device inside of the cavity; 5.) a mechanical projection from an interior wall of the cavity for recoiling to absorb a shock wave produced by the detonation of the nuclear device and thereby protecting the cavity from damage. A plurality of segments defines a shell within the cavity and a plurality of shock absorbers, each connecting a corresponding segment to a corresponding location on the wall of the cavity. Each of these shock absorbers regulate the recoil action of the segments; and 6.) means for permitting controlled extraction of a quantity of hot gases from the cavity produced by the vaporization of the working fluid upon detonation of the nuclear device. A method of generating power is also described. This method consists of: 1.) introducing a quantity of water in an underground cavity; 2.) heating the water in the cavity to form saturated steam; 3.) detonating a nuclear device at a central location inside the cavity; 4.) recoiling plate-like elements inside the cavity away from the central location in a mechanically regulated and controlled manner to absorb a shock wave produced by the nuclear device detonation and thereby protect the underground cavity against damage; 5.) extracting a quantity of superheated steam produced by the detonation of the nuclear device; and 6.) Converting the energy in the extracted superheated steam into electrical power

  14. Misunderstanding nuclear power

    International Nuclear Information System (INIS)

    Tombs, F.

    1981-01-01

    The inaugural lecture of Sir Francis Tombs as newly installed President of the Institution of Electrical Engineers, on the reasons for the widely differing perceptions of opposing factions in the nuclear debate, is reviewed with extensive quotations. The lecturer pointed out that development of nuclear power as an energy source requires the consent of the majority and the uncommitted must be persuaded to spend the time necessary to understand the issues and to evaluate the arguments in an objective way. (U.K.)

  15. Safety enhancement concept for NPP of new generation with VVER reactors

    International Nuclear Information System (INIS)

    Bezlepkin, V.; Kukhtevich, I.; Semashko, S.; Svetlov, S.; Solodovnikov, A.

    2004-01-01

    With the present day conditions, in order to successfully promote new NPP designs in the electric power markets, it is necessary to ensure enhanced technical/economic performances provided that international safety requirements are properly adhered to. When compared with high-powered nuclear power plants, NPP VVER-640 design (medium powered) possesses a number of advantages for the regions with undeveloped energy systems. Reduced specific energy intensity of the core adopted in this type of reactor allows to ensure the emergency cooldown of the reactor plant by passive means and to minimize the 'human factor' risk and external effects and provide sound substantiations as to how to retain corium inside RPV in case of severe accidents. At the same time, high-powered NPPs seem to be promising for regions with developed energy systems. Among such designs, NPP VVER-1000 and VVER-1500 designs are the most desirable. Configuration of new generation NPP with VVER-1500 is to be selected based on the gained experience in designing NPPs of previous generations considering the latest safety requirements and situation in the domestic and global energy markets for the time being and in the short run. Recent IAEA publications and latest EUR requirements insist that the following key safety indices should be established for new NPP designs: - aggregated frequency of core melting is 10 -6 (1/year); - frequency of maximum accident release is 10 -7 (1/year). To meet the aforementioned criteria, it is necessary to implement some safety assurance principles recommended by IAEA (in-depth defence, single failure, redundancy, diversity, etc.), application of deterministic and probabilistic methods for selection of safety assurance activities and means and use of reasonable combination of active and passive systems. Application of VVER-640 concept to high-powered NPPs seems to be a formidable task due to a number of reasons, namely, it is quite difficult to carry out cooldown process

  16. Nuclear power in Germany

    International Nuclear Information System (INIS)

    Schaefer, A.

    1990-01-01

    I want to give some ideas on the situation of public and utility acceptance of nuclear power in the Federal Republic of Germany and perhaps a little bit on Europe. Let me start with public perception. I think in Germany we have a general trend in the public perception of technology during the last decade that has been investigated in a systematic manner in a recent study. It is clear that the general acceptance of technology decreased substantially during the last twenty years. We can also observe during this time that aspects of the benefits of technology are much less reported in the media, that most reporting by the media now is related to the consequences of technologies, such as negative environmental consequences. hat development has led to a general opposition against new technological projects, in particular unusual and large. That trend is related not only to nuclear power, we see it also for new airports, trains, coal-fired plants. here is almost no new technological project in Germany where there is not very strong opposition against it, at least locally. What is the current public opinion concerning nuclear power? Nuclear power certainly received a big shock after Chernobyl, but actually, about two thirds of the German population wants to keep the operating plants running. Some people want to phase the plants out as they reach the end-of-life, some want to substitute newer nuclear technology, and a smaller part want to increase the use of nuclear power. But only a minority of the German public would really like to abandon nuclear energy

  17. Nuclear power: Europe report

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    Last year, 1999, nuclear power plants were available for energy supply, respectively, in 18 countries all over Europe. In eight of the fifteen member countries of the European Union nuclear power plants have been in operation. A total of 218 plants with an aggregate net capacity of 181,120 MWe and an aggregate gross capacity of 171,802 MWe were in operation. Two units, i.e. Civaux 2 in France and Mochovce-2 in Slovakia went critical for the first time and started commercial operation after having been connected to the grid. Three further units in France, Chooz 1 and 2 and Civaux 1, started commercial operation in 1999 after the completion of technical measures in the primary circuit. Last year, 13 plants were under construction in Romania, Russia, Slovakia and the Czech Republic, that is only in East European countries. In eight countries of the European Union 146 nuclear power plants have been operated with an aggregate gross capacity of 129.772 MWe and an aggregate net capacity of 123.668 MWe. Net electricity production in 1999 in the EU amounts to approx. 840.2 TWh, which means a share of 35 per cent of the total production. Shares of nuclear power differ widely among the operator countries. They reach 75 per cent in France, 73 per cent in Lithuania, 58 per cent in Belgium and 47 per cent in Bulgaria, Sweden and Slovakia. Nuclear power also provides a noticeable share in the electricity supply of countries, which operate no own nuclear power plants, e.g. Italy, Portugal and Austria. (orig.) [de

  18. Nuclear power: Europe report

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    Last year, 2000, nuclear power plants were available for energy supply, respectively, in 18 countries all over Europe. In eight of the fifteen member countries of the European Union nuclear power plants have been in operation. A total of 218 plants with an aggregate net capacity of 172 259 MWe and an aggregate gross capacity of 181 642 MWe were in operation (31.12.2000; 215 plants, 180 067 MWe (gross), 172 259 MWe (net)). One unit, i.e. Temelin in the Czech Republic went critical for the first time and started test operation after having been connected to the grid. Temelin adds about 981 MWe (gross) and 912 MWe (net) to the electricity production capacity. Three units, Hinkley Point A1 and A2 in United Kingdom, and Chernobyl 3 in the Ukraine have been shut down during the year 2000. This means a loss of 1534 MWe gross capacity and 1420 MWe net capacity. Last year, 12 plants (31.12.2000: 11 plants) were under construction in Romania, Russia, Slovakia, the Czech Republic and the Ukraine, that is only in east european countries. In eight countries of the European Union 146 nuclear power plants have been operated with an aggregate gross capacity of 129 188 MWe and an aggregate net capacity of 123 061 MWe (31.12.2000: 144 plants, 128 613 MWe (gross), 122 627 MWe (net)). Net electricity production in 2000 in the EU amounts to approx. 818.8 TWh, which means a share of 35 per cent of the total production in the whole EU. Shares of nuclear power differ widely among the operator countries. The reach 76 per cent in France, 74 per cent in Lithuania, 57 per cent in Belgium and 47 per cent in the Ukraine. Nuclear power also provides an noticeable share in the electricity supply of countries, which operate no own nuclear power plants, e. g. Italy, Portugal and Austria. (orig.) [de

  19. How nuclear power began

    International Nuclear Information System (INIS)

    Gowing, M.

    1987-01-01

    Many of the features of the story of nuclear power, both in nuclear weapons and nuclear power stations, derive from their timing. Usually, in the history of science the precise timing of discovery does not make much difference, but in the case of nuclear fission there was the coincidence that crucial discoveries were made and openly published in the same year, 1939, as the outbreak of the Second World War. It is these events of the 1930s and the early post-war era that are mainly discussed. However, the story began a lot earlier and even in the early 1900s the potential power within the atom had been foreseen by Soddy and Rutherford. In the 1930s Enrico Fermi and his team saw the technological importance of their discoveries and took out a patent on their process to produce artificial radioactivity from slow neutron beams. The need for secrecy because of the war, and the personal trusts and mistrusts run through the story of nuclear power. (UK)

  20. Nuclear power safety

    International Nuclear Information System (INIS)

    1988-01-01

    The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

  1. Nuclear power and physics

    International Nuclear Information System (INIS)

    Xu Mi

    2006-01-01

    During the 30s and 40s of the last century atomic physicists discovered the fission of uranium nuclei bombarded by neutrons and realized the first self-sustaining controlled fission chain reaction, which ushered in the atomic age. After 50 years of electricity production, in 2003 nuclear power plants were generating 16% of the total electricity in the world. Of these, thermal neutron reactors make up over 99%. For the large scale production of nuclear power, say up to hundreds of GWe, it is very important to speed up the development and deployment of fast breeder reactors to avoid the future lack of uranium resources. (authors)

  2. Nuclear power plants maintenance

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Nuclear power plants maintenance now appears as an important factor contributing to the competitivity of nuclea energy. The articles published in this issue describe the way maintenance has been organized in France and how it led to an actual industrial activity developing and providing products and services. An information note about Georges Besse uranium enrichment plant (Eurodif) recalls that maintenance has become a main data not only for power plants but for all nuclear industry installations. (The second part of this dossier will be published in the next issue: vol. 1 January-February 1989) [fr

  3. Nuclear power safety economics

    International Nuclear Information System (INIS)

    Legasov, V.A.; Demin, V.F.; Shevelev, Ya.V.

    1984-01-01

    The existing conceptual and methodical basis for the decision-making process insuring safety of the nuclear power and other (industrial and non-industrial) human activities is critically analyzed. Necessity of development a generalized economic safety analysis method (GESAM) is shown. Its purpose is justifying safety measures. Problems of GESAM development are considered including the problem of costing human risk. A number of suggestions on solving them are given. Using the discounting procedure in the assessment of risk or detriment caused by harmful impact on human health is substantiated. Examples of analyzing some safety systems in the nuclear power and other spheres of human activity are given

  4. Compact simulators for WWER-440 type nuclear power plants

    International Nuclear Information System (INIS)

    Vegh, E.; Janosy, J.S.

    1991-09-01

    This paper describes a compact simulator for VVER-440 type plants. Up till now three simulators have been delivered: to Paks Nuclear Power Plant (Hungary), and to Kola and Rovno NPPs (Soviet Union). In this compact simulator the modelling complexity of the plant is almost similar to that of a full-scope one apart from the Control Room being replaced by a Control Desk and four colour graphic display units. The simulation of the plant covers the whole operating range: from cold shut-down state to nominal power level. The simulator contains up to 32 different initial conditions. Moreover, every 5 minutes the simulator produces so called 'snapshots', i.e. disc images of the Data Base. Using these snapshots the instructor can go back in time (called backtracking) in order to repeat some previously passed events

  5. Beloyarsk Nuclear Power Plant

    International Nuclear Information System (INIS)

    1997-01-01

    The Beloyarsk Nuclear Power Plant (BNPP) is located in Zarechny, approximately 60 km east of Ekaterinberg along the Trans-Siberian Highway. Zarechny, a small city of approximately 30,000 residents, was built to support BNPP operations. It is a closed city to unescorted visitors. Residents must show identification for entry. BNPP is one of the first and oldest commercial nuclear power plants in Russia and began operations in 1964. As for most nuclear power plants in the Russian Federation, BNPP is operated by Rosenergoatom, which is subordinated to the Ministry of Atomic Energy of the Russian Federation (Minatom). BNPP is the site of three nuclear reactors, Units 1, 2, and 3. Units 1 and 2, which have been shut-down and defueled, were graphite moderated reactors. The units were shut-down in 1981 and 1989. Unit 3, a BN-600 reactor, is a 600 MW(electric) sodium-cooled fast breeder reactor. Unit 3 went on-line in April 1980 and produces electric power which is fed into a distribution grid and thermal power which provides heat to Zarechny. The paper also discusses the SF NIKIET, the Sverdiovsk Branch of NIKIET, Moscow, which is the research and development branch of the parent NIKEIT and is primarily a design institute responsible for reactor design. Central to its operations is a 15 megawatt IVV research reactor. The paper discusses general security and fissile material control and accountability at these two facilities

  6. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

  7. Nuclear power and modern society

    International Nuclear Information System (INIS)

    Komarek, A.

    1999-01-01

    A treatise consisting of the following sections: Development of modern society (Origin of modern society; Industrial society; The year 1968; Post-industrial society; Worldwide civic society); Historic breaks in the development of the stationary power sector (Stationary thermal power; Historic breaks in the development of nuclear power); Czech nuclear power engineering in the globalization era (Major causes of success of Czech nuclear power engineering; Future of Czech nuclear power engineering). (P.A.)

  8. Power generation by nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.

    2004-01-01

    Nuclear power plays an important role in the world, European (33%) and French (75%) power generation. This article aims at presenting in a synthetic way the main reactor types with their respective advantages with respect to the objectives foreseen (power generation, resources valorization, waste management). It makes a fast review of 50 years of nuclear development, thanks to which the nuclear industry has become one of the safest and less environmentally harmful industry which allows to produce low cost electricity: 1 - simplified description of a nuclear power generation plant: nuclear reactor, heat transfer system, power generation system, interface with the power distribution grid; 2 - first historical developments of nuclear power; 3 - industrial development and experience feedback (1965-1995): water reactors (PWR, BWR, Candu), RBMK, fast neutron reactors, high temperature demonstration reactors, costs of industrial reactors; 4 - service life of nuclear power plants and replacement: technical, regulatory and economical lifetime, problems linked with the replacement; 5 - conclusion. (J.S.)

  9. LDC nuclear power: Argentina

    International Nuclear Information System (INIS)

    Tweedale, D.L.

    1982-01-01

    Argentina's 31-year-old nuclear research and power program makes it a Third World leader and the preeminent Latin American country. Easily accessible uranium fuels the heavy water reactor, Atucha I, which provides 10% of the country's electric power. Atucha II and III are under construction. Several domestic and international factors combined to make Argentina's program succeed, but achieving fuel-cycle independence and the capacity to divert fissionable material to military uses is a cause for some concern. 60 references

  10. Nuclear power: Pt. 6

    International Nuclear Information System (INIS)

    Janse van Rensburg, H.J.

    1985-01-01

    Based on the annual growthrate of 2,5% in the need for energy and the present coal, oil, gas and uranium reserves, it is expected that there will be an energy deficiency early in the twentieth century. Coal-fired power stations have the disadvantage of pollution and a high water consumption. The use of nuclear power in South Africa is backed-up by its uranium reserves

  11. The abuse of nuclear power

    International Nuclear Information System (INIS)

    Hill, J.

    1977-01-01

    Different aspects of possible abuse of nuclear power by countries or individuals are discussed. Special attention is paid to the advantage of nuclear power, despite the risk of weapon proliferation or terrorism. The concepts of some nuclear power critics, concerning health risks in the nuclear sector are rejected as untrue and abusive

  12. Nuclear power plant analyzer

    International Nuclear Information System (INIS)

    Stritar, A.

    1986-01-01

    The development of Nuclear Power Plant Analyzers in USA is described. There are two different types of Analyzers under development in USA, the forst in Idaho and Los Alamos national Lab, the second in brookhaven National lab. That one is described in detail. The computer hardware and the mathematical models of the reactor vessel thermalhydraulics are described. (author)

  13. Benchmarking Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jakic, I.

    2016-01-01

    One of the main tasks an owner have is to keep its business competitive on the market while delivering its product. Being owner of nuclear power plant bear the same (or even more complex and stern) responsibility due to safety risks and costs. In the past, nuclear power plant managements could (partly) ignore profit or it was simply expected and to some degree assured through the various regulatory processes governing electricity rate design. It is obvious now that, with the deregulation, utility privatization and competitive electricity market, key measure of success used at nuclear power plants must include traditional metrics of successful business (return on investment, earnings and revenue generation) as well as those of plant performance, safety and reliability. In order to analyze business performance of (specific) nuclear power plant, benchmarking, as one of the well-established concept and usual method was used. Domain was conservatively designed, with well-adjusted framework, but results have still limited application due to many differences, gaps and uncertainties. (author).

  14. Nuclear power and safety

    International Nuclear Information System (INIS)

    Chidambaram, R.

    1992-01-01

    Some aspects of safety of nuclear power with special reference to Indian nuclear power programme are discussed. India must develop technology to protect herself from the adverse economic impact arising out of the restrictive regime which is being created through globalization of safety and environmental issues. Though the studies done and experience gained so far have shown that the PHWR system adopted by India has a number of superior safety features, research work is needed in the field of operation and maintenance of reactors and also in the field of reactor life extension through delaying of ageing effects. Public relations work must be pursued to convince the public at large of the safety of nuclear power programme. The new reactor designs in the second stage of evolution are based on either further improvement of existing well-proven designs or adoptions of more innovative ideas based on physical principles to ensure a higher level of safety. The development of Indian nuclear power programme is characterised by a balanced approach in the matter of assuring safety. Safety enforcement is not just looked upon as a pure administrative matter, but experts with independent minds are also involved in safety related matters. (M.G.B.)

  15. Nuclear Power in Space.

    Science.gov (United States)

    Department of Energy, Washington, DC. Nuclear Energy Office.

    Research has shown that nuclear radioisotope power generators can supply compact, reliable, and efficient sources of energy for a broad range of space missions. These missions range from televising views of planetary surfaces to communicating scientific data to Earth. This publication presents many applications of the advancing technology and…

  16. Captivated by nuclear power

    International Nuclear Information System (INIS)

    Kaageson, P.; Kjellstroem, B.

    1984-01-01

    The Swedish decision to discontinue nuclear power production is discussed. The basis of the referendum is presented. A number of cases where the decision to stop production in the year 2010 is counteracted, are described. The political and technical steps to facilitate the settlement are presented. (GB)

  17. 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.)

  18. Aspect of nuclear power

    International Nuclear Information System (INIS)

    Haghighi Oskoei, R.; Raeis Hosseiny, N.

    2004-01-01

    Over the next 50 years, unless patterns change dramatically, energy production and use will contribute to global warming through large-scale greenhouse gas emissions-hundreds of billions of tonnes of carbon in the form of carbon dioxide. Nuclear power would be one option for reducing carbon emissions. At present, however, this is unlikely: nuclear power faces stagnation and decline. We decided to study the future of nuclear power because we believe this technology , despite the changes it faces, is an important option for the world to meet future energy needs without emitting carbon dioxide and other atmospheric pollutants. Other options include increased efficiency, renewable and sequestration. We believe that all options should be preserved as nations develop strategies at provide energy while meeting important environmental challenges. The nuclear power option will only be exercised, however if the technology demonstrates better economics, improved safety, successful waste management, and low proliferation risk, and if public policies place a significant value on electricity production that does not produce carbon dioxide

  19. Safe nuclear power

    International Nuclear Information System (INIS)

    Cady, K.B.

    1992-01-01

    Nearly 22 percent of the electricity generated in the United States already comes from nuclear power plants, but no new plants have been ordered since 1978. This paper reports that the problems that stand in the way of further development have to do with complexity and perceived risk. Licensing, construction management, and waste disposal are complex matters, and the possibility of accident has alienated a significant portion of the public. But a national poll conducted by Bruskin/Goldring at the beginning of February shows that opposition to nuclear energy is softening. Sixty percent of the American people support (strongly or moderately) the use of nuclear power, and 18 percent moderately oppose it. Only 15 percent remain obstinately opposed. Perhaps they are not aware of recent advances in reactor technology

  20. Construction of the Plant RT-2 as a way for solving the problem of VVER-1000 spent fuel management in Russia

    International Nuclear Information System (INIS)

    Lazarev, L.N.; Lyubtsev, R.I.; Egorov, N.N.; Lebedev, V.A.; Revenko, Y.A.; Fedosov, Y.G.; Dubrovskii, V.M.

    1993-01-01

    Nuclear power in the Russian Federation in the future will be based on the VVER-1000 and it's modifications. To manage the spent fuels from this plant, the Plant RT-2 was designed to process the spent fuel. Plant construction was started in 1984 and stopped in 1989 due to economic difficulties. The necessity of the continuation of the plant is discussed

  1. Nuclear power and nuclear safety 2006

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2007-04-01

    The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

  2. Nuclear power and nuclear safety 2004

    International Nuclear Information System (INIS)

    2005-03-01

    The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  3. Nuclear power and nuclear safety 2005

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampman, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2006-03-01

    The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  4. Nuclear power and nuclear safety 2008

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.

    2009-06-01

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  5. Nuclear power. [Contains glossary

    Energy Technology Data Exchange (ETDEWEB)

    Patterson, W.C.

    1983-01-01

    Lay language brings an understanding of nuclear technology and nuclear politics to the non-specialist reader. The author notes that there has been little change in the technology during the four decades of the nuclear age, but mankind has still to learn how to live with it. Part One explains how reactors work, identifies different reactor types, and describes the fuel cycle. Part two follows research developments during the pre-Manhatten Project days, the war effort, and the decision to pursue commercial nuclear power. He traces the development of policies to secure fission materials and international efforts to prevent the proliferation of weapons grade material and the safe handling of radioactive wastes on a global as well as national scale. There are four appendices, including an annotated reference to other publications. 9 figures.

  6. Nuclear-powered submarines

    International Nuclear Information System (INIS)

    Curren, T.

    1989-01-01

    The proposed acquisition of nuclear-powered submarines by the Canadian Armed Forces raises a number of legitimate concerns, including that of their potential impact on the environment. The use of nuclear reactors as the propulsion units in these submarines merits special consideration. Radioactivity, as an environmental pollutant, has unique qualities and engenders particular fears among the general population. The effects of nuclear submarines on the environment fall into two distinct categories: those deriving from normal operations of the submarine (the chief concern of this paper), and those deriving from a reactor accident. An enormous body of data must exist to support the safe operation of nuclear submarines; however, little information on this aspect of the proposed submarine program has been made available to the Canadian public. (5 refs.)

  7. Can nuclear power compete?

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1993-01-01

    The competitiveness of electricity generation from new nuclear plant with that from fossil-fired plant depends on a number of factors, the most important of which are the future costs of fossil fuels and the required rate of return on capital. Nuclear power is generally expected to remain competitive for baseload generation in OECD countries except in regions with direct access to cheap fossil fuels, based on the economic criteria and price expectations prevailing in the different countries. The situation in the United Kingdom will be clearer later in 1993 when comparisons prepared for the Government's Nuclear Review are published, but on the basis of the information available new nuclear plants should be competitive with the other technical options available for deployment around the year 2000. (author)

  8. LDC nuclear power: Philippines

    International Nuclear Information System (INIS)

    Scherr, S.J.

    1982-01-01

    The US created the need for nuclear power in the Phillipines and then provided the means to fill it, but the 20-year nuclear program was reversed in 1976 because of public opposition to heavy-handed government policies. The situation illustrates the overriding importance of foreign influence and political judgment. Despite substantial investments in the training of Filipino nuclear scientists and technicians, nuclear energy continues to be viewed as an alien technology by the people. Even the protracted debate over the first reactor has been dominated by US experts and advisers because the traditional transnational cooperation was extended beyond government to nongovernmental citizen organizations when Filipno protestors sought help from US groups. 120 references

  9. VVER 1000-NPP Temelin safety upgrading

    International Nuclear Information System (INIS)

    Fleischhans, J.; Ubra, O.

    1995-01-01

    A modernisation program upgrading Temelin plant to meet internationally adopted standard has been implemented during plant design and construction phases. The initial Czech-Russian design (primary system was of Russian design, secondary system was of Czech design) has been extensively modified and adapted to present western safety criteria and operational requirements. The goals are to achieve a high level of safety, reliability, availability and load-following ability. The load-following ability and response to grid frequency changes are very important for the Czech Republic, since the nuclear capacity represents a high proportion of the overall electrical system there. On the basis of IAEA OSART missions and Halliburton NUS audit results and in compliance with recommendations of The State Office for Nuclear Safety, Czech Power Company and Czech scientists and researchers a modernisation program project for Temelin has been carried out. It includes three main groups of VVER1000 MW unit innovations: - Modernization and upgrading of the safety and control systems. - Fuel replacement and modification of the reactor core. - Innovation of some components of the primary and secondary systems. The tenders for instrumentation and control system, nuclear fuel, diagnostic system and radiation monitoring system were issued to the world-well known suppliers. The US company Westinghouse Electric >Corporation (WEC) was selected to submit contract for the delivery of instrumentation and control system primary side diagnostic system and for the delivery of nuclear fuel. The contract was signed in 1993

  10. Facts about nuclear power

    International Nuclear Information System (INIS)

    Muench, E.

    1980-01-01

    The argument concerning the introduction and the further expansion of nuclear energy in the Federal Republic of Germany has been existing for several years in differing intensities and most different forms. The arguments and theses of the discussion deal with the various aspects of the reciprocity between nuclear energy and environment. This is the key-note for the scientists to treat the relevant problems and questions in the discussion about nuclear energy. The controversy in which often emotional theses are stated instead of reasonably deliberating the pros and contras includes civil initiatives, societies, and environment protection organisations on the one hand and authorities, producers, and operators of nuclear-technical plants on the other. And the scale of the different opinions reaches from real agreement to deep condemnation of a technology which represents an option to meet the energy need in the future. In this situation, this book is an attempt to de-emotionalize the whole discussion. Most of the authors of the articles come from research centres and have been working on the problems they deal with for years. The spectrum of the topics includes the energy-political coherences of nuclear energy, the technical fundaments of the individual reactor types, safety and security of nuclear-technical plants the fuel cycle, especially the waste management in nuclear power plants, environmental aspects of energy generation in general and nuclear energy in special, the question of Plutonium and the presentation of alternative energy sources including nuclear fusion. The arrangement of these topics is meant to help to clarify the complex coherences of nuclear energy and to help those interested in problems of energy policy to make their own personal decisions. (orig./RW) [de

  11. Economics of nuclear power

    International Nuclear Information System (INIS)

    Roth, B.F.

    1977-01-01

    The economics of electricity supply and production in the FRG is to see on the background of the unique European interconnected grid system which makes very significant contributions to the availability of standby energy and peak load power. On this basis and the existing high voltage grid system, we can build large nuclear generating units and realise the favorable cost aspects per installed KW and reduced standby power. An example of calculating the overall electricity generating costs based on the present worth method is explained. From the figures shown, the sensitivity of the generating costs with respect to the different cost components can be derived. It is apparent from the example used, that the major advantage of nuclear power stations compared with fossil fired stations lies in the relatively small percentage fraction contributed by the fuel costs to the electricity generating costs. (orig.) [de

  12. Nuclear power and weapons proliferation

    International Nuclear Information System (INIS)

    Greenwood, T.; Rathjens, C.W.; Ruina, J.

    1977-01-01

    The relationship between nuclear weapons development and nuclear electric power is examined. A brief description of nuclear weapons design is first given. This is then followed by a discussion of various aspects of nuclear power technology and of how they affect a nuclear weapon programme. These include fuel cycles, chemical reprocessing of spent fuel, uranium enrichment, and the control of dissemination of nuclear technology. In conclusion there is a discussion of possible political and institutional controls for limiting nuclear proliferation. (U.K.)

  13. Is nuclear power competitive

    International Nuclear Information System (INIS)

    Brandfon, W.W.

    1984-01-01

    The first phase of a two-phase study of the competitiveness of electricity from new coal and nuclear plants with oil and natural gas in common markets concludes that, with few exceptions throughout the country, overall levelized nuclear generating cost could be lower than coal generating costs by more than 40%. The study shows a wider margin of economic superiority for nuclear than has been seen in other recent studies. Capital and fuel costs are the major determinants of relative nuclear and coal economics. The only substantial difference in the input assumptions has related to a shorter lead time for both coal and nuclear units, which reduces capital costs. The study gives substance to the charge that delaying tactics by intervenors and an unstable licensing environment drove up lifetime costs of both coal and nuclear plants. This caused an increase in electric rates and affected the entire economy. The study shows that nuclear power is competitive when large baseload capacity is required. 14 figures

  14. Economics of nuclear power

    International Nuclear Information System (INIS)

    Reichle, L.F.C.

    1977-01-01

    Mr. Reichle feels that the economic advantages of pursuing nuclear power should prompt Congress and the administration to seek ways of eliminating undue delays and enabling industry to proceed with the design, construction, and management of nuclear plants and facilities. Abundant, low-cost energy, which can only be supplied by coal and nuclear, is vital to growth in our gross national product, he states. While conservation efforts are commendable, we must have more energy if we are to maintain our standard of living. Current energy resources projections into the next century indicate an energy gap of 42 quads with a 3 percent growth and 72 quads with a 4 percent growth. Comparisons of fuel prices, plant capital investment, and electric generation costs are developed for both coal and nuclear energy; these show that nuclear energy has a clear advantage economically as long as light water reactors are supplemented by breeder reactor development and the nuclear industry can demonstrate that these reactors are safe, reliable, and compatible with the environment. Mr. Reichle says excessive regulation and legal challenges combined with public apathy toward developing nuclear energy are delaying decisions and actions that should be taken now

  15. Economics of Nuclear Power Plant and the development of nuclear power in Viet Nam

    International Nuclear Information System (INIS)

    Thanh, Thuy Nguyen Thi; Song, JinHo; Ha, Kwang Soon

    2015-01-01

    There are many factors affecting the capital costs like: increased plant size, multiple unit construction, improved construct methods, increase the lifetime of plant and so on, and beside is technical to enhancing the safety for NPPs. For the question that whether building a NPP is really economic than other energy resources or not, we will find the answer by comparing the USD per kWh of different energy sources as: nuclear power, coal, oil, hydro natural energy sources. The situation of energy in Vietnam was also mentioned in this paper. Vietnam has an abundant natural resources likes: coal, gas, hydro power etc, but from year 2013 to now Vietnam facing of electricity shortage and to solve the problem, Vietnam Government has chosen nuclear power energy to achieve energy balance between the rate of energy consumption and the ability to energy supply. Eight units will be built in Vietnam and in October 2014 Vietnamese officials have chosen Rosatom's AES-2006 design with VVER-1200/v-491 reactors for country's first nuclear power plant at Ninh Thuan and a second plant should follow based on a partnership with Japan. In this paper, the breakdown of NPP costs is considered. All the costs for building a NPP includes: the investment costs are the largest components (about 60%), fuel costs (15%), O and M costs (25%) and external costs are lower than 1% of the kWh costs. The situation for energy in Vietnam was mentioned with increase annually by 5.5 %, and now the shortage electricity is the big problem in power section. The purpose of this report is to give a general picture to consider the cost of nuclear power. It includes all the costs for building a nuclear power plant like total capital investment costs, production costs, external costs in which the capital investment costs is the largest component of the kWh cost. Nuclear energy Power was chosen to deal with situation of diminishing resources shortages

  16. Economics of Nuclear Power Plant and the development of nuclear power in Viet Nam

    Energy Technology Data Exchange (ETDEWEB)

    Thanh, Thuy Nguyen Thi; Song, JinHo [University of Science and Technology, Daejeon (Korea, Republic of); Ha, Kwang Soon [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    There are many factors affecting the capital costs like: increased plant size, multiple unit construction, improved construct methods, increase the lifetime of plant and so on, and beside is technical to enhancing the safety for NPPs. For the question that whether building a NPP is really economic than other energy resources or not, we will find the answer by comparing the USD per kWh of different energy sources as: nuclear power, coal, oil, hydro natural energy sources. The situation of energy in Vietnam was also mentioned in this paper. Vietnam has an abundant natural resources likes: coal, gas, hydro power etc, but from year 2013 to now Vietnam facing of electricity shortage and to solve the problem, Vietnam Government has chosen nuclear power energy to achieve energy balance between the rate of energy consumption and the ability to energy supply. Eight units will be built in Vietnam and in October 2014 Vietnamese officials have chosen Rosatom's AES-2006 design with VVER-1200/v-491 reactors for country's first nuclear power plant at Ninh Thuan and a second plant should follow based on a partnership with Japan. In this paper, the breakdown of NPP costs is considered. All the costs for building a NPP includes: the investment costs are the largest components (about 60%), fuel costs (15%), O and M costs (25%) and external costs are lower than 1% of the kWh costs. The situation for energy in Vietnam was mentioned with increase annually by 5.5 %, and now the shortage electricity is the big problem in power section. The purpose of this report is to give a general picture to consider the cost of nuclear power. It includes all the costs for building a nuclear power plant like total capital investment costs, production costs, external costs in which the capital investment costs is the largest component of the kWh cost. Nuclear energy Power was chosen to deal with situation of diminishing resources shortages.

  17. The problem of nuclear power

    International Nuclear Information System (INIS)

    Heimbrecht, J.; Kade, G.; Krusewitz, K.; Moldenhauer, B.; Steinhaus, K.; Weish, P.

    1977-01-01

    The battle over the problems of nuclear power has gone on in the Federal Republic for several years. The Buergerinitiativen, which used to be small and largely unpolitical, have become a major social force during this time. Subjects: 1) Dangers of nuclear power - can the risk be justified; 2)The necessity of nuclear power; 3) The enforcement of nuclear power - political and economic background; 4) Limits of power generation - limits of growth or limits of the system. (orig./HP) [de

  18. Nuclear Power Prospects

    International Nuclear Information System (INIS)

    Cintra do Prado, L.

    1966-01-01

    The present trend is to construct larger plants: the average power of the plants under construction at present, including prototypes, is 300 MW(e), i.e. three times higher than in the case of plants already in operation. Examples of new large-scale plants ares (a) Wylfa, Anglesey, United Kingdom - scheduled power of 1180 MW(e) (800 MW to be installed by 1967), to be completed in 1968; (b) ''Dungeness B'', United Kingdom - scheduled power of 1200 MW(e); (c) second unit for United States Dresden power plant - scheduled power of 715 MW(e) minimum to almost 800 MW(e). Nuclear plants on the whole serve the same purpose as conventional thermal plants

  19. The nuclear power debate

    International Nuclear Information System (INIS)

    Woerndl, B.

    1992-01-01

    This material-intensive analysis of the public dispute about nuclear power plants uses the fundamental thoughts of the conflict theory approach by Georg Simmel, linking them to results of recent value change research. Through the medium of a qualitative content analysis of arguments in favour of and against nuclear energy it is shown how values are expressed and move, how they differentiate and get modified, in conflicting argumentation patterns. The first part reconstructs the history of the nuclear power conflict under the aspect of its subject priorities changing from time to time. The second part shows, based on three debate priorities, how social value patterns recognized for the moment changed in and by the conflict: the argumentation is that the nuclear power controversy has led to a relativization of its scientific claim for recognition; it has created a problem awareness with regard to purely quantitatively oriented growth objectives and developed criteria of an ecologically controlled satisfaction of needs; the debate has paved the way, in the area of political regulation models, for the advancement of basic democratic elements within a representative democracy. (orig./HP) [de

  20. Nuclear power for desalination

    International Nuclear Information System (INIS)

    Patil, Siddhanth; Lanjekar, Sanket; Jagdale, Bhushan; Srivastava, V.K.

    2015-01-01

    Water is one of the most important assets to mankind and without which the human race would cease to exist. Water is required by us right from domestic to industrial levels. As notified by the 'American Nuclear Society' and 'World Nuclear Association' about 1/5 th of the world population does not access to portable water especially in the Asian and African subcontinent. The situation is becoming adverse day by day due to rise in population and industrialization. The need of alternative water resource is thus becoming vital. About 97.5% of Earth is covered by oceans. Desalination of saline water to generate potable water is thus an important topic of research. Currently about 12,500 desalination plants are operating worldwide with a capacity of about 35 million m 3 /day using mainly fossil fuels for generation of large amount of energy required for processing water. These thermal power station release large amount of carbon dioxide and other green house gases. Nuclear reactors are capable of delivering energy to the high energy-intensive processes without any environmental concerns for climate change etc., giving a vision to sustainable growth of desalination process. These projects are currently employed in Kazakhstan, India, Japan, and Pakistan and are coupled to the nuclear reactor for generating electricity and potable water as well. The current climatic scenario favors the need for expanding dual purpose nuclear power plants producing energy and water at the same location. (author)

  1. Economics of nuclear power projects

    International Nuclear Information System (INIS)

    Chu, I.H.

    1985-01-01

    Nuclear power development in Taiwan was initiated in 1956. Now Taipower has five nuclear units in smooth operation, one unit under construction, two units under planning. The relatively short construction period, low construction costs and twin unit approach had led to the significant economical advantage of our nuclear power generation. Moreover betterment programmes have further improved the availability and reliability factors of our nuclear power plants. In Taipower, the generation cost of nuclear power was even less than half of that of oil-fired thermal power in the past years ever since the nuclear power was commissioned. This made Taipower have more earnings and power rates was even dropped down in March 1983. As Taiwan is short of energy sources and nuclear power is so well-demonstrated nuclear power will be logically the best choice for Taipower future projects

  2. Prospects for nuclear power

    International Nuclear Information System (INIS)

    Kaplan, G.

    1983-01-01

    Describes how the nuclear power industry is improving plant operation and safety procedures and is reducing maintenance costs as it hopes for a brighter political climate. Points out that most of the efforts focus on key areas, such as improvements in control rooms and operator training and studies of physical processes within the reactor and associated systems. Discusses the increasing complexity of nuclear plants, the use of computers to process data in BWR plants, the decommissioning of old plants, and plant safety research activities worldwide. Offers an annotated bibliography

  3. Economics of nuclear power

    International Nuclear Information System (INIS)

    Marwah, O.S.

    1982-01-01

    There can be no precise economic measures, in the abstract, of the costs of nuclear power production in the less-developed countries (LDCs). The conditions that affect the calculations have to be evaluated specifically for each country and individually for each nuclear-related project in that country. These conditions are a combination of internal and external factors, and their mix for one project can change during the course of construction. The author lists 21 factors that may vary according to individual national costs. 6 references, 4 tables

  4. Analysing The Thermalhydraulic Parameters Of VVER-1000 Reactor For The Accident Of Steam Generator Tube Rupture

    International Nuclear Information System (INIS)

    Luu Nam Hai; Truong Cong Thang

    2011-01-01

    To ensure the safety operation of nuclear power plant (NPP), a lot of postulated accident scenarios were considered and analysed. This research chose and analysed the accident of steam generator tube rupture (SGTR) under the actual plant conditions by using the simulation program PCTRAN. The SGTR accident is happen when the NPP is under operation with the steady state condition (power of 3000 MWth, primary pressure of 157 bar and secondary pressure of 63 bar). The accident is initiated by creating a break with equivalent diameter of 100 mm in the area of lower row heat exchanging tubes. The result of analysis is compared with the calculation of the Shariz University, Iran using the thermal hydraulics code RELAP5/mod3.2 and the report in the PSAR data of VVER-1000. This comparison shows that it is possible for using PCTRAN to analyse accidents of VVER-1000 reactor. (author)

  5. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Hardy, C.J.; Silver, J.M.

    1985-09-01

    The report provides data and assessments of the status and prospects of nuclear power and the nuclear fuel cycle. The report discusses the economic competitiveness of nuclear electricity generation, the extent of world uranium resources, production and requirements, uranium conversion and enrichment, fuel fabrication, spent fuel treatment and radioactive waste management. A review is given of the status of nuclear fusion research

  6. Making nuclear power sustainable

    International Nuclear Information System (INIS)

    Barre, B

    2003-01-01

    According to the present data, we must double our energy production while dividing by a factor of two the greenhouse gases emissions, knowing that today, 80% of our energy comes from the combustion of coal, gas and oil, all of which produce CO, released in the atmosphere. This is the toughest challenge facing us in the next few decades, and I include the water challenge, since producing drinking water will also increase our energy needs. This formidable challenge will not be easily met. No magic bullet is in sight, not even a nuclear bullet. To have any chance of success, we must actually implement all the available measures, and invent some more. In fact, we shall certainly need a three-pronged approach: Increase energy efficiency to limit energy consumption in our developed countries; Diversify our energy mix to reduce the share supplied by fossil fuels and that translates into increasing nuclear and renewable energy source; Trap and sequester CO 2 wherever and whenever economically possible. This article focuses on the nuclear issue. According to International Energy Agency (lEA) statistics, nuclear energy accounts today for 6.8% of the world energy supply. Is it realistic to expect this share to grow, when many forecasts (including lEA's own) predict a slow reduction? The future is not engraved in marble, it is ours to make; the future role of nuclear power will depend on the results of our present efforts to expand or overcome its limitations. It is quite possible that, within four decades, 40% of the electric power generated in all OECD countries, plus Russia, China, India and Brazil, comes from nuclear reactors. It is not far-fetched, when you consider that it took only two decades for France to increase its nuclear share of electricity from 8% to 80%. More ambitious, let's assume that in the same time frame and within the same countries 15% of the fuels for transportation come from nuclear produced hydrogen and that 10% of the space heating is supplied by

  7. Nuclear power system

    International Nuclear Information System (INIS)

    Yampolsky, J.S.; Cavallaro, L.; Paulovich, K.F.; Schleicher, R.W.

    1989-01-01

    This patent describes an inherently safe modular nuclear power system for producing electrical power at acceptable efficiency levels using working fluids at relatively low temperatures and pressures. The system comprising: a reactor module for heating a first fluid; a heat exchanger module for transferring heat from the first fluid to a second fluid; a first piping system effecting flow of the first fluid in a first fluid circuit successively through the reactor module and the heat exchanger module; a power conversion module comprising a turbogenerator driven by the second fluid, and means for cooling the second fluid upon emergence thereof from the turbogenerator; a second piping system comprising means for effecting flow of the second fluid in a second fluid circuit successively through the heat exchanger module and the power conversion module; and a plurality of pits for receiving the modules

  8. Accident sequences simulated at the Juragua nuclear power plant

    International Nuclear Information System (INIS)

    Carbajo, J.J.

    1998-01-01

    Different hypothetical accident sequences have been simulated at Unit 1 of the Juragua nuclear power plant in Cuba, a plant with two VVER-440 V213 units under construction. The computer code MELCOR was employed for these simulations. The sequences simulated are: (1) a design-basis accident (DBA) large loss of coolant accident (LOCA) with the emergency core coolant system (ECCS) on, (2) a station blackout (SBO), (3) a small LOCA (SLOCA) concurrent with SBO, (4) a large LOCA (LLOCA) concurrent with SBO, and (5) a LLOCA concurrent with SBO and with the containment breached at time zero. Timings of important events and source term releases have been calculated for the different sequences analyzed. Under certain weather conditions, the fission products released from the severe accident sequences may travel to southern Florida

  9. Preparedness against nuclear power accidents

    International Nuclear Information System (INIS)

    1985-01-01

    This booklet contains information about the organization against nuclear power accidents, which exist in the four Swedish counties with nuclear power plants. It is aimed at classes 7-9 of the Swedish schools. (L.E.)

  10. Nuclear power: pros and cons

    International Nuclear Information System (INIS)

    Hirsch, H.

    1977-01-01

    The author deals with the nuclear power controversy in science and indicates the main points of the nuclear power debate by the population. The different scientific and ideological positions shown by the results of the campaign are explained. (HP) [de

  11. Ethical aspects of nuclear power

    International Nuclear Information System (INIS)

    Streithofen, H.B.

    1989-01-01

    The nuclear controversy comprises many ethical aspects, e.g. the waste disposal problem. Nuclear opponents should not neglect the environmental protection aspect; for example, the use of nuclear power alone brought about an 8% reduction of the CO 2 burden in 1987. Our responsibility towards nature and humans in the Third World leaves us no alternative to nuclear power. On the other hand, the nuclear power debate should not become a matter of religious beliefs. (DG) [de

  12. US nuclear power programs

    International Nuclear Information System (INIS)

    McGolf, D.J.

    1994-01-01

    In the United States, coal provided 56 percent of the electricity generated in 1992. Nuclear energy was the next largest contributor, supplying 22 percent. Natural gas provided 9 percent, while hydro-electric and renewables together supplied another 9 percent. Currently, the 109 nuclear power plants in the U.S. have an overall generating capacity of 99,000 MWe. To improve efficiency, safety, and performance, the lessons of 30 years of experience with nuclear powerplants are being incorporated into design criteria for the next generation of U.S. plants. The new Advanced Light Water Reactor plants will feature simpler designs, which will enable more cost-effective construction and maintenance. To enhance safety, design margins are being increased, and human factors are being considered and incorporated into the designs

  13. Lessons of nuclear power

    International Nuclear Information System (INIS)

    Collingridge, D.

    1984-01-01

    In an earlier article the author has argued that the turbulent history of nuclear power in Britain and the USA stems from the technology itself, and has little to do with the very different institutional arrangements made for the new technology in the two countries. Nuclear plant has various features which make its planning extraordinarily difficult. Its long lead time, large unit size, capital intensity and dependence on complex infrastructure combine to ensure that mistakes are likely to be made in planning the technology and that what mistakes do occur are expensive. This article aims to expand on the earlier one in two ways; by looking at the apparent success of the French nuclear programme which seems to run counter to the thesis of the earlier article, and by trying to draw lessons from the earlier analysis for the breeder reactor. (author)

  14. Insurance and nuclear power

    International Nuclear Information System (INIS)

    Whipple, C.

    1985-01-01

    The Price-Anderson Act is discussed, which establishes procedures for insuring nuclear facilities (including nuclear power plants). The act was enacted with the dual purpose of protecting the public and encouraging the development of a private nuclear energy industry. Criticisms that can generally be grouped into four categories regarding the Act are presented, the most controversial aspect being that should an accident occur, the aggregate liability of the reactor operator, the NRC, or any others who might be at fault is limited to $560 million. Lawsuits for amounts in excess of $560 million are prohibited. The 1975 renewal of the Price-Anderson Act does provide that damages in excess of the $560 million prompt Congress to review the particular incident and take action to protect the public from the consequences of a disaster of such magnitude

  15. US nuclear power programs

    Energy Technology Data Exchange (ETDEWEB)

    McGolf, D J

    1994-12-31

    In the United States, coal provided 56 percent of the electricity generated in 1992. Nuclear energy was the next largest contributor, supplying 22 percent. Natural gas provided 9 percent, while hydro-electric and renewables together supplied another 9 percent. Currently, the 109 nuclear power plants in the U.S. have an overall generating capacity of 99,000 MWe. To improve efficiency, safety, and performance, the lessons of 30 years of experience with nuclear powerplants are being incorporated into design criteria for the next generation of U.S. plants. The new Advanced Light Water Reactor plants will feature simpler designs, which will enable more cost-effective construction and maintenance. To enhance safety, design margins are being increased, and human factors are being considered and incorporated into the designs.

  16. Ardennes nuclear power plant

    International Nuclear Information System (INIS)

    1974-12-01

    The SENA nuclear power plant continued to operate, as before, at authorized rated power, namely 905MWth during the first half year and 950MWth during the second half year. Net energy production:2028GWh; hours phased to the line: 7534H; availability factor: 84%; utilization factor: 84%; total shutdowns:19; number of scrams:10; cost per KWh: 4,35 French centimes. Overall, the plant is performing very satisfactory. Over the last three years net production has been 5900GWh, corresponding to in average utilization factor of 83%

  17. Nuclear power plant

    International Nuclear Information System (INIS)

    Orlov, V.V.; Rineisky, A.A.

    1975-01-01

    The invention is aimed at designing a nuclear power plant with a heat transfer system which permits an accelerated fuel regeneration maintaining relatively high initial steam values and efficiency of the steam power circuit. In case of a plant with three circuits the secondary cooling circuit includes a steam generator with preheater, evaporator, steam superheater and intermediate steam superheater. At the heat supply side the latter is connected with its inlet to the outlet of the evaporator and with its outlet to the low-temperature side of the secondary circuit

  18. Siting nuclear power plants

    International Nuclear Information System (INIS)

    Yellin, J.; Joskow, P.L.

    1980-01-01

    The first edition of this journal is devoted to the policies and problems of siting nuclear power plants and the question of how far commercial reactors should be placed from urban areas. The article is divided into four major siting issues: policies, risk evaluation, accident consequences, and economic and physical constraints. One concern is how to treat currently operating reactors and those under construction that were established under less-stringent criteria if siting is to be used as a way to limit the consequences of accidents. Mehanical cost-benefit analyses are not as appropriate as the systematic use of empirical observations in assessing the values involved. Stricter siting rules are justified because (1) opposition because of safety is growing: (2) remote siting will make the industry more stable; (3) the conflict is eliminated between regulatory policies and the probability basis for nuclear insurance; and (4) joint ownership of utilities and power-pooling are increasing. 227 references, 7 tables

  19. Nuclear power and ethics

    International Nuclear Information System (INIS)

    Schwery, H.

    1998-01-01

    The author can see no sense in demanding an ethical regime to be applied exclusively to nuclear power but rather calls for an approach that discusses nuclear power as one constituent of the complex energy issue in a way spanning all dimensions involved, as e.g. the technological, economic, cultural, humanitarian, and humanistic aspects. An ethical approach does not question scientific research, or science or technology, but examines their relation to man and the future of humanity, so that an ethical approach will first of all demand that society will bring forward conscientious experts as reliable partners in the process of discussing the ethical implications of progress and development in a higly industrialised civilisation. (orig./CB) [de

  20. Nuclear power plant

    International Nuclear Information System (INIS)

    Aisaka, Tatsuyoshi; Kamahara, Hisato; Yanagisawa, Ko.

    1982-01-01

    Purpose: To prevent corrosion stress cracks in structural materials in a BWR type nuclear power plant by decreasing the oxygen concentration in the reactor coolants. Constitution: A hydrogen injector is connected between the condensator and a condensate clean up system of a nuclear power plant. The injector is incorporated with hydrogenated compounds formed from metal hydrides, for example, of alloys such as lanthanum-nickel alloy, iron titanium alloy, vanadium, palladium, magnesium-copper alloy, magnesium-nickel alloy and the like. Even if the pressure of hydrogen obtained from a hydrogen bomb or by way of water electrolysis is changed, the hydrogen can always be injected into a reactor coolant at a pressure equal to the equilibrium dissociation pressure for metal hydride by introducing the hydrogen into the hydrogen injector. (Seki, T.)

  1. Adaptive Neural Network Algorithm for Power Control in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Husam Fayiz, Al Masri

    2017-01-01

    The aim of this paper is to design, test and evaluate a prototype of an adaptive neural network algorithm for the power controlling system of a nuclear power plant. The task of power control in nuclear reactors is one of the fundamental tasks in this field. Therefore, researches are constantly conducted to ameliorate the power reactor control process. Currently, in the Department of Automation in the National Research Nuclear University (NRNU) MEPhI, numerous studies are utilizing various methodologies of artificial intelligence (expert systems, neural networks, fuzzy systems and genetic algorithms) to enhance the performance, safety, efficiency and reliability of nuclear power plants. In particular, a study of an adaptive artificial intelligent power regulator in the control systems of nuclear power reactors is being undertaken to enhance performance and to minimize the output error of the Automatic Power Controller (APC) on the grounds of a multifunctional computer analyzer (simulator) of the Water-Water Energetic Reactor known as Vodo-Vodyanoi Energetichesky Reaktor (VVER) in Russian. In this paper, a block diagram of an adaptive reactor power controller was built on the basis of an intelligent control algorithm. When implementing intelligent neural network principles, it is possible to improve the quality and dynamic of any control system in accordance with the principles of adaptive control. It is common knowledge that an adaptive control system permits adjusting the controller’s parameters according to the transitions in the characteristics of the control object or external disturbances. In this project, it is demonstrated that the propitious options for an automatic power controller in nuclear power plants is a control system constructed on intelligent neural network algorithms. (paper)

  2. Nuclear power: Year 2000

    International Nuclear Information System (INIS)

    Siegel, J.R.

    1984-01-01

    This paper offers a contrary view on the future of nuclear power in the U.S. Contrarian, in that it argues that it is quite possible that the installed U.S. nuclear capacity in the year 2000 will be in the range of 250GWe. This projection is based on the longer view - a 20-30 year picture - of the price trends of the fuels commercially available to make electricity. And on the belief that other projections of nuclear capacity for the year 2000, while generally acknowledging the need to add significant amounts of new electricity capacity, are essentially discounting nuclear power. And thus, are ignoring fundamental economics. The logic for the projected 250 GWe follows: The demand for electricity is continuing to grow, albeit at a slower rate than that experienced prior to 1973; The excess generating capacity in the construction pipeline, which developed during the 1970s as economic growth rates came in at half the projections made in 1973, has been worked off; in fact, the pendulum has swung past the mid-point; U.S. utilities need to order an additional 200-350 GWe of capacity for service between 1992 and 2000; The real capital costs of plants, particularly nuclear plants, ordered in the 1980s will be less than that being completed today, as this new plant will be completed on a more expedient basis for reliability reasons, and built in an improved financial climate for utilities; Owing primarily to more favorable economics, but also to environmental considerations, at least half of new generating capacity will be nuclear

  3. Nuclear power in Italy

    International Nuclear Information System (INIS)

    Santarossa, G.

    1990-01-01

    As is known to most of this audience in November of 1987 a referendum determined a rejection of nuclear power in Italy. The referendum may be taken into consideration here as a large scale experiment which offers points of interest to this conference and problems to be aware of, in approaching a severe confrontation with the public. To give a synopsis of the Italian perspective I will examine: first the public acceptance in the situation before Chernobyl, then the most disturbing and sensitive factors of Chernobyl's consequences; how the opposition to nuclear energy worked with the support of most media and the strong pressures of an anti-nuclear political party, the syllogism of the opponents and the arguments used, the causes of major weakness of the defenders and how a new perception of nuclear risk was generated in the public. I will come to the topic of utility acceptance by mentioning that ENEL, as the National Utility, in its role is bound to a policy of compliance with Government decisions. It is oriented today to performance of feasibility studies and development of requirements for the next generation of reactors in order to maintain an updated proposal for a future recovery of the nuclear option. I will then try to identify in general terms the factors determining the future acceptance of nuclear power. They will be determined in the interdisciplinary area of politics, media and public interactions with the utilities the uses of the technology are forced to follow, by political constraints, two main directives: working only in new projects to achieve, if possible, new safety goals

  4. Nuclear power in Italy

    Energy Technology Data Exchange (ETDEWEB)

    Santarossa, G [ENEA, Rome (Italy)

    1990-07-01

    As is known to most of this audience in November of 1987 a referendum determined a rejection of nuclear power in Italy. The referendum may be taken into consideration here as a large scale experiment which offers points of interest to this conference and problems to be aware of, in approaching a severe confrontation with the public. To give a synopsis of the Italian perspective I will examine: first the public acceptance in the situation before Chernobyl, then the most disturbing and sensitive factors of Chernobyl's consequences; how the opposition to nuclear energy worked with the support of most media and the strong pressures of an anti-nuclear political party, the syllogism of the opponents and the arguments used, the causes of major weakness of the defenders and how a new perception of nuclear risk was generated in the public. I will come to the topic of utility acceptance by mentioning that ENEL, as the National Utility, in its role is bound to a policy of compliance with Government decisions. It is oriented today to performance of feasibility studies and development of requirements for the next generation of reactors in order to maintain an updated proposal for a future recovery of the nuclear option. I will then try to identify in general terms the factors determining the future acceptance of nuclear power. They will be determined in the interdisciplinary area of politics, media and public interactions with the utilities the uses of the technology are forced to follow, by political constraints, two main directives: working only in new projects to achieve, if possible, new safety goals.

  5. AAEC nuclear power projections

    International Nuclear Information System (INIS)

    Khoe, G.; Fredsall, J.; Scurr, I.; Plotnikoff, W.

    1981-01-01

    The nuclear power capacity projections developed in the May-June period of 1981 by the AAEC are presented. There have been downward revisions for nearly all countries with centrally planned economies. Projections for the year 2000 for the Western World have decreased in aggregate by 4.7% (27Gw) compared to those of 1980. However, this reduction is less than the previous estimate reduction and there appears to have been a stabilisation in the projection

  6. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.; Laurer, E.

    1976-01-01

    The invention concerns a quick-acting valve on the main-steam pipe of a nuclear power plant. The engineering design of the valve is to be improved. To the main valve disc, a piston-operated auxiliary valve disc is to be assigned closing a section of the area of the main valve disc. This way it is avoided that the drive of the main valve disc has to carry out different movements. 15 sub-claims. (UWI) [de

  7. Nuclear power in British politics

    International Nuclear Information System (INIS)

    Pocock, R.F.

    1987-01-01

    The paper concerns the subject of nuclear power in British politics in 1986. The policies of the major political parties towards nuclear power are briefly outlined, along with public attitudes to nuclear energy, Chernobyl, and the rise of the anti-nuclear campaigners. (UK)

  8. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    Enohara, Masami; Araragi, Fujio.

    1980-01-01

    Purpose: To provide a ballast tank, and nuclear power facilities within the containment shell of a pressure resistance structure and a maintenance operator's entrance and a transmission cable cut-off device at the outer part of the containment shell, whereby after the construction, the shell is towed, and installed by self-submerging, and it can be refloated for repairs by its own strength. Constitution: Within a containment shell having a ballast tank and a pressure resisting structure, there are provided nuclear power facilities including a nuclear power generating chamber, a maintenance operator's living room and the like. Furthermore, a maintenance operator's entrance and exit device and a transmission cable cut-off device are provided within the shell, whereby when it is towed to a predetermined a area after the construction, it submerges by its own strength and when any repair inspection is necessary, it can float up by its own strength, and can be towed to a repair dock or the like. (Yoshihara, H.)

  9. The corrosion and corrosion mechanical properties evaluation for the LBB concept in VVERs

    Energy Technology Data Exchange (ETDEWEB)

    Ruscak, M.; Chvatal, P.; Karnik, D.

    1997-04-01

    One of the conditions required for Leak Before Break application is the verification that the influence of corrosion environment on the material of the component can be neglected. Both the general corrosion and/or the initiation and, growth of corrosion-mechanical cracks must not cause the degradation. The primary piping in the VVER nuclear power plant is made from austenitic steels (VVER 440) and low alloy steels protected with the austenitic cladding (VVER 1000). Inspection of the base metal and heterogeneous weldments from the VVER 440 showed that the crack growth rates are below 10 m/s if a low oxygen level is kept in the primary environment. No intergranular cracking was observed in low and high oxygen water after any type of testing, with constant or periodic loading. In the framework of the LBB assessment of the VVER 1000, the corrosion and corrosion mechanical properties were also evaluated. The corrosion and corrosion mechanical testing was oriented predominantly to three types of tests: stress corrosion cracking tests corrosion fatigue tests evaluation of the resistance against corrosion damage. In this paper, the methods used for these tests are described and the materials are compared from the point of view of response on static and periodic mechanical stress on the low alloyed steel 10GN2WA and weld metal exposed in the primary circuit environment. The slow strain rate tests and static loading of both C-rings and CT specimens were performed in order to assess the stress corrosion cracking characteristics. Cyclic loading of CT specimens was done to evaluate the kinetics of the crack growth under periodical loading. Results are shown to illustrate the approaches used. The data obtained were evaluated also from the point of view of comparison of the influence of different structure on the stress corrosion cracking appearance. The results obtained for the base metal and weld metal of the piping are presented here.

  10. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1988-06-01

    The percentage of electricity generated by nuclear energy in each of the 26 countries that operated nuclear power plants in 1987 is given. The current policy and programs of some of these countries is described. News concerning uranium mining, enrichment, reprocessing and waste management is also included. Data in the form of a generalized status summary for all power reactors (> 30 MWEN) prepared from the nuclear power reactor data files of ANSTO is shown

  11. Nuclear power: the turning tide

    International Nuclear Information System (INIS)

    Riley, P.J.; Warren, D.S.

    1981-01-01

    During 1980 and 1981, opposition to the expansion of the nuclear power generation programme grew from about 45% of the population to approximately 53%. Women, young people and labour voters are the most strongly opposed to nuclear power but among no section of the population is there a clear majority in favour of building more nuclear power stations. (author)

  12. Nuclear power in the EC

    International Nuclear Information System (INIS)

    Charrault, J.C.

    1991-01-01

    Nuclear power accounts for some 35% of electricity production in the European Community (EC). Using a mathematical analysis, based on different scenarios, i.e. low/high electricity demand and nuclear moratorium/revival, various demand forecasts are made. A pragmatic approach, considering conventional power generation pollution problems, forecasts a revival of nuclear power

  13. Overview paper on nuclear power

    International Nuclear Information System (INIS)

    Spiewak, I.; Cope, D.F.

    1980-09-01

    This paper was prepared as an input to ORNL's Strategic Planning Activity, ORNL National Energy Perspective (ONEP). It is intended to provide historical background on nuclear power, an analysis of the mission of nuclear power, a discussion of the issues, the technology choices, and the suggestion of a strategy for encouraging further growth of nuclear power

  14. Nuclear power proliferation

    International Nuclear Information System (INIS)

    Johnson, B.

    1977-01-01

    The nuclear industry is experiencing a multiple crisis in which economic, technical and ethical aspects are blended inextricably. Nuclear hardware costs have everywhere soared far beyond inflation in the last five years, largely as a result of delays in programme completion arising from problems of reactor and fuel cycle. Meanwhile, partly as a result of this cost escalation, there is widespread and growing doubt as to whether capital will be available to finance the electricity generating levels projected by the industry and by governments for the 1990s. The nuclear industry is now in trouble at every stage of the fuel cycle. The industry's difficulties have also revealed a lack of overall - but particularly nuclear - energy strategy at either national or international levels, and a lack of will to create regulations and institutional machinery at either of these levels which might reassure both concerned publics and the energy industries themselves. This paper appraises some of the present limitations of international institutions in achieving control and management of nuclear power. (author)

  15. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    1998-01-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

  16. Management of primary-to-secondary leaks at Loviisa nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Mohnsen, B.; Jaenkaelae, K. [IVO International Ltd, Vantaa (Finland)

    1995-12-31

    The Loviisa Nuclear power plant consisting of two VVER-440 type press water reactor units has been in commercial operation since the late 1970`s. Specific features for VVER-440 reactors are six primary loops with horizontal steam generators and main gate valves. The structure of the horizontal steam generators construction may cause a large primary to secondary leak in case of a break in the cover of the primary collector. An accident where two primary collector covers opened totally and two covers opened partly took place in Rovno, Ukraine January 1982. Primary to secondary leaks are one of the main contributors to the core melt frequency in VVER reactors according to the Loviisa 1 Probabilistic Safety Assessment. The high core damage contribution has set requirements for the development of effective means to cope with all sizes of primary to secondary leaks in the steam generator. A concept for all leak sizes has been developed for Loviisa 1 and 2. The solution includes four main areas which are a new steam generator leakage monitoring system based on nitrogen-16 measurement, an upgraded pressurizer spray system, an increased emergency cooling water reserve and an automated isolation of the defected steam generator.

  17. Management of primary-to-secondary leaks at Loviisa nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Mohnsen, B; Jaenkaelae, K [IVO International Ltd, Vantaa (Finland)

    1996-12-31

    The Loviisa Nuclear power plant consisting of two VVER-440 type press water reactor units has been in commercial operation since the late 1970`s. Specific features for VVER-440 reactors are six primary loops with horizontal steam generators and main gate valves. The structure of the horizontal steam generators construction may cause a large primary to secondary leak in case of a break in the cover of the primary collector. An accident where two primary collector covers opened totally and two covers opened partly took place in Rovno, Ukraine January 1982. Primary to secondary leaks are one of the main contributors to the core melt frequency in VVER reactors according to the Loviisa 1 Probabilistic Safety Assessment. The high core damage contribution has set requirements for the development of effective means to cope with all sizes of primary to secondary leaks in the steam generator. A concept for all leak sizes has been developed for Loviisa 1 and 2. The solution includes four main areas which are a new steam generator leakage monitoring system based on nitrogen-16 measurement, an upgraded pressurizer spray system, an increased emergency cooling water reserve and an automated isolation of the defected steam generator.

  18. Management of primary-to-secondary leaks at Loviisa nuclear power plant

    International Nuclear Information System (INIS)

    Mohnsen, B.; Jaenkaelae, K.

    1995-01-01

    The Loviisa Nuclear power plant consisting of two VVER-440 type press water reactor units has been in commercial operation since the late 1970's. Specific features for VVER-440 reactors are six primary loops with horizontal steam generators and main gate valves. The structure of the horizontal steam generators construction may cause a large primary to secondary leak in case of a break in the cover of the primary collector. An accident where two primary collector covers opened totally and two covers opened partly took place in Rovno, Ukraine January 1982. Primary to secondary leaks are one of the main contributors to the core melt frequency in VVER reactors according to the Loviisa 1 Probabilistic Safety Assessment. The high core damage contribution has set requirements for the development of effective means to cope with all sizes of primary to secondary leaks in the steam generator. A concept for all leak sizes has been developed for Loviisa 1 and 2. The solution includes four main areas which are a new steam generator leakage monitoring system based on nitrogen-16 measurement, an upgraded pressurizer spray system, an increased emergency cooling water reserve and an automated isolation of the defected steam generator

  19. Banning nuclear power at sea

    International Nuclear Information System (INIS)

    Handler, J.

    1993-01-01

    This article argues that now that the East-West conflict is over, nuclear-powered vessels should be retired. Nuclear-powered ships and submarines lack military missions, are expensive to build and operate, generate large amounts of long-lived deadly nuclear waste from their normal operations and when they are decommissioned, and are subject to accidents or deliberate attack which can result in the sinking of nuclear reactors and the release of radiation. With the costs of nuclear-powered vessels mounting, the time has come to ban nuclear power at sea. (author)

  20. The need for nuclear power

    International Nuclear Information System (INIS)

    1977-12-01

    This leaflet examines our energy future and concludes that nuclear power is an essential part of it. The leaflet also discusses relative costs, but it does not deal with social and environmental implications of nuclear power in any detail, since these are covered by other British Nuclear Forum publications. Headings are: present consumption; how will this change in future; primary energy resources (fossil fuels; renewable resources; nuclear); energy savings; availability of fossil fuels; availability of renewable energy resources; the contribution of thermal nuclear power; electricity; costs for nuclear power. (U.K.)

  1. Nuclear power renaissance or demise?

    Energy Technology Data Exchange (ETDEWEB)

    Dossani, Umair

    2010-09-15

    Nuclear power is going through a renaissance or demise is widely debated around the world keeping in mind the facts that there are risks related to nuclear technology and at the same time that is it environmentally friendly. My part of the argument is that there is no better alternative than Nuclear power. Firstly Nuclear Power in comparison to all other alternative fuels is environmentally sustainable. Second Nuclear power at present is at the dawn of a new era with new designs and technologies. Third part of the debate is renovation in the nuclear fuel production, reprocessing and disposal.

  2. Torness: proposed nuclear power station

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  3. Nuclear Power Plant 1996

    International Nuclear Information System (INIS)

    1997-01-01

    Again this year, our magazine presents the details of the conference on Spanish nuclear power plant operation held in February and that was devoted to 1996 operating results. The Protocol for Establishment of a New Electrical Sector Regulation that was signed last December will undoubtedly represent a new challenge for the nuclear industry. By clearing stating that current standards of quality and safety should be maintained or even increased if possible, the Protocol will force the Sector to improve its productivity, which is already high as demonstrated by the results of the last few years described during this conference and by recent sectorial economic studies. Generation of a nuclear kWh that can compete with other types of power plants is the new challenge for the Sector's professionals, who do not fear the new liberalization policies and approaching competition. Lower inflation and the resulting lower interest rates, apart from being representative indices of our economy's marked improvement, will be very helpful in facing this challenge. (Author)

  4. Nuclear power regional analysis

    International Nuclear Information System (INIS)

    Parera, María Delia

    2011-01-01

    In this study, a regional analysis of the Argentine electricity market was carried out considering the effects of regional cooperation, national and international interconnections; additionally, the possibilities of insertion of new nuclear power plants in different regions were evaluated, indicating the most suitable areas for these facilities to increase the penetration of nuclear energy in national energy matrix. The interconnection of electricity markets and natural gas due to the linkage between both energy forms was also studied. With this purpose, MESSAGE program was used (Model for Energy Supply Strategy Alternatives and their General Environmental Impacts), promoted by the International Atomic Energy Agency (IAEA). This model performs a country-level economic optimization, resulting in the minimum cost for the modelling system. Regionalization executed by the Wholesale Electricity Market Management Company (CAMMESA, by its Spanish acronym) that divides the country into eight regions. The characteristics and the needs of each region, their respective demands and supplies of electricity and natural gas, as well as existing and planned interconnections, consisting of power lines and pipelines were taken into account. According to the results obtained through the model, nuclear is a competitive option. (author) [es

  5. Nuclear power for developing countries

    International Nuclear Information System (INIS)

    Hirschmann, H.; Vennemann, J.

    1980-01-01

    The paper describes the energy policy quandary of developing countries and explains why nuclear power plants of a suitable size - the KKW 200 MW BWR nuclear power plant for electric power and/or process steam generation is briefly presented here - have an economic advantage over fossil-fuelled power plants. (HP) [de

  6. Nuclear power in Sweden

    International Nuclear Information System (INIS)

    Wikdahl, C.E.

    1999-01-01

    Sweden uses 16,000 kWh of electricity per person, by far the highest consumption in EU. The reason is a well-developed electricity intensive industry and a cold climate with high share of electric heating. The annual power consumption has for several years been about 140 TWh and a normal year almost 50 per cent is produced by hydro and 50 percent by nuclear. A new legislation, giving the Government the right to ordering the closure nuclear power plants of political reasons without any reference to safety, has been accepted by the Parliament. The new act, in force since January 1, 1998, is a specially tailored expropriation act. Certain rules for the economical compensation to the owner of a plant to be closed are defined in the new act. The common view in the Swedish industry is that the energy conservation methods proposed by the Government are unrealistic. During the first period of about five years the import from coal fired plants in Denmark and Germany is the only realistic alternative. Later natural gas combi units and new bioenergy plants for co-production of heat and power (CHP) might be available. (orig.) [de

  7. Qualification of coupled 3D neutron kinetic/thermal hydraulic code systems by the calculation of a VVER-440 benchmark. Re-connection of an isolated loop

    Energy Technology Data Exchange (ETDEWEB)

    Kotsarev, Alexander; Lizorkin, Mikhail [National Research Centre ' Kurchatov Institute' , Moscow (Russian Federation); Bencik, Marek; Hadek, Jan [UJV Rez, a.s., Rez (Czech Republic); Kozmenkov, Yaroslav; Kliem, Soeren [Helmholtz-Zentrum Dresden-Rossendorf (HZDR) e.V., Dresden (Germany)

    2016-09-15

    The 7th AER dynamic benchmark is a continuation of the efforts to validate the codes systematically for the estimation of the transient behavior of VVER type nuclear power plants. The main part of the benchmark is the simulation of the re-connection of an isolated circulation loop with low temperature in a VVER-440 plant. This benchmark was calculated by the National Research Centre ''Kurchatov Institute'' (with the code ATHLET/BIPR-VVER), UJV Rez (with the code RELAP5-3D {sup copyright}) and HZDR (with the code DYN3D/ATHLET). The paper gives an overview of the behavior of the main thermal hydraulic and neutron kinetic parameters in the provided solutions.

  8. Bradwell Nuclear Power Station

    International Nuclear Information System (INIS)

    1987-01-01

    When built, the Magnox reactors were expected to have operating lifetimes of 20-25 years. In order to satisfy the licensing authorities of their continued safety, long term safety reviews (LTSRs) are being carried out as the reactors reach 20 years of operation. This is the Nuclear Installations Inspectorate's (NII) summary report on Bradwell nuclear power station. The objectives of the LTSR are stated. A description of the plant is followed by an explanation of the statutory position on licensing. The responsibilities of the Central Electricity Generating Board (CEGB) and the NII are defined. From the examination of the CEGB's LTSR it is concluded that this generally confirms the validity of the existing safety case for present operation. However, some recommendations are made as to work required for reactor operation up to 1992. A summary of the NII findings is presented. This includes the reactor pressure circuit integrity, effects of ageing and in-service wear and radiation doses. (U.K.)

  9. Perspectives of nuclear power plants

    International Nuclear Information System (INIS)

    Vajda, Gy.

    2001-01-01

    In several countries the construction of nuclear power plants has been stopped, and in some counties several plants have been decommissioned or are planned to. Therefore, the question arises: have nuclear power plants any future? According to the author, the question should be reformulated: can mankind survive without nuclear power? To examine this challenge, the global power demand and its trends are analyzed. According to the results, traditional energy sources cannot be adequate to supply power. Therefore, a reconsideration of nuclear power should be imminent. The economic, environmental attractions are discussed as opposite to the lack of social support. (R.P.)

  10. Nuclear Power Today and Tomorrow

    International Nuclear Information System (INIS)

    Bychkov, Alexander

    2013-01-01

    Worldwide, with 437 nuclear power reactors in operation and 68 new reactors under construction, nuclear power's global generating capacity reached 372.5 GW(e) at the end of 2012. Despite public scepticism, and in some cases fear, which arose following the March 2011 Fukushima Daiichi nuclear accident, two years later the demand for nuclear power continues to grow steadily, albeit at a slower pace. A significant number of countries are pressing ahead with plans to implement or expand their nuclear power programmes because the drivers toward nuclear power that were present before Fukushima have not changed. These drivers include climate change, limited fossil fuel supply, and concerns about energy security. Globally, nuclear power looks set to continue to grow steadily, although more slowly than was expected before the Fukushima Daiichi nuclear accident. The IAEA's latest projections show a steady rise in the number of nuclear power plants in the world in the next 20 years. They project a growth in nuclear power capacity by 23% by 2030 in the low projection and by 100% in the high projection. Most new nuclear power reactors planned or under construction are in Asia. In 2012 construction began on seven nuclear power plants: Fuqing 4, Shidaowan 1, Tianwan 3 and Yangjiang 4 in China; Shin Ulchin 1 in Korea; Baltiisk 1 in Russia; and Barakah 1 in the United Arab Emirates. This increase from the previous year's figures indicates an on-going interest and commitment to nuclear power and demonstrates that nuclear power is resilient. Countries are demanding new, innovative reactor designs from vendors to meet strict requirements for safety, national grid capacity, size and construction time, which is a sign that nuclear power is set to keep growing over the next few decades.

  11. Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

    Science.gov (United States)

    Ternovykh, Mikhail; Tikhomirov, Georgy; Saldikov, Ivan; Gerasimov, Alexander

    2017-09-01

    Decay heat power of actinides and fission products from spent nuclear fuel of power VVER-1000 type reactors at long-term storage is calculated. Two modes of storage are considered: mode in which single portion of actinides or fission products is loaded in storage facility, and mode in which actinides or fission products from spent fuel of one VVER reactor are added every year in storage facility during 30 years and then accumulated nuclides are stored without addition new nuclides. Two values of fuel burnup 40 and 70 MW·d/kg are considered for the mode of storage of single fuel unloading. For the mode of accumulation of spent fuel with subsequent storage, one value of burnup of 70 MW·d/kg is considered. Very long time of storage 105 years accepted in calculations allows to simulate final geological disposal of radioactive wastes. Heat power of fission products decreases quickly after 50-100 years of storage. The power of actinides decreases very slow. In passing from 40 to 70 MW·d/kg, power of actinides increases due to accumulation of higher fraction of 244Cm. These data are important in the back end of fuel cycle when improved cooling system of the storage facility will be required along with stronger radiation protection during storage, transportation and processing.

  12. Decay heat power of spent nuclear fuel of power reactors with high burnup at long-term storage

    Directory of Open Access Journals (Sweden)

    Ternovykh Mikhail

    2017-01-01

    Full Text Available Decay heat power of actinides and fission products from spent nuclear fuel of power VVER-1000 type reactors at long-term storage is calculated. Two modes of storage are considered: mode in which single portion of actinides or fission products is loaded in storage facility, and mode in which actinides or fission products from spent fuel of one VVER reactor are added every year in storage facility during 30 years and then accumulated nuclides are stored without addition new nuclides. Two values of fuel burnup 40 and 70 MW·d/kg are considered for the mode of storage of single fuel unloading. For the mode of accumulation of spent fuel with subsequent storage, one value of burnup of 70 MW·d/kg is considered. Very long time of storage 105 years accepted in calculations allows to simulate final geological disposal of radioactive wastes. Heat power of fission products decreases quickly after 50-100 years of storage. The power of actinides decreases very slow. In passing from 40 to 70 MW·d/kg, power of actinides increases due to accumulation of higher fraction of 244Cm. These data are important in the back end of fuel cycle when improved cooling system of the storage facility will be required along with stronger radiation protection during storage, transportation and processing.

  13. HOMOGENEOUS NUCLEAR POWER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  14. Nuclear power plant disasters

    International Nuclear Information System (INIS)

    Trott, K.R.

    1979-01-01

    The possibility of a nuclear power plant disaster is small but not excluded: in its event, assistance to the affected population mainly depends on local practitioners. Already existing diseases have to be diagnosed and treated; moreover, these physicians are responsible for the early detection of those individuals exposed to radiation doses high enough to induce acute illness. Here we present the pathogenesis, clinical development and possible diagnostic and therapeutical problems related to acute radiation-induced diseases. The differentiation of persons according to therapy need and prognosis is done on the sole base of the clinical evidence and the peripheral blood count. (orig.) [de

  15. Nuclear power plant diagnostics

    International Nuclear Information System (INIS)

    Hollo, E.; Siklossy, P.

    1982-01-01

    The cooling circuit vibration diagnostic system of the Block 1 of the Paks nuclear power station is described. The automatic online vibration monitoring system consisting presently of 42 acceleration sensors and 9 pressure fluctuation sensors, which could be extended, performs both global and local inspection of the primary cooling circuit and its components. The offline data processing system evaluates the data for failure mode analysis. The software under development will be appropriate for partial preliminary identification of failure reasons during their initial phases. The installation experiences and the preliminary results during the hot operational testing of Block 1 are presented. (Sz.J.)

  16. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Scurr, I.F.; Silver, J.M.

    1990-01-01

    Australian Nuclear Science and Technology Organization maintains an ongoing assessment of the world's nuclear technology developments, as a core activity of its Strategic Plan. This publication reviews the current status of the nuclear power and the nuclear fuel cycle in Australia and around the world. Main issues discussed include: performances and economics of various types of nuclear reactors, uranium resources and requirements, fuel fabrication and technology, radioactive waste management. A brief account of the large international effort to demonstrate the feasibility of fusion power is also given. 11 tabs., ills

  17. The Role of Nuclear Power in Hungary, a Regional Comparison

    International Nuclear Information System (INIS)

    Cserhati, A.

    2016-01-01

    The presentation and paper are giving the broad picture on the country's nuclear competence and the atomic electricity production in international appraisal. The Central and Eastern Europe (CEE) region nuclear statistics were compiled by the author and appear in compact, easily understandable graphical form: Worldwide and regional figures of nuclear share for electricity generation. Types of operating nuclear power plant units. Age and performance (cumulative load factors) of units. Power uprate history of affected units. Status of the long term operation (or by earlier name: lifetime extension) projects. The cycle length expansion is a transition from 12 to 15 month fuel cycle, as a pioneering initiative of Paks NPP for efficiency increase of VVER-440 type. New build trends will be outlined in general for the world, Europe and the CEE region. The last topic is the Hungarian path to Paks-5 and Paks-6 completion. Preparatory projects (Teller and Levai), establishment of the Paks II company. Potential suppliers and types for the new build (AREVA EPR, ATMEA Atmea1, KEPCO/KHNP APR1400, Rosatom AES-2006, Toshiba-Westinghouse AP1000). Intergovernmental agreement with Russian Federation for building of two 1200 MW units. Financing of 80 percent of the investment by Russian loan with moderate interest rates. Planned schedule of the new build. EC infringement procedures. Public acceptance. (author).

  18. Fusion of eastern and western technology in VVER 1000 NPP upgrade

    International Nuclear Information System (INIS)

    Ubra, O.; Fleischhans, J.; Kveton, M.

    1997-01-01

    An extensive modernization program upgrading two units of VVER 1000 type of the Czech nuclear power plant (NPP) Temelin to meet the latest international standards is presented. The program is based primarily on combination of eastern and western technology and it has been implemented during plant construction. The NPP Temelin was originally designed according to the standards of the former Soviet Union. After a series of reviews in the 1990s, a decision was made by the Temelin management of upgrade the design of the plant, including the supply of fuel and instrumentation and control system by a western company. The adoption of western technology and practices has helped to solve a large number of IAEA safety issues related to design and operation of VVER 1000 NPP. Details on the current Temelin design and other related safety matters are presented

  19. Nuclear power generation modern power station practice

    CERN Document Server

    1971-01-01

    Nuclear Power Generation focuses on the use of nuclear reactors as heat sources for electricity generation. This volume explains how nuclear energy can be harnessed to produce power by discussing the fundamental physical facts and the properties of matter underlying the operation of a reactor. This book is comprised of five chapters and opens with an overview of nuclear physics, first by considering the structure of matter and basic physical concepts such as atomic structure and nuclear reactions. The second chapter deals with the requirements of a reactor as a heat source, along with the diff

  20. On nuclear power plant uprating

    International Nuclear Information System (INIS)

    Ho, S. Allen; Bailey, James V.; Maginnis, Stephen T.

    2004-01-01

    Power uprating for commercial nuclear power plants has become increasingly attractive because of pragmatic reasons. It provides quick return on investment and competitive financial benefits, while involving low risks regarding plant safety and public objection. This paper briefly discussed nuclear plant uprating guidelines, scope for design basis analysis and engineering evaluation, and presented the Salem nuclear power plant uprating study for illustration purposes. A cost and benefit evaluation of the Salem power uprating was also included. (author)

  1. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  2. Validation of computer codes and modelling methods for giving proof of nuclear saefty of transport and storage of spent VVER-type nuclear fuels. Part 1. Purposes and goals of the project. Final report

    International Nuclear Information System (INIS)

    Buechse, H.; Langowski, A.; Lein, M.; Nagel, R.; Schmidt, H.; Stammel, M.

    1995-01-01

    The report gives the results of investigations on the validation of computer codes used to prove nuclear safety during transport and storage of spent VVER - fuel of NPP Greifswald and Rheinsberg. Characteristics of typical spent fuel (nuclide concentration, neutron source strength, gamma spectrum, decay heat) - calculated with several codes - and dose rates (e.g. in the surrounding of a loaded spent fuel cask) - based on the different source terms - are presented. Differences and their possible reasons are discussed. The results show that despite the differences in the source terms all relevant health physics requirements are met for all cases of source term. The validation of the criticality code OMEGA was established by calculation of appr. 200 critical experiments of LWR fuel, including VVER fuel rod arrangements. The mean error of the effective multiplication factor k eff is -0,01 compared to the experiment for this area of applicability. Thus, the OMEGA error of 2% assumed in earlier works has turned out to be sufficiently conservative. (orig.) [de

  3. Nuclear power and nuclear safety 2011

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Aage, H.K.; Kampmann, D.; Nystrup, P.E.; Thomsen, J.

    2012-07-01

    The report is the ninth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2011 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the Fukushima accident. (LN)

  4. Nuclear power and nuclear safety 2009

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Nystrup, P.E.; Thorlaksen, B.

    2010-05-01

    The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

  5. Nuclear power and nuclear safety 2012

    International Nuclear Information System (INIS)

    Lauritzen, B.; Nonboel, E.; Israelson, C.; Kampmann, D.; Nystrup, P.E.; Thomsen, J.

    2013-11-01

    The report is the tenth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is prepared in collaboration between DTU Nutech and the Danish Emergency Management Agency. The report for 2012 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the results of the EU stress test. (LN)

  6. Development and qualification of a thermal-hydraulic nodalization for modeling station blackout accident in PSB-VVER test facility

    Energy Technology Data Exchange (ETDEWEB)

    Saghafi, Mahdi [Department of Energy Engineering, Sharif University of Technology, Azadi Avenue, Tehran (Iran, Islamic Republic of); Ghofrani, Mohammad Bagher, E-mail: ghofrani@sharif.edu [Department of Energy Engineering, Sharif University of Technology, Azadi Avenue, Tehran (Iran, Islamic Republic of); D’Auria, Francesco [San Piero a Grado Nuclear Research Group (GRNSPG), University of Pisa, Via Livornese 1291, San Piero a Grado, Pisa (Italy)

    2016-07-15

    Highlights: • A thermal-hydraulic nodalization for PSB-VVER test facility has been developed. • Station blackout accident is modeled with the developed nodalization in MELCOR code. • The developed nodalization is qualified at both steady state and transient levels. • MELCOR predictions are qualitatively and quantitatively in acceptable range. • Fast Fourier Transform Base Method is used to quantify accuracy of code predictions. - Abstract: This paper deals with the development of a qualified thermal-hydraulic nodalization for modeling Station Black-Out (SBO) accident in PSB-VVER Integral Test Facility (ITF). This study has been performed in the framework of a research project, aiming to develop an appropriate accident management support tool for Bushehr nuclear power plant. In this regard, a nodalization has been developed for thermal-hydraulic modeling of the PSB-VVER ITF by MELCOR integrated code. The nodalization is qualitatively and quantitatively qualified at both steady-state and transient levels. The accuracy of the MELCOR predictions is quantified in the transient level using the Fast Fourier Transform Base Method (FFTBM). FFTBM provides an integral representation for quantification of the code accuracy in the frequency domain. It was observed that MELCOR predictions are qualitatively and quantitatively in the acceptable range. In addition, the influence of different nodalizations on MELCOR predictions was evaluated and quantified using FFTBM by developing 8 sensitivity cases with different numbers of control volumes and heat structures in the core region and steam generator U-tubes. The most appropriate case, which provided results with minimum deviations from the experimental data, was then considered as the qualified nodalization for analysis of SBO accident in the PSB-VVER ITF. This qualified nodalization can be used for modeling of VVER-1000 nuclear power plants when performing SBO accident analysis by MELCOR code.

  7. Nuclear power. Volume 1. Nuclear power plant design

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

  8. International nuclear power status 2001

    International Nuclear Information System (INIS)

    Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L.

    2002-04-01

    This report is the eighth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2001, the report contains: 1) General trends in the development of nuclear power; 2) Nuclear terrorism; 3) Statistical information on nuclear power production (in 2000); 4) An overview of safety-relevant incidents in 2001; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

  9. International nuclear power status 2002

    International Nuclear Information System (INIS)

    Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L.

    2003-03-01

    This report is the ninth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2002, the report contains: 1) General trends in the development of nuclear power; 2) Decommissioning of the nuclear facilities at Risoe National Laboratory: 3) Statistical information on nuclear power production (in 2001); 4) An overview of safety-relevant incidents in 2002; 5) The development in West Europe; 6) The development in East Europe; 7) The development in the rest of the world; 8) Development of reactor types; 9) The nuclear fuel cycle; 10) International nuclear organisations. (au)

  10. Problems and prospects of nuclear power plants construction

    Directory of Open Access Journals (Sweden)

    Pergamenshhik Boris Klimentyevich

    2014-02-01

    Full Text Available 60 years ago, in July 1954 in the city of Obninsk near Moscow the world's first nuclear power plant was commissioned with a capacity of 5 MW. Today more than 430 nuclear units with a total capacity of almost 375000 MW are in operation in dozens of the countries worldwide. 72 electrical power units are currently under construction, 8 of them are located in the Russian Federation. There will be no alternative to nuclear energy in the coming decades. Among the factors contributing to the construction of nuclear power plants reckon limited fossil fuel supply, lack of air and primarily carbon dioxide emissions. The holding back factors are breakdown, hazard, radioactive wastes, high construction costs and long construction period. Nuclear accidents in the power plant of «Three-Mile-Island» in the USA, in Chernobyl and in Japan have resulted in termination of construction projects and closure of several nuclear power plants in the Western Europe. The safety systems have become more complex, material consumption and construction costs have significantly increased. The success of modern competing projects like EPR-1600, AP1000, ABWR, national ones AES-2006 and VVER-TOI, as well as several others, depends not only on structural and configuration but also on construction and technological solutions. The increase of the construction term by one year leads to growth of estimated total costs by 3—10 %. The main improvement potentials include external plate reinforcement, pre-fabricated large-block assembly, production and installation of the equipment packages and other. One of the crucial success factors is highly skilled civil engineers training.

  11. Competitiveness of nuclear power generation

    International Nuclear Information System (INIS)

    Sumi, Yoshihiko

    1998-01-01

    In view of the various merits of nuclear power generation, Japanese electric utilities will continue to promote nuclear power generation. At the same time, however, it is essential to further enhance cost performance. Japanese electric utilities plan to reduce the cost of nuclear power generation, such as increasing the capacity factor, reducing operation and maintenance costs, and reducing construction costs. In Asia, nuclear power will also play an important role as a stable source of energy in the future. For those countries planning to newly introduce nuclear power, safety is the highest priority, and cost competitiveness is important. Moreover, financing will be an essential issue to be resolved. Japan is willing to support the establishment of nuclear power generation in Asia, through its experience and achievements. In doing this, support should not only be bilateral, but should include all nuclear nations around the Pacific rim in a multilateral support network. (author)

  12. Ecological problems of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Babaev, N S; Demin, V F; Kuz' min, I I; Stepanchikov, V I [Gosudarstvennyj Komitet po Ispol' zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii

    1978-10-01

    Modern power sources including nuclear one are characterized. Basic information on radiation protection of man and biosphere is presented. Problems of radiation effect of nuclear fuel cycle enterprises on population and environment are discussed. Comparative evaluation of nuclear and thermal power effect on biosphere is made. It is shown that nuclear power is the safest power source at the present development state. The conclusion is drawn that the use of nuclear energy controlled and limited by scientifically founded norms does not present radiation hazard for population and environment.

  13. Nuclear power in western society

    International Nuclear Information System (INIS)

    Franklin, N.L.

    1977-01-01

    The degree to which problems of public acceptance have contributed to the slowdown in progress of nuclear power in Western European countries and the USA is discussed. Some of the effects on the nuclear power industry, i.e. the electrical utilities, the power station suppliers, and the fuel cycle contractors are described. The problem of the lack of public acceptance is examined by consideration of four areas: the position of the employee working in nuclear installations, opposition from the local community, the question of terrorism and its impact on nuclear policy, and finally, what is felt to constitute the greatest anxiety concerning nuclear power, that of proliferation. (U.K.)

  14. Validation studies of thermal-hydraulic code for safety analysis of nuclear power plants

    International Nuclear Information System (INIS)

    Haapalehto, T.

    1995-01-01

    The thesis gives an overview of the validation process for thermal-hydraulic system codes and it presents in more detail the assessment and validation of the French code CATHARE for VVER calculations. Three assessment cases are presented: loop seal clearing, core reflooding and flow in a horizontal steam generator. The experience gained during these assessment and validation calculations has been used to analyze the behavior of the horizontal steam generator and the natural circulation in the geometry of the Loviisa nuclear power plant. Large part of the work has been performed in cooperation with the CATHARE-team in Grenoble, France. (41 refs., 11 figs., 8 tabs.)

  15. The complex approach to the flow accelerated cracking in Czech nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ruscak, M; Splichal, K; Kaplan, J [Nuclear Research Institute, Rez (Czech Republic)

    1994-12-31

    The paper shows the approach of NRI to the problems of flow accelerated cracking of the secondary piping in VVER nuclear power plants. The utilization of the CHECMATE family codes is described in the framework of other activities to support the prediction and evaluation of damage. The code allows the effects of parameters such as temperature, geometry, mass transport conditions, void fraction and material composition to be assessed. The influence of exact measurement of chromium content is discussed. 2 refs., 6 figs., 1 tab.

  16. The complex approach to the flow accelerated cracking in Czech nuclear power plants

    International Nuclear Information System (INIS)

    Ruscak, M.; Splichal, K.; Kaplan, J.

    1994-01-01

    The paper shows the approach of NRI to the problems of flow accelerated cracking of the secondary piping in VVER nuclear power plants. The utilization of the CHECMATE family codes is described in the framework of other activities to support the prediction and evaluation of damage. The code allows the effects of parameters such as temperature, geometry, mass transport conditions, void fraction and material composition to be assessed. The influence of exact measurement of chromium content is discussed. 2 refs., 6 figs., 1 tab

  17. Is nuclear power and alternative?

    International Nuclear Information System (INIS)

    Lejon, E.

    1996-01-01

    In this chapter of the book author deals with the historical background for the nuclear energy power. Some statistical data about nuclear power stations as well as on radioactive wastes are given. The Chernobyl catastrophe is described. Author thinks that nuclear energy is not safe and it has no perspective in future

  18. Meeting the physics design challenges of modern LWRs being inducted into the Indian nuclear power programme

    International Nuclear Information System (INIS)

    Jagannathan, V.; Pal, Usha; Karthikeyan, R.; Raj, Devesh; Srivastava, Argala; Khan, Suhail Ahmad

    2007-01-01

    Indian nuclear power programme started with the two Boiling Water Reactors (BWR) of 210 MWe capacity at Tarapur. Two VVER-1000 MWe reactors which are Pressurized Water Reactors (PWR) of Russian design are being constructed at Kudankulam, Tamilnadu and are expected to be commissioned by end 2008. There may be also a possibility of inducting some western PWRs in future. These reactors belong to the category of light water reactors (LWR). The LWRs are compact and have complex physical characteristics distinctly different from those of the Pressurized Heavy Water Reactors (PHWR) which, currently form the mainstay of our indigenous nuclear power programme. The physics design and analysis capability for the modern LWRs (BWR, PWR and VVER) has been developed at Light Water Reactors Physics Section, BARC. This paper presents the current state of art in this key technology area to meet the physics design and operation challenges when LWRs would be inducted in a major way into the Indian nuclear power programme and commence operating in the coming decades. (author)

  19. Nuclear power and the nuclear fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-07-01

    The IAEA is organizing a major conference on nuclear power and the nuclear fuel cycle, which is to be held from 2 to 13 May 1977 in Salzburg, Austria. The programme for the conference was published in the preceding issue of the IAEA Bulletin (Vol.18, No. 3/4). Topics to be covered at the conference include: world energy supply and demand, supply of nuclear fuel and fuel cycle services, radioactivity management (including transport), nuclear safety, public acceptance of nuclear power, safeguarding of nuclear materials, and nuclear power prospects in developing countries. The articles in the section that follows are intended to serve as an introduction to the topics to be discussed at the Salzburg Conference. They deal with the demand for uranium and nuclear fuel cycle services, uranium supplies, a computer simulation of regional fuel cycle centres, nuclear safety codes, management of radioactive wastes, and a pioneering research project on factors that determine public attitudes toward nuclear power. It is planned to present additional background articles, including a review of the world nuclear fuel reprocessing situation and developments in the uranium enrichment industry, in future issues of the Bulletin. (author)

  20. An experimental investigation of 1% SBLOCA on PSB-VVER test facility

    Energy Technology Data Exchange (ETDEWEB)

    Lipatov, I.A.; Dremin, G.I.; Galtchanskaia, S.A.; Gorbunov, Yu.S. [Electrogorsk Research and Engineering Center, EREC, Electrogorsk (Russian Federation); Elkin, I.V. [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    2001-07-01

    The paper presents the results of the three tests carried out in the PSB-VVER large-scale integral test facility. The PSB-VVER test facility is a four loop, full pressure scaled down model bearing structural similarities to the primary system of the NRP with VVER-1000 Russian design reactor. Volume-power scale is 1/300 while elevation scale is 1/1. (orig.)

  1. Nuclear Power Division

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    The 1981-85 research program planned by the Nuclear Power Division of EPRI places major emphasis on the assurance of safety and realiability of light water reactors (LWRs). Of high priority is a better knowledge of LWR-system behavior undeer abnormal conditions and the behavior of structural materials used for pressure vessels, piping, and large nuclear-plant components. Strong emphasis is also placed on achieving the most-effective performance and utilization of nuclear fuels and improving the corrosion resistance of pressurized-water-reactor steam generators. Efforts are underway to reduce radiation exposure and outage duration and to investigate the human factors involved in plant operation and maintenance. Substantial emphasis is placed on short-range goals designed to achieve useful results in the next two to seven years. The Division's mid- and long-range goal is to improve the use of fissionable and fertile materials and aid in the realization of other reactor systems. A series of general goals, categorized into three time frames and planned expenditures shows the trend of work to be undertaken. 53 figures

  2. Nuclear power in Spain

    International Nuclear Information System (INIS)

    Koryakin, Yu.I.

    1977-01-01

    The present states of nuclear power in Spain is shortly surveyed. Data are provided on NPPs currently in operation, under construction, designed and planned. In line with the 10-year ''National programme of electricity supply'' a major and all increasing part of the electricity generation growth is to be ensured by NPPs and to account for more than 50% by the end of the period (1987). Out of the 7 units of NPPs now under construction, 6 units utilize PWR reactors and only 1 unit- a BWR reactor. The roles of private and public sectors are noted. Main characteristics of the ''ENSA'' plant now under construction are provided where components of NPPs with PWR and BWR reactors will be fabricated. Major developments in the fields of mining, milling and extraction of U from lignites, U enrichment, fuel fabrication and spent fuel reprocessing are considered. Measures now taken to improve the licensing procedure, surveillance of NPPs and personnel training are to advance the nuclear power development programme in the country

  3. VVER-specific features regarding core degradation - Status Report

    International Nuclear Information System (INIS)

    Hozer, Z.; Trambauer, K.; Duspiva, J.

    1999-01-01

    The objective of this report is to compare VVER reactors to pressurised water reactors (PWRs) of Western design from the point of view of core degradation phenomena using the terminology which was applied to the systematisation of severe accident phenomena in earlier CSNI reports. In the following the acronym 'PWR' is used for a PWR of Western design. The basic design features are described and the most important parameters are summarised in order to identify the differences between the two reactor types. In some specific cases the comparison shows more similarities with boiling water reactors (BWRs) than with PWRs. The known VVER experimental support is also summarised. RBMKs are not included in this report, as this reactor type is not operated in OECD countries, furthermore its design is completely different from those of VVERs and PWRs. The scope of this report is limited to in-vessel severe fuel damage phenomena. Neither thermal hydraulic processes involving no core degradation, nor containment phenomena, are discussed in detail. The VVER (water-cooled water-moderated power reactor) is a pressurised light water reactor of Soviet design. It operates on the same principles as a Western PWR reactor and uses similar technological systems. The primary coolant is pressurised water, which heats up in the reactor core and steam is produced on the secondary side of steam generators. The comparison of basic geometrical and technological parameters pointed out some differences between a PWR and a VVER, but it should be noted that differences exist even between two Western PWRs of different design. The VVER reactors are special types of PWRs, the most important design features of which are the horizontal steam generators and the hexagonal core structure. Similarity between PWR and VVER reactors was found in the comparison of dominant accidents sequences leading to core melt. The accident progression sequence consists of the same steps for VVERs and PWRs. The larger water

  4. Nuclear power: how and why

    International Nuclear Information System (INIS)

    1982-10-01

    The subject is discussed, with special reference to the United Kingdom, under the headings: the need for nuclear power; Britain's experience (nuclear reactors); the nuclear process; how fuel is made; recycling fuel; wastes and their treatment; decommissioning; fast reactors; nuclear fusion; safety and radiation. (U.K.)

  5. Nuclear power plant emergency preparedness

    International Nuclear Information System (INIS)

    2005-01-01

    The guide sets forth detailed requirements on how the licensee of a nuclear power plant shall plan, implement and maintain emergency response arrangements. The guide is also applied to nuclear material and nuclear waste transport in situations referred to in guide YVL 6.5. Requirements on physical protection are presented in a separate guide of Finnish Radiation and Nuclear Safety Authority (STUK)

  6. Nuclear power without nuclear weapons

    International Nuclear Information System (INIS)

    Kaiser, K.; Klein, F.J.

    1982-01-01

    In this study leading experts summarize the work of a working group meeting during several years, and they represent the state of the art of the international discussion about the non-proliferation of nuclear weapons. The technical basis of proliferation, the relations between energy policy and nuclear energy, as well as the development of the non-proliferation system up to the present are thoroughly studied. Special attention is paid to the further development of the instruments of the non-proliferation policy, and approaches and ways to improving the control of the fuel cycle, e.g. by means of multinational methods or by improving the control requirements are analyzed. Also the field of positive inducements and negative sanctions to prevent the proliferation as well as the question of ensured supply are elucidated in detail. A further section then analyzes the functions of the international organizations active in this field and the nuclear policy of the most important western industrial nations, the RGW-states and the threshold countries of the Third World. This volume pays special attention to the nuclear policy of the Federal Republic of Germany and to the possibilities and necessities of a further development of the non-proliferation policy. (orig.) [de

  7. Canada's steps towards nuclear power

    International Nuclear Information System (INIS)

    Lewis, W.B.

    1958-09-01

    This paper describes the policy development of nuclear power in Canada. Canada has a natural abundance of coal, oil, natural gas, water power and uranium. It was recognized that the demand for nuclear power would only materialize if it met an economically competitive range.

  8. Fields of nuclear power application

    International Nuclear Information System (INIS)

    Laue, H.J.

    1975-01-01

    The paper deals with nuclear power application in fields different from electricity generation, i.e. district heating, sea water desalination, coal gasification and nuclear splitting of water. (RW) [de

  9. Nuclear power: a British view

    International Nuclear Information System (INIS)

    Shaw, G.

    1985-01-01

    The subject is covered in sections, entitled: importance of nuclear power; the problems; fuel availability (uranium purchasing policy; uranium market; longer-term demand; enrichment market; fast reactor); non-proliferation and nuclear export policy; public acceptability. (U.K.)

  10. Services for nuclear power stations

    International Nuclear Information System (INIS)

    Fremann, M.; Ryckelynck

    1987-01-01

    This article gives an information as complete as possible about the activities of the french nuclear industry on the export-market. It describes the equipment and services available in the field of services for nuclear power stations [fr

  11. The benefits of nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This article briefly outlines the benefits of nuclear power. Nuclear electricity generation is compared with fossil-fuel generated electricity in terms of environmental pollution and accidents and disease hazards

  12. Nuclear power in Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, S. (Sussex Univ., Brighton (UK). Science Policy Research Unit)

    1991-01-01

    The main aim of this article is that of illustrating the experience of the use of nuclear power in Eastern Europe in order to estimate the degree of adequacy or inadequacy of COMECON's nuclear technology. The author examines four areas of interest concerning: the feasibility of new orders for nuclear plants in Eastern Europe; the pros and cons of completing half-built nuclear power plants; current policy towards existing nuclear power plants; and a review of the available evidence on the operating performance of plants in Eastern Europe. The common belief that the nuclear power experience had by old COMECON countries is uniformly bad does not seem to be fully supported by the limited evidence available. In the author's opinion, the prospects for a successful nuclear power industry in these countries depends on a series on interdependent factors among which, human skills hold a prominent position.

  13. Fuel for new Russian reactor VVER-1200

    Energy Technology Data Exchange (ETDEWEB)

    Vasilchenko, Ivan Nikitovich [GRPress, 21, Ordzhonikidze Street, 142103 Podolsk, Moscow region (Russian Federation)

    2009-06-15

    A great program is accepted in Russia on increasing the nuclear power capacities. The basis of the program is commissioning of VVER-1200 Units of AES-2006 design. This is largely an evolutionary project of VVER-1000 reactor plant. It is referred also to reactor core. The plant electric power is increased due to increase in the reactor thermal power and forcing the main parameters and the efficiency increase. With this, reactor pressure increases from 15,7 to 16,2 MPa. The reactor inlet temperature increases from 290 deg. C to 298 deg. C, and outlet temperature from 319 deg. C to 329 deg. C. In a set of the design for four Units (2 Units at Novovoronezh NPP and 2 Units at Leningrad NPP) two base fuel cycles are developed: 5 year and 3 year. To provide such fuel cycles the fuel loading is increased by 8 tons, as compared to VVER-1000 base design, due to fuel column increase by 200 mm and change of fuel pellet sizes. In the mentioned fuel cycles the average burnup in the unloaded batch will be {approx}57 MW.day/kg U and 52 MW.day/kg U (maximum burnup over FAs is 64,5 MW.day/kg U and 60,3 MW.day/kg U), respectively. Specific consumption of natural uranium will be reduced by 5% as compared to that reached at VVER-1000 reactor. In spite of increase in Unit power the limiting permissible fuel rod linear heat rate is decreased from 448 W/cm to 420 W/cm. Refueling pattern is used with small neutron escape. The safety criteria are used that were established for VVER-1000, except for those that did not comply with EUR. For instance, the number of leaky fuel rods under accident is limited. The more stringent requirements are stated on efficiency margin of CPS rods for reactor shutdown that is ensured by the increased number of CPS rods. The well-proved design of fuel assembly TVS-2 and its close modification TVS-2M, operated at Balakovo NPP and Rostov NPP, is laid down in the basis of the core design. The load-carrying component of this structure is a rigid skeleton formed by

  14. Nuclear power plants

    International Nuclear Information System (INIS)

    Ushijima, Susumu.

    1984-01-01

    Purpose: To enable to prevent the degradation in the quality of condensated water in a case where sea water leakage should occur in a steam condenser of a BWR type nuclear power plant. Constitution: Increase in the ion concentration in condensated water is detected by an ion concentration detector and the leaking factor of sea water is calculated in a leaking factor calculator. If the sea water leaking factor exceeds a predetermined value, a leak generation signal is sent from a judging device to a reactor power control device to reduce the reactor power. At ehe same tiem, the leak generation signal is also sent to a steam condenser selection and isolation device to interrupt the sea water pump of a specified steam condenser based on the signal from the ion concentration detector, as well as close the inlet and outlet valves while open vent and drain valves to thereby forcively discharge the sea water in the cooling water pipes. This can keep the condensate desalting device from ion breaking and prevent the degradation in the quality of the reactor water. (Horiuchi, T.)

  15. Nuclear power. Volume 2. Nuclear power project management

    International Nuclear Information System (INIS)

    Pedersen, E.S.

    1978-01-01

    NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 2 contains the following chapters: (1) review of nuclear power plants; (2) licensing procedures; (3) safety analysis; (4) project professional services; (5) quality assurance and project organization; (6) construction, scheduling, and operation; (7) nuclear fuel handling and fuel management; (8) plant cost management; and (9) conclusion

  16. Problems of nuclear power development

    International Nuclear Information System (INIS)

    Panasenkov, A.

    1982-01-01

    The answers are reported given by the head of the department for peaceful uses of nuclear energy of the secretariat of the Council of Mutual Economic Assistance, Mr. A. Pasenkov to questions given him in an interview for APN. The questions were related to the current state and development of world nuclear power, nuclear safety and the attitude of the general public to nuclear power in the West and in the CMEA countries. (B.S.)

  17. Nuclear power in East Asia

    International Nuclear Information System (INIS)

    Abelson, P.H.

    1996-01-01

    This editorial discusses the shifting dominance in the nuclear reactor technology from the USA to new leadership in East Asia. With the expanding economies and electricity demand, Design, construction and operation of a large number of nuclear power plants in east Asia will support nuclear engineers, technologist, manufacturing facilities, and potential weapons experts. In contrast, the cessation of construction of power reactors in the US is leading to deminished nuclear capabilities

  18. Status and prospects of the core surveillance system SCORPIO-VVER in Czech Republic and Slovakia

    International Nuclear Information System (INIS)

    Molnar, J.; Vocka, R.

    2011-01-01

    The SCORPIO-VVER core monitoring system has proved since the first installation at Dukovany NPP in 1999 to be a valuable tool for the reactor operators and reactor physicists. It is now installed on four units of Dukovany NPP (Czech Republic) and two units of Bohunice NPP (Slovak Republic) replacing the original Russian VK3 system. By both Czech and Slovak nuclear regulatory bodies it was licensed as a Technical Specification Surveillance tool. Since it's first installation, the development of SCORPIO-VVER system continues along with the changes in WWER reactors operation. The system is being adapted according the utility needs and several notable improvements in physical modules of the system were introduced. The latest most significant changes were done in connection with implementation of a new digital I and C system, loading of the optimized gadolinium bearing Gd2 fuel assemblies, improvements in the area of core design (neutron physics, core thermal hydraulics and fuel thermal mechanics), adaptation of the system to up-rated unit conditions, in design and methodology of the limit and technical specifications checking (implementation of the on-line shutdown margin calculation to the system) and improvements in the predictive part of the system (Strategy Generator). After the currently finished upgrades (Upgrade 2 at EBO Slovakia in 2009, Upgrade 5 at EDU Czech Republic in 2010) the SCORPIO-VVER is still in focus of Central European nuclear power plants with the road map of modification and implementation up to 2015. In April 2011 the Upgrade 3 at EBO Slovakia has been contracted to support the changed reactor technical specification and for support of the new type of fuel planned to load in 2012. During the summer of 2011 the discussions started with EDU NPP in Czech Republic regarding to the future development of the SCORPIO-VVER system up to 2015. Parallel with the support of current installations at NPPs the project of new installations is ongoing. During

  19. Nuclear power 2005: European report

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    In 2005, nuclear power plants were operated and/or built in eighteen European countries. Thirteen of these countries are members of EU-25. Five of the ten countries joining the European Union on May 1, 2004 operate nuclear power stations. A total of 204 power reactors with a gross power of 181,030 MWe and a net power of 171,8479 MWe were in operation at the end of the year. In 2005, no nuclear power plant was commissioned. Two nuclear power plants were decommissioned in Europe in the course of 2005. In Germany the Obrigheim NPP and in Sweden the Barsebaeck 2 NPP have been permanently shut down due to political decisions. As a result of ongoing technical optimization in some plants, involving increases in reactor power or generator power as well as commissioning of plants of higher capacity, nuclear generating capacity increased by approx. 1.6 GW. In late 2005, five nuclear generating units were under construction in Finland (1), Romania (1), and Russia (3). 148 nuclear power plants were operated in thirteen states of the European Union (EU-25). They had an aggregate gross power of 137,023 MWe and a net power of 130,415 MWe, generating approx. 970 billion gross kWh of electricity in 2005, thus again contributing some 31% to the public electricity supply in the EU-25. In largest share of nuclear power in electricity generation is found in France (80%), followed by 72% in Lithuania, 55% in the Slovak Republic, 55% in Belgium, and 51% in Ukraine. In several countries not operating nuclear power plants of their own, such as Italy, Portugal, and Austria, nuclear power makes considerable contributions to public electricity supply as a result of electricity imports. (All statistical data in the country report apply to 2004 unless indicated otherwise. This is the year for which sound preliminary data are currently available for the states listed.) (orig.)

  20. Discharges from nuclear power stations

    International Nuclear Information System (INIS)

    1991-02-01

    HM Inspectorate of Pollution commissioned, with authorising responsibilities in England and Wales, a study into the discharges of radioactive effluents from Nuclear Power Stations. The study considered arisings from nuclear power stations in Europe and the USA and the technologies to treat and control the radioactive discharges. This report contains details of the technologies used at many nuclear power stations to treat and control radioactive discharges and gives, where information was available, details of discharges and authorised discharge limits. (author)

  1. Energy situation and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Megahid, M R [Reactor and Neutron physics Department Nuclear Research Center A.E., Cairo (Egypt)

    1997-12-31

    A brief general review is given concerning the requirements of power throughout history with an indication to the world capital reserves of energy. The energy released from the conversion of mass in chemical and nuclear processes is also discussed with comparative analysis between conventional fuel fired plant and nuclear power plant having the same energy output. The advantages and disadvantages arising from having a nuclear power programme are also discussed. 1 fig.

  2. Nuclear power news no 38

    International Nuclear Information System (INIS)

    1986-01-01

    The following matters are treated: What happened at the Chernobyl accident? - The Russian graphite reactor - a comparison with light water reactors. - The Soviet program for nuclear power. - Serious organizational unsatisfactory state of things at the nuclear power plants of Soviet. - Graphite reactors of the nuclear power program of the world. - The radioactive fallout in Sweden after Chernobyl. - The risks involved in radioactive radiation - an experts conception

  3. Manpower development for nuclear power

    International Nuclear Information System (INIS)

    1980-01-01

    This Guidebook provides policy-makers and managers of nuclear power programmes with information and guidance on the role, requirements, planning and implementation of manpower development programmes. It presents and discusses the manpower requirements associated with the activities of a nuclear power programme, the technical qualifications of this manpower and the manpower development corresponding to these requirements and qualifications. The Guidebook also discusses the purpose and conditions of national participation in the activities of a nuclear power programme

  4. Nuclear power - facts, trends, problems

    International Nuclear Information System (INIS)

    Spickermann, W.

    1981-01-01

    An attempt has been made to describe the state-of-the-art of nuclear power utilization, particularly for energy production. On the basis of information obtained from study tours through the USSR a rather comprehensive review of nuclear power plants and research establishments in the Soviet Union, of desalination reactors, ship propulsion reactors and fast breeder reactors is given, including nuclear facilities of other countries, e.g. France, USA, GDR. Heat generation, radiation-induced chemical processes and aspects associated with nuclear energy uses, such as risks, environmental protection or radioactive wastes, are also considered. Moreover, the author attempts to outline the social relevance of nuclear power

  5. Wuergassen nuclear power plant

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The decision of the Federal Court of Administration concerns an application for immediate decommissioning of a nuclear power plant (Wuergassen reactor): The repeal of the permit granted. The decision dismisses the appeal for non-admission lodged by the plaintiffs against the ruling of the Higher Court of Administration (OVG) of North-Rhine Westphalia of December 19th 1988 (File no. 21 AK 8/88). As to the matter in dispute, the Federal Court of Administration confirms the opinion of the Higher Court of Administration. As to the headnotes, reference can be made to that decision. Federal Court of Administration, decision of April 5th 1989 - 7 B 47.89. Lower instance: OVG NW, Az.: 21 AK 8/88. (orig./RST) [de

  6. Nuclear power plant

    International Nuclear Information System (INIS)

    Uruma, Hiroshi

    1998-01-01

    In the first embodiment of the present invention, elements less activated by neutrons are used as reactor core structural materials placed under high neutron irradiation. In the second embodiment of the present invention, materials less activated by neutrons when corrosive materials intrude to a reactor core are used as structural materials constituting portions where corrosion products are generated. In the third embodiment, chemical species comprising elements less activated by neutrons are used as chemical species to be added to reactor water with an aim of controlling water quality. A nuclear power plant causing less radioactivity can be provided by using structural materials comprising a group of specific elements hardly forming radioactivity by activation of neutrons or by controlling isotope ratios. (N.H.)

  7. Nuclear power plant

    International Nuclear Information System (INIS)

    Schabert, H.P.

    1976-01-01

    A nuclear power plant is described which includes a steam generator supplied via an input inlet with feedwater heated by reactor coolant to generate steam, the steam being conducted to a steam engine having a high pressure stage to which the steam is supplied, and which exhausts the steam through a reheater to a low pressure stage. The reheater is a heat exchanger requiring a supply of hot fluid. To avoid the extra load that would be placed on the steam generator by using a portion of its steam output as such heating fluid, a portion of the water in the steam generator is removed and passed through the reheater, this water having received at least adequate heating in the steam generator to make the reheater effective, but not at the time of its removal being in a boiling condition

  8. Nuclear power ecology: comparative analysis

    International Nuclear Information System (INIS)

    Trofimenko, A.P.; Lips'ka, A.Yi.; Pisanko, Zh.Yi.

    2005-01-01

    Ecological effects of different energy sources are compared. Main actions for further nuclear power development - safety increase and waste management, are noted. Reasons of restrained public position to nuclear power and role of social and political factors in it are analyzed. An attempt is undertaken to separate real difficulties of nuclear power from imaginary ones that appear in some mass media. International actions of environment protection are noted. Risk factors at different energy source using are compared. The results of analysis indicate that ecological influence and risk for nuclear power are of minimum

  9. Nuclear power reactor physics

    International Nuclear Information System (INIS)

    Barjon, Robert

    1975-01-01

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

  10. Nuclear power plants

    International Nuclear Information System (INIS)

    Kiyokawa, Teruyuki; Soman, Yoshindo.

    1985-01-01

    Purpose: To constitute a heat exchanger as one unit by integrating primary and secondary coolant circuits with secondary coolant circuit and steam circuit into a single primary circuit and steam circuit. Constitution: A nuclear power plant comprises a nuclear reactor vessel, primary coolant pipeways and a leakage detection system, in which a dual-pipe type heat exchanger is connected to the primary circuit pipeway. The heat conduction tube of the heat exchanger has a dual pipe structure, in which the inside of the inner tube is connected to the primary circuit pipeway, the outside of the outer tube is connected to steam circuit pipeway and a fluid channel is disposed between the inner and outer tubes and the fluid channel is connected to the inside of an expansion tank for intermediate heat medium. The leak detection system is disposed to the intermediate heat medium expansion tank. Sodium as the intermediate heat medium is introduced from the intermediate portion (between the inner and outer tubes) by way of inermediate heat medium pipeways to the intermediate heat medium expansion tank and, further, to the intermediate portion for recycling. (Kawakami, Y.)

  11. Nuclear power in Europe

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The increase in electronuclear production is the result of an investment policy which was started twenty years ago and actively pursued, notably by France where the programme was speeded up during the last decade. Over the whole of Europe taken in the widest sense, that is to say over the 10 million sq kms which stretch from the Atlantic to the Eastern borders of the Soviet Union with its population of nearly 664 million inhabitants (a sixth of the world population), the number of reactors continues to grow. In Eastern Europe a major investment programme is in progress and the Soviets have already reached the 1,500 MWe level. In the West, after a period of uncertainty marked by a systematic opposition to nuclear, public opinion is now much more favourable to this form of energy. The next referendum due to be held in Switzerland is likely to confirm this trend. There is still some uncertainty over the size of programmes as in Spain and Italy but it is true that the economic crisis had lead to a cut-back in energy demand. Consumption increases however turn up increasingly often. The following study examines 17 European countries which have already built nuclear power plants or are just about to do so [fr

  12. Analytical validation of operator actions in case of primary to secondary leakage for VVER-1000/V320

    Energy Technology Data Exchange (ETDEWEB)

    Andreeva, M., E-mail: m_andreeva@inrne.bas.bg; Groudev, P., E-mail: pavlinpg@inrne.bas.bg; Pavlova, M., E-mail: pavlova@inrne.bas.bg

    2015-12-15

    Highlights: • We validate operator actions in case of primary to secondary leakage. • We perform four scenarios related to SGTR accident for VVER-1000/V320. • The reference power plant for the analyses is Unit 6 at Kozloduy NPP. • The RELAP5/MOD 3.2 computer code is used in performing the analyses. • The analyses confirm the effectiveness of operator actions during PRISE. - Abstract: This paper presents the results of analytical validation of operator actions in case of “Steam Generator Tube Rupture” (SGTR) for VVER-1000/V320 units at Kozloduy Nuclear Power Plant (KNPP), done during the development of Symptom Based Emergency Operating Procedures (SB EOPs) for this plant. The purpose of the analyses is to demonstrate the ability to terminate primary to secondary leakage and to indicate an effective strategy for preventing secondary leakage to the environment and in this way to prevent radiological release to the environment. Following depressurization and cooldown of reactor coolant system (RCS) with isolation of the affected steam generator (SG), in these analyses are validated options for post-SGTR cooldown by: • back up filling the ruptured SG; • using letdown system in the affected SG and • by opening Fast Acting Isolation Valve (FAIV) and using Steam Dump Facility to the Condenser (BRU-K). The results of the thermal-hydraulic analyses have been used to assist KNPP specialists in analytical validation of EOPs. The RELAP5/MOD3.2 computer code has been used for the analyses in a VVER-1000 Nuclear Power Plant (NPP) model. A model of VVER-1000 based on Unit 6 of Kozloduy NPP has been developed for the thermal-hydraulics code RELAP5/MOD3.2 at the Institute for Nuclear Research and Nuclear Energy – Bulgarian Academy of Sciences (INRNE-BAS). This paper is possible through the participation of leading specialists from KNPP.

  13. Nuclear power perspective in China

    International Nuclear Information System (INIS)

    Liu Xinrong; Xu Changhua

    2003-01-01

    China started developing nuclear technology for power generation in the 1970s. A substantial step toward building nuclear power plants was taken as the beginning of 1980 s. The successful constructions and operations of Qinshan - 1 NPP, which was an indigenous PWR design with the capacity of 300 MWe, and Daya Bay NPP, which was an imported twin-unit PWR plant from France with the capacity of 900 MWe each, give impetus to further Chinese nuclear power development. Now there are 8 units with the total capacity of 6100 MWe in operation and 3 units with the total capacity of 2600 MWe under construction. For the sake of meeting the increasing demand for electricity for the sustainable economic development, changing the energy mix and mitigating the environment pollution impact caused by fossil fuel power plant, a near and middle term electrical power development program will be established soon. It is preliminarily predicted that the total power installation capacity will be 750-800GWe by the year 2020. The nuclear share will account for at least 4.0-4.5 percent of the total. This situation leaves the Chinese nuclear power industry with a good opportunity but also a great challenge. A practical nuclear power program and a consistent policy and strategy for future nuclear power development will be carefully prepared and implemented so as to maintain the nuclear power industry to be healthfully developed. (author)

  14. Nuclear power in eastern and central Europe. Background paper

    International Nuclear Information System (INIS)

    Myers, L.C.

    1993-11-01

    The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab

  15. Nuclear power in eastern and central Europe. Background paper

    Energy Technology Data Exchange (ETDEWEB)

    Myers, L C [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

    1993-11-01

    The breakup of the former Soviet Union and other political changes in eastern and central Europe have opened up the area to closer scrutiny than was previously possible. Because of the accident at Chernobyl, nuclear power is one of the subjects that western nations have had a great deal of interest in exploring. The former Soviet Union designed and/or helped build more than 60 civilian reactors in the region. Most of these reactors follow one of two distinctly different designs: the VVER, or pressurized water reactor series; and the RBMK, which is a graphite-moderated, multi-channel reactor (the so-called Chernobyl type). In addition, there are two fast-breeder reactors and four graphite-moderated boiling water reactors for combined heat and power in operation in Russia. These last two designs are not widely distributed and so are not discussed in detail in this report. As noted above, the safety of Soviet-designed reactors has been of great concern around the world since the catastrophic events at Chernobyl in 1986. This paper will briefly describe the technology involved. It will also examine the main safety concerns, both technical and organizational, associated with each reactor type. In addition, the paper will review the nuclear power programs in the new countries emerging from the former Soviet Union and its satellites and discuss the international efforts underway to address the most pressing problems. (author). 1 tab.

  16. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    1997-01-01

    The guide applies to the nuclear power plant operator licensing procedure referred to the section 128 of the Finnish Nuclear Energy Degree. The licensing procedure applies to shift supervisors and those operators of the shift teams of nuclear power plant units who manipulate the controls of nuclear power plants systems in the main control room. The qualification requirements presented in the guide also apply to nuclear safety engineers who work in the main control room and provide support to the shift supervisors, operation engineers who are the immediate superiors of shift supervisors, heads of the operational planning units and simulator instructors. The operator licensing procedure for other nuclear facilities are decided case by case. The requirements for the basic education, work experience and the initial, refresher and complementary training of nuclear power plant operating personnel are presented in the YVL guide 1.7. (2 refs.)

  17. Nuclear Power Plant Module, NPP-1: Nuclear Power Cost Analysis.

    Science.gov (United States)

    Whitelaw, Robert L.

    The purpose of the Nuclear Power Plant Modules, NPP-1, is to determine the total cost of electricity from a nuclear power plant in terms of all the components contributing to cost. The plan of analysis is in five parts: (1) general formulation of the cost equation; (2) capital cost and fixed charges thereon; (3) operational cost for labor,…

  18. Nuclear power falling to pieces

    International Nuclear Information System (INIS)

    Moberg, Aa.

    1985-01-01

    The international development during the 80s is reviewed. It is stated that the construction of plants has come to a standstill. The forecasting of nuclear power as a simple and cheap source of energy has been erroneous because of cracks and leakage, unsolved waste problems and incidents. Nuclear power companies go into liquidation and reactors are for sale. Sweden has become the country with most nuclear power per capita mainly due to its controlled decommissioning. The civilian nuclear power makes the proliferation of nuclear weapons possible. With 324 reactors all over the world, a conventional war may cause disasters like Hiroshima. It is stated that the nuclear power is a dangerous and expensive source of energy and impossible to manage. (G.B.)

  19. Nuclear power - the Hydra's head

    Energy Technology Data Exchange (ETDEWEB)

    Bunyard, P

    1986-01-01

    Following the accident at Chernobyl, the nuclear policies of many governments have been reconsidered and restated. Those in favour of nuclear power are those with highly centralised state bureaucracies, such as France and the USSR, where public opinion is disregarded. In more democratic countries, where referenda are held, such as Austria and Sweden, the people have chosen to do away with nuclear power. Indeed, the author states that nuclear power represents the State against the people, the State against democracy. Reference is made to the IAEA Reactor Safety Conference held in September, 1986, in Vienna, and the declaration sent to it by AntiAtom International. This called for the United Nations to promote the phasing out of nuclear power facilities throughout the world. It also called on the IAEA to support the phasing out of nuclear power and promote benign energy forms instead.

  20. Nuclear power - the Hydra's head

    International Nuclear Information System (INIS)

    Bunyard, Peter.

    1986-01-01

    Following the accident at Chernobyl, the nuclear policies of many governments have been reconsidered and restated. Those in favour of nuclear power are those with highly centralised state bureaucracies, such as France and the USSR, where public opinion is disregarded. In more democratic countries, where referenda are held, such as Austria and Sweden, the people have chosen to do away with nuclear power. Indeed, the author states that nuclear power represents the State against the people, the State against democracy. Reference is made to the IAEA Reactor Safety Conference held in September, 1986, in Vienna, and the declaration sent to it by AntiAtom International. This called for the United Nations to promote the phasing out of nuclear power facilities throughout the world. It also called on the IAEA to support the phasing out of nuclear power and promote benign energy forms instead. (UK)

  1. Nuclear power and the UK

    International Nuclear Information System (INIS)

    Murphy, St.

    2009-01-01

    This series of slides describes the policy of the UK government concerning nuclear power. In January 2008 the UK Government published the White Paper on the Future of Nuclear Power. The White Paper concluded that new nuclear power stations should have a role to play in this country's future energy mix. The role of the Government is neither to build nuclear power plants nor to finance them. The White Paper set out the facilitative actions the Government planned to take to reduce regulatory and planning risks associated with investing in new nuclear power stations. The White Paper followed a lengthy period of consultation where the UK Government sought a wide variety of views from stakeholders and the public across the country on the future of nuclear power. In total energy companies will need to invest in around 30-35 GW of new electricity generating capacity over the next two decades. This is equivalent to about one-third of our existing capacity. The first plants are expected to enter into service by 2018 or sooner. The Office for Nuclear Development (OND) has been created to facilitate new nuclear investment in the UK while the Nuclear Development Forum (NDF) has been established to lock in momentum to secure the long-term future of nuclear power generation in the UK. (A.C.)

  2. Nuclear power in human medicine

    International Nuclear Information System (INIS)

    Kuczera, Bernhard

    2012-01-01

    The public widely associate nuclear power with the megawatt dimensions of nuclear power plants in which nuclear power is released and used for electricity production. While this use of nuclear power for electricity generation is rejected by part of the population adopting the polemic attitude of ''opting out of nuclear,'' the application of nuclear power in medicine is generally accepted. The appreciative, positive term used in this case is nuclear medicine. Both areas, nuclear medicine and environmentally friendly nuclear electricity production, can be traced back to one common origin, i.e. the ''Atoms for Peace'' speech by U.S. President Eisenhower to the U.N. Plenary Assembly on December 8, 1953. The methods of examination and treatment in nuclear medicine are illustrated in a few examples from the perspective of a nuclear engineer. Nuclear medicine is a medical discipline dealing with the use of radionuclides in humans for medical purposes. This is based on 2 principles, namely that the human organism is unable to distinguish among different isotopes in metabolic processes, and the radioactive substances are employed in amounts so small that metabolic processes will not be influenced. As in classical medicine, the application of these principles serves two complementary purposes: diagnosis and therapy. (orig.)

  3. Nuclear power in the USSR

    Energy Technology Data Exchange (ETDEWEB)

    Vasiliev, V A

    1981-04-01

    This article examines the role of nuclear power in the USSR. Since the beginning of development of power reactors in the Soviet Union in the 1950s, their contribution had grown to 6% of all electric power by 1980. Reactor development has proceeded rapidly, with a number of reactor designs in use. Fast-breeder reactors and designs for specialized applications are under development. It is anticipated that the contribution of nuclear power will continue to grow. The status of nuclear power stations at 20 locations is summarized in a table.

  4. Nuclear power in the USSR

    International Nuclear Information System (INIS)

    Vasiliev, V.A.

    1982-01-01

    This Article examines the role of nuclear power in the USSR. Since the beginning of development of power reactors in the Soviet Union in the 1950s, their contribution had grown to 6% of all electric power by 1980. Reactor development has proceeded rapidly, with a number of reactor designs in use. Fast breeder reactors and designs for specialized applications are under development. It is anticipated that the contribution of nuclear power will continue to grow. (author)

  5. Power peaking nuclear reliability factors

    International Nuclear Information System (INIS)

    Hassan, H.A.; Pegram, J.W.; Mays, C.W.; Romano, J.J.; Woods, J.J.; Warren, H.D.

    1977-11-01

    The Calculational Nuclear Reliability Factor (CNRF) assigned to the limiting power density calculated in reactor design has been determined. The CNRF is presented as a function of the relative power density of the fuel assembly and its radial local. In addition, the Measurement Nuclear Reliability Factor (MNRF) for the measured peak hot pellet power in the core has been evaluated. This MNRF is also presented as a function of the relative power density and radial local within the fuel assembly

  6. Nuclear power in the USSR

    Energy Technology Data Exchange (ETDEWEB)

    Vasiliev, V A [AN SSSR, Moscow. Akusticheskij Inst.

    1982-04-01

    This Article examines the role of nuclear power in the USSR. Since the beginning of development of power reactors in the Soviet Union in the 1950s, their contribution had grown to 6% of all electric power by 1980. Reactor development has proceeded rapidly, with a number of reactor designs in use. Fast breeder reactors and designs for specialized applications are under development. It is anticipated that the contribution of nuclear power will continue to grow.

  7. Nuclear power in the USSR

    Energy Technology Data Exchange (ETDEWEB)

    Vasiliev, V A [State Committee for Science and Technology, Moscow, USSR

    1981-04-01

    This article examines the role of nuclear power in the USSR. Since the beginning of development of power reactors in the Soviet Union in the 1950's, their contribution had grown to six per cent of all electric power by 1980. Reactor development has proceeded rapidly, with a number of reactor designs in use. Fast breeder reactors and designs for specialized applications are under development. It is anticipated that the contribution of nuclear power will continue to grow.

  8. Nuclear power and other thermal power

    International Nuclear Information System (INIS)

    Bakke, J.

    1978-01-01

    Some philosophical aspects of mortality statistics are first briefly mentioued, then the environmental problems of, first, nuclear power plants, then fossil fuelled power plants are summarised. The effects of releases of carbon dioxide, sulphur dioxide and nitrogen oxides are briefly discussed. The possible health effects of radiation from nuclear power plants and those of gaseous and particulate effluents from fossil fuel plants are also discussed. It is pointed out that in choosing between alternative evils the worst course is to make no choice at all, that is, failure to install thermal power plants will lead to isolated domestic burning of fossil fuels which is clearly the worst situation regarding pollution. (JIW)

  9. Power generation costs. Coal - nuclear power

    International Nuclear Information System (INIS)

    1979-01-01

    This supplement volume contains 17 separate chapters investigating the parameters which determine power generation costs on the basis of coal and nuclear power and a comparison of these. A detailed calculation model is given. The complex nature of this type of cost comparison is shown by a review of selected parameter constellation for coal-fired and nuclear power plants. The most favourable method of power generation can only be determined if all parameters are viewed together. One quite important parameter is the load factor, or rather the hours of operation. (UA) 891 UA/UA 892 AMO [de

  10. 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.

  11. Images of nuclear power plants

    International Nuclear Information System (INIS)

    Hashiguchi, Katsuhisa; Misumi, Jyuji; Yamada, Akira; Sakurai, Yukihiro; Seki, Fumiyasu; Shinohara, Hirofumi; Misumi, Emiko; Kinjou, Akira; Kubo, Tomonori.

    1995-01-01

    This study was conducted to check and see, using Hayashi's quantification method III, whether or not the respondents differed in their images of a nuclear power plant, depending on their demographic variables particularly occupations. In our simple tabulation, we compared subject groups of nuclear power plant employees with general citizens, nurses and students in terms of their images of a nuclear power plant. The results were that while the nuclear power plant employees were high in their evaluations of facts about a nuclear power plant and in their positive images of a nuclear power plant, general citizens, nurses and students were overwhelmingly high in their negative images of a nuclear power plant. In our analysis on category score by means of the quantification method III, the first correlation axis was the dimension of 'safety'-'danger' and the second correlation axis was the dimension of 'subjectivity'-'objectivity', and that the first quadrant was the area of 'safety-subjectivity', the second quadrant was the area of 'danger-subjectivity', the third quadrant as the area of 'danger-objectivity', and the forth quadrant was the area of 'safety-objectivity'. In our analysis of sample score, 16 occupation groups was compared. As a result, it was found that the 16 occupation groups' images of a nuclear power plant were, in the order of favorableness, (1) section chiefs in charge, maintenance subsection chiefs, maintenance foremen, (2) field leaders from subcontractors, (3) maintenance section members, operation section members, (4) employees of those subcontractors, (5) general citizens, nurses and students. On the 'safety-danger' dimension, nuclear power plant workers on the one hand and general citizens, nurses and students on the other were clearly divided in terms of their images of a nuclear power plant. Nuclear power plant workers were concentrated in the area of 'safety' and general citizens, nurses and students in the area of 'danger'. (J.P.N.)

  12. East/West cooperation on the safety of USSR-designed nuclear power stations

    International Nuclear Information System (INIS)

    Spencer, P.H.

    1991-01-01

    In the aftermath of the accident at the Chernobyl nuclear power station in the Soviet Union, nuclear power plant operators throughout the world came together in May 1989 to form the World Association of Nuclear Operators (WANO). When it became clear that the operators of plants of an early design supplied by the USSR needed assistance in the upgrading of the safety of these units, WANO was uniquely placed to assist and facilitate in this. In July 1990, WANO took the decision to form a special project to assist the operators of the VVER 440/230 plants in their efforts to increase the safety standards for these units. The work performed by this special project team is described

  13. Core designs of modern VVER projects

    International Nuclear Information System (INIS)

    Vasilchenko, I.; Kushmanov, S.; Vjalitsyn, V.; Vasilchenko, R.

    2015-01-01

    The presented operational experience of TVS - 2M (pilot-commercial operation started in 2006 at Balakovo NPP -1) enables to use it as reference for new projects because of similarity in designs and operational conditions. In the paper main parameters of fuel cycles, stability to impact of damaging factors, pilot operation of MG, new alloys, ADF and NTMC, upgrade of FA - 2M for the further power uprating, profiling of Gd-fuel rods for 18-month Fuel Cycle (FC) and perfection of absorber element design are the discussed issues. At the end author concluded that: 1) Core designs of new projects AES-2006 and VVER-TOI are based on extensive successful operational experience of the close prototype of TVS - 2M. 2) All improvements both of technical and economic parameters of fuel are subjected to representative examination by pilot operation at the power units with VVER-1000 being close prototypes of new designs

  14. Potential consequences in Norway after a hypothetical accident at Leningrad nuclear power plant. Potential release, fallout and predicted impacts on the environment

    International Nuclear Information System (INIS)

    Nalbandyan, A.; Ytre-Eide, M.A.; Thoerring, H.; Liland, A.; Bartnicki, J.; Balonov, M.

    2012-06-01

    The report describes different hypothetical accident scenarios at the Leningrad nuclear power plant for both RBMK and VVER-1200 reactors. The estimated release is combined with different meteorological scenarios to predict possible fallout of radioactive substances in Norway. For a hypothetical catastrophic accident at an RBMK reactor combined with a meteorological worst case scenario, the consequences in Norway could be considerable. Foodstuffs in many regions would be contaminated above the food intervention levels for radioactive cesium in Norway. (Author)

  15. Potential consequences in Norway after a hypothetical accident at Leningrad nuclear power plant. Potential release, fallout and predicted impacts on the environment

    Energy Technology Data Exchange (ETDEWEB)

    Nalbandyan, A.; Ytre-Eide, M.A.; Thoerring, H.; Liland, A.; Bartnicki, J.; Balonov, M.

    2012-06-15

    The report describes different hypothetical accident scenarios at the Leningrad nuclear power plant for both RBMK and VVER-1200 reactors. The estimated release is combined with different meteorological scenarios to predict possible fallout of radioactive substances in Norway. For a hypothetical catastrophic accident at an RBMK reactor combined with a meteorological worst case scenario, the consequences in Norway could be considerable. Foodstuffs in many regions would be contaminated above the food intervention levels for radioactive cesium in Norway. (Author)

  16. US nuclear power industry overview

    International Nuclear Information System (INIS)

    Wood, C.J.

    1995-01-01

    The electric utilities in the United States are facing a number of challenges as deregulation proceeds. Cost control is one of these challenges that impacts directly the operators of nuclear power plants. This presentation reviews recent data on the performance of nuclear power plants and discusses technical developments to reduce operating costs, with particular reference to low-level radioactive waste issues

  17. Islands for nuclear power stations

    International Nuclear Information System (INIS)

    Usher, E.F.F.W.; Fraser, A.P.

    1981-01-01

    The safety principles, design criteria and types of artificial island for an offshore nuclear power station are discussed with particular reference to siting adjacent to an industrial island. The paper concludes that the engineering problems are soluble and that offshore nuclear power stations will eventually be built but that much fundamental work is still required. (author)

  18. Nuclear power - the moral question

    International Nuclear Information System (INIS)

    Searby, P.

    1978-01-01

    Nuclear power has raised moral and ethical as well as technological issues and the British Council of churches, recognising this, has participated in the UK nuclear power debate. In this short article, Mr Philip Searby, Secretary of the UKAEA, considers some of the views adopted by the Council. (author)

  19. Nuclear power and the environment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1970-07-01

    One of the most important points of agreement arising from international studies of nuclear energy is that no significant change to the environment has occurred as a result of operating power plants. This emerged from the Agency's symposium at United Nations headquarters during August on Environmental Aspects of Nuclear Power. (author)

  20. Competitive economics of nuclear power

    International Nuclear Information System (INIS)

    Hellman, R.

    1981-01-01

    Some 12 components of a valid study of the competitive economics of a newly ordered nuclear power plant are identified and explicated. These are then used to adjust the original cost projections of four authoritative studies of nuclear and coal power economics

  1. Social aspects of nuclear power

    International Nuclear Information System (INIS)

    Koryakin, Yu.I.

    1990-01-01

    Social aspects of nuclear power crisis in the USSR are considered. It is shown that the system of economic and social stimulation and different compensations widely used abroad when locating nuclear power plants, is the effective factor, providing loyal attitude to them

  2. Nuclear power development in Japan

    International Nuclear Information System (INIS)

    Sugawara, A.

    1994-01-01

    Energy situation in Japan and Japan's strategy for stable supply of energy are discussed. Benefits of nuclear power in comparison with other energy sources is considered. History of nuclear power development in Japan, modern status and future trends are described. 6 figs

  3. 25 years of nuclear power

    International Nuclear Information System (INIS)

    Pocock, R.F.

    1984-01-01

    The paper lists some of the notable events of the British nuclear power industry during the past 25 years. The list includes achievements in nuclear power station technology, administrative reorganisation and public concern about the industry's impact on the environment. (U.K.)

  4. Nuclear power in the US

    International Nuclear Information System (INIS)

    Judson, Tim

    2018-01-01

    The Trump government promotes the further operation of aging nuclear power plants in the US by governmental support although several operators close their nuclear power plants due to economic reasons. The Trump government is also repowering the Yucca-Mountain-Project for radioactive waste disposal that was stopped by the Obama government based on geological problems in the region.

  5. International nuclear power status 2000

    International Nuclear Information System (INIS)

    Lauritzen, B.; Majborn, B.; Nonboel, E.; Oelgaard, P.L.

    2001-03-01

    This report is the seventh in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 2000, the report contains: 1. General trends in the development of nuclear power. 2. Deposition of low-level radioactive waste. 3. Statistical information on nuclear power production (in 1999). 4. An overview of safety-relevant incidents in 2000. 5. The development in Sweden. 6. The development in Eastern Europe. 7. The development in the rest of the world. 8. Trends in the development of reactor types. 9. Trends in the development of the nuclear fuel cycle. (au)

  6. The collapse of nuclear power

    International Nuclear Information System (INIS)

    Jeffery, J.W.

    1991-01-01

    The decision of the UK government of 9 November 1989, withdrawing all nuclear stations from privatization and cancelling the three PWRs which were to have followed on from Sizewell B, was a shattering blow to the nuclear industry. The reversal (at least temporarily) of decades of government support for nuclear power, and the figures which were becoming available of its relatively high-cost (confirmed by the levy on electricity sales to subsidize nuclear and other non-fossil generation), caused the House of Commons Energy Select Committee to conduct the inquiry culminating in its Report The Cost of Nuclear power. (author)

  7. Crunch time for nuclear power

    International Nuclear Information System (INIS)

    Edwards, Rob.

    1994-01-01

    The Federal Republic of Germany, one of the most advanced nations, technically has a thriving nuclear power industry. However there is stiff opposition to nuclear power from political parties and environmental groups. General elections due to be held in mid October hold the future of the nuclear industry in the balance. If the present opposition party comes to power, it is committed to a policy of phasing out nuclear power completely. At the centre of the political uproar is the Gorleben ''interim store'' which is intended to house Germany's spent fuel for at least the next forty years. The nuclear industry must resolve the issue of nuclear waste disposal to the voters' satisfaction if it is to have a viable future. (UK)

  8. Nuclear power and the environment

    International Nuclear Information System (INIS)

    Blix, H.

    1989-11-01

    The IAEA Director General pointed out that continued and expanded use of nuclear power must be one among several measures to restrain the use of fossil fuels and thereby limit the emissions of greenhouse gases. With regards to future trends in world electricity demands, the Director General emphasized the existing gap between the frequent claims as to what conservation can achieve and actual energy plans. The objections to nuclear power which are related to safety, waste disposal and the risk of proliferation of nuclear weapons are also discussed. His conclusion is that nuclear power can help significantly to meet growing needs of electricity without contributing to global warming, acid rains or dying forests, responsible management and disposal of nuclear wastes is entirely feasible, and the safety of nuclear power must be continuously strengthened through technological improvement and methods of operation

  9. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    Morrison, R.W.

    1980-01-01

    A few of the essential issues which arise when we consider nuclear power and development together in the context of energy policy are discussed. Ethical concerns must ultimately be expressed through policies and their impact on people. There are ethical issues associated with nuclear power in the developing countries which deserve our attention. Four aspects of the question of nuclear power in developing countries are considered: their energy situation; the characteristics of nuclear power which are relevant to them; whether developing countries will undertake nuclear power programmes; and finally the ethical implications of such programmes. It is concluded that what happens in developing countries will depend more on the ethical nature of major political decisions and actions than on the particular technology they use to generate their electricity. (LL)

  10. Nuclear power supply (Japan Nuclear Safety Institute)

    International Nuclear Information System (INIS)

    Kameyama, Masashi

    2013-01-01

    After experienced nuclear disaster occurred on March 11, 2011, role of nuclear power in future energy share in Japan became uncertain because most public seemed to prefer nuclear power phase out to energy security or costs. Whether nuclear power plants were safe shutdown or operational, technologies were requisite for maintaining their equipment by refurbishment, partly replacement or pressure proof function recovery works, all of which were basically performed by welding. Nuclear power plants consisted of tanks, piping and pumps, and considered as giant welded structures welding was mostly used. Reactor pressure vessel subject to high temperature and high pressure was around 200mm thick and made of low-alloy steels (A533B), stainless steels (308, 316) and nickel base alloys (Alloy 600, 690). Kinds of welding at site were mostly shielded-metal arc welding and TIG welding, and sometimes laser welding. Radiation effects on welding of materials were limited although radiation protection was needed for welding works under radiation environment. New welding technologies had been applied after their technical validation by experiments applicable to required regulation standards. Latest developed welding technologies were seal welding to prevent SCC propagation and temper-bead welding for cladding after removal of cracks. Detailed procedures of repair welding of Alloy 600 at the reactor outlet pipe at Oi Nuclear Power Plants unit 3 due to PWSCC were described as an example of crack removal and water jet peening, and then overlay by temper-bead welding using Alloy 600 and clad welding using Alloy 690. (T. Tanaka)

  11. Nuclear safeguards control in nuclear power stations

    International Nuclear Information System (INIS)

    Boedege, R.; Braatz, U.; Heger, H.

    1976-01-01

    The execution of the Non-Proliferation Treaty (NPT) has initiated a third phase in the efforts taken to ensure peace by limiting the number of atomic powers. In this phase it is important, above all, to turn into workable systems the conditions imposed upon technology by the different provisions of the Verification Agreement of the NPT. This is achieved mainly by elaborating annexes to the Agreement specifically geared to certain model plants, typical representatives selected for LWR power stations being the plants at Garigliano, Italy (BWR), and Stade, Federal Republic of Germany (PWR). The surveillance measures taken to prevent any diversion of special nuclear material for purposes of nuclear weapons manufacture must be effective in achieving their specific objective and must not impede the circumspect management of operations of the plants concerned. A VDEW working party has studied the technical details of the planned surveillance measures in nuclear power stations in the Federal Republic of Germany and now presents a concept of material balancing by units which meets the conditions imposed by the inspection authority and could also be accepted by the operators of nuclear power stations. The concept provides for uninterrupted control of the material balance areas of the nuclear power stations concerned, allows continuous control of the whole nuclear fuel cycle, is based exclusively on existing methods and facilities, and can be implemented at low cost. (orig.) [de

  12. Separation of nuclear power from nuclear proliferation

    International Nuclear Information System (INIS)

    Starr, C.

    1978-01-01

    A successful development of the proposed combination of the Fast Breeder Reactor and the CIVEX fuel reprocessing facility would provide an economical nuclear power source for many centuries which inherently separates nuclear power from the issue of weapons material diversion and proliferation. Further, by so doing, it permits great flexibility in international and national planning for nuclear power, as the issues of fuel dependence and terrorist and subnational diversions disappear. In addition, the expansion of the FBR/CIVEX system would eat into the LWR spent fuel stockpile, diminishing steadily this relatively accessible plutonium source. And finally, a rapid development of the FBR/CIVEX for the above reasons would substantially reduce the worldwide concern as to the adequacy of uranium ore supply. From a historical view, it would restore fast reactor development to the path originally foreseen in the programs of worldwide nuclear energy authorities, including the Atomic Energy Commission during its first two decades of existence

  13. Strategy for utilizing nuclear power

    International Nuclear Information System (INIS)

    Martens, E.J.

    1977-01-01

    One of the national goals is to achieve independence in the area of energy supplies in the next few years. It is believed that attaining this goal will require extensive utilization of nuclear power in conventional fission reactors. It is proposed that the best way to develop the nuclear resource is through government ownership of the reactors. It is argued that this will minimize the risks associated with the nuclear-power option and clear the way for its exploitation

  14. Canadian attitudes to nuclear power

    International Nuclear Information System (INIS)

    Davies, J.E.O.

    1977-01-01

    In the past ten years, public interest in nuclear power and its relationship to the environment has grown. Although most Canadians have accepted nuclear power as a means of generating electricity, there is significant opposition to its use. This opposition has effectively forced the Canadian nuclear industry to modify its behaviour to the public in the face of growing concern over the safety of nuclear power and related matters. The paper reviews Canadian experience concerning public acceptance of nuclear power, with special reference to the public information activities of the Canadian nuclear industry. Experience has shown the need for scientific social data that will permit the nuclear industry to involve the public in a rational examination of its concern about nuclear power. The Canadian Nuclear Association sponsored such studies in 1976 and the findings are discussed. They consisted of a national assessment of public attitudes, two regional studies and a study of Canadian policy-makers' views on nuclear energy. The social data obtained were of a base-line nature describing Canadian perceptions of and attitudes to nuclear power at that time. This research established that Canadian levels of knowledge about nuclear power are very low and that there are marked regional differences. Only 56% of the population have the minimum knowledge required to indicate that they know that nuclear power can be used to generate electricity. Nevertheless, 21% of informed Canadians oppose nuclear power primarily on the grounds that it is not safe. Radiation and waste management are seen to be major disadvantages. In perspective, Canadians are more concerned with inflation than with the energy supply. About half of all Canadians see the question of energy supplies as a future problem (within five years), not a present one. A more important aspect of energy is seen by the majority of Canadians to be some form of energy independence. The use of data from these studies is no easy

  15. Nuclear power plant V-1

    International Nuclear Information System (INIS)

    1998-01-01

    The nuclear power plant Bohunice V -1 is briefly described. This NPP consists from two reactor units. Their main time characteristics are (Reactor Unit 1, Reactor Unit 2): beginning of construction - 24 April 1972; first controlled reactor power - 27 November 1978, 15 March 1980; connection to the grid - 17 December 1978, 26 March 1980; commercial operation - 1 April 1980, 7 January 1981. This leaflet contains: NPP V-1 construction; Major technological equipment (Primary circuit: Nuclear reactor [WWER 440 V230 type reactor];Steam generator; Reactor Coolant Pumps; Primary Circuit Auxiliary Systems. Secondary circuit: Turbine generators, Nuclear power plant electrical equipment; power plant control) and technical data

  16. French lessons in nuclear power

    International Nuclear Information System (INIS)

    Valenti, M.

    1991-01-01

    In stark contrast to the American atomic power experience is that of the French. Even the disaster at Chernobyl in 1986, which chilled nuclear programs throughout Western Europe, did not slow the pace of the nuclear program of the state-owned Electricite de France (EDF), based in Paris. Another five units are under construction and are scheduled to be connected to the French national power grid before the end of 1993. In 1989, the EDF's 58 nuclear reactors supplied 73 percent of French electrical needs, a higher percentage than any other country. In the United States, for example, only about 18 percent of electrical power is derived from the atom. Underpinning the success of nuclear energy in France is its use of standardized plant design and technology. This has been an imperative for the French nuclear power industry since 1974, when an intensive program of nuclear power plant construction began. It was then, in the aftermath of the first oil embargo, that the French government decided to reduce its dependence on imported oil by substituting atomic power sources for hydrocarbons. Other pillars supporting French nuclear success include retrofitting older plants with technological or design advances, intensive training of personnel, using robotic and computer aids to reduce downtime, controlling the entire nuclear fuel cycle, and maintaining a comprehensive public information effort about the nuclear program

  17. Climate change and nuclear power

    International Nuclear Information System (INIS)

    Schneider, M.

    2000-04-01

    The nuclear industry has increased its efforts to have nuclear power plants integrated into the post- Kyoto negotiating process of the UN Framework Convention on Climate Change. The Nuclear Energy Institute (NEI) states: ''For many reasons, current and future nuclear energy projects are a superior method of generating emission credits that must be considered as the US expands the use of market- based mechanisms designed around emission credit creation and trading to achieve environmental goals ''. The NEI considers that nuclear energy should be allowed to enter all stages of the Kyoto ''flexibility Mechanisms'': emissions trading, joint implementation and the Clean Development Mechanism. The industry sees the operation of nuclear reactors as emission ''avoidance actions'' and believes that increasing the generation of nuclear power above the 1990 baseline year either through extension and renewal of operating licenses or new nuclear plant should be accepted under the flexibility mechanisms in the same way as wind, solar and hydro power. For the time being, there is no clear definition of the framework conditions for operating the flexibility mechanisms. However, eligible mechanisms must contribute to the ultimate objective of the Climate Convention of preventing ''dangerous anthropogenic interference with the climate system''. The information presented in the following sections of this report underlines that nuclear power is not a sustainable source of energy, for many reasons. In conclusion, an efficient greenhouse gas abatement strategy will be based on energy efficiency and not on the use of nuclear power. (author)

  18. Nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Urata, Hidehiro; Oya, Takashi

    1996-11-05

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  19. Nuclear power plant

    International Nuclear Information System (INIS)

    Urata, Hidehiro; Oya, Takashi.

    1996-01-01

    The present invention provides a highly safe light water-cooled type nuclear power plant capable of reducing radiation dose by suppressing deposition of activated corrosion products by a simple constitution. Namely, equipments and pipelines for fluid such as pumps at least in one of fluid systems such as a condensate cleanup system are constituted by a material containing metal species such as Zn having an effect of suppressing deposition of radioactivity. Alternatively, the surface of these equipments and pipelines for fluids on which water passes is formed by a coating layer comprising a material containing a metal having a radiation deposition suppressing effect. As a result, radioactivity deposited on the equipments and pipelines for fluids is reduced. In addition, since the method described above may be applied only at least to a portion of the members constituting at least one of the systems for fluids, it is economical. Accordingly, radiation dose upon inspection of equipments and pipelines for fluids can be reduced simply and reliably. (I.S.)

  20. Underground nuclear power plant

    International Nuclear Information System (INIS)

    Takahashi, Hideo.

    1997-01-01

    In an underground-type nuclear power plant, groups of containing cavities comprising a plurality of containing cavities connected in series laterally by way of partition walls are disposed in parallel underground. Controlled communication tunnels for communicating the containing cavities belonging to a control region to each other, and non-controlled communication tunnels for communicating containing cavities belonging to a non-controlled area to each other are disposed underground. A controlled corridor tunnel and a non-controlled corridor tunnel extended so as to surround the containing cavity groups are disposed underground, and the containing cavities belonging to the controlled area are connected to the controlled corridor tunnel respectively, and the containing cavities belonging to the non-controlled area are connected to the non-controlled corridor tunnel respectively. The excavating amount of earth and sand upon construction can be reduced by disposing the containing cavity groups comprising a plurality of containing cavities connected in series laterally. The time and the cost for the construction can be reduced, and various excellent effects can be provided. (N.H.)

  1. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    1976-03-01

    During the period under review, the Garigliano power station produced 1,028,77 million kWh with a utilization factor of 73,41% and an availability factor of 85,64%. The disparity between the utilization and availability factors was mainly due to a shutdown of about one and half months owing to lack of staff at the plant. The reasons for nonavailability (14.36%) break down as follows: nuclear reasons 11,49%; conventional reasons 2,81%; other reasons 0,06%. During the period under review, no fuel replacements took place. The plant functioned throughout with a single reactor reticulation pump and resulting maximum available capacity of 150 MWe gross. After the month of August, the plant was operated at levels slightly below the maximum available capacity in order to lengthen the fuel cycle. The total number of outages during the period under review was 11. Since the plant was brought into commercial operation, it has produced 9.226 million kWh

  2. Validation of coupled neutronic / thermal-hydraulic codes for VVER reactors. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Mittag, S.; Grundmann, U.; Kliem, S.; Kozmenkov, Y.; Rindelhardt, U.; Rohde, U.; Weiss, F.-P.; Langenbuch, S.; Krzykacz-Hausmann, B.; Schmidt, K.-D.; Vanttola, T.; Haemaelaeinen, A.; Kaloinen, E.; Kereszturi, A.; Hegyi, G.; Panka, I.; Hadek, J.; Strmensky, C.; Darilek, P.; Petkov, P.; Stefanova, S.; Kuchin, A.; Khalimonchuk, V.; Hlbocky, P.; Sico, D.; Danilin, S.; Ionov, V.; Nikonov, S.; Powney, D.

    2004-08-01

    In recent years, the simulation methods for the safety analysis of nuclear power plants have been continuously improved to perform realistic calculations. Therefore in VALCO work package 2 (WP 2), the usual application of coupled neutron-kinetic / thermal-hydraulic codes to VVER has been supplemented by systematic uncertainty and sensitivity analyses. A comprehensive uncertainty analysis has been carried out. The GRS uncertainty and sensitivity method based on the statistical code package SUSA was applied to the two transients studied earlier in SRR-1/95: A load drop of one turbo-generator in Loviisa-1 (VVER-440), and a switch-off of one feed water pump in Balakovo-4 (VVER-1000). The main steps of these analyses and the results obtained by applying different coupled code systems (SMABRE - HEXTRAN, ATHLET - DYN3D, ATHLET - KIKO3D, ATHLET - BIPR-8) are described in this report. The application of this method is only based on variations of input parameter values. No internal code adjustments are needed. An essential result of the analysis using the GRS SUSA methodology is the identification of the input parameters, such as the secondary-circuit pressure, the control-assembly position (as a function of time), and the control-assembly efficiency, that most sensitively affect safety-relevant output parameters, like reactor power, coolant heat-up, and primary pressure. Uncertainty bands for these output parameters have been derived. The variation of potentially uncertain input parameter values as a consequence of uncertain knowledge can activate system actions causing quite different transient evolutions. This gives indications about possible plant conditions that might be reached from the initiating event assuming only small disturbances. In this way, the uncertainty and sensitivity analysis reveals the spectrum of possible transient evolutions. Deviations of SRR-1/95 coupled code calculations from measurements also led to the objective to separate neutron kinetics from

  3. Global outlook for nuclear power

    International Nuclear Information System (INIS)

    Southworth, F.H.

    2010-01-01

    'Full text:' The global nuclear power forecast, the North American outlook and the effect of nuclear power growth on greenhouse gas emissions in North America will be discussed. The construction of Generation III reactors will replace aging power plants and, further, add capacity that is environmentally sustainable. The outlook for Generation IV reactors also may significantly improve the environmental balance after 2030, both in electrical markets, waste reduction, and in non-traditional markets such as process heat. (author)

  4. Hendry collides with nuclear power

    International Nuclear Information System (INIS)

    Wade, S.

    1979-01-01

    It is argued that nuclear power is not the answer to future energy needs in the UK. Problems associated with nuclear power programmes are summarized (cost; lead time; ecological; safety; reliability; waste disposal). It is suggested, instead, that conservation is the first key to economic stability over the next decade, and steps are proposed. Particular emphasis is laid on combined heat and power schemes, linked to a district heating network. (U.K.)

  5. The UK nuclear power industry

    International Nuclear Information System (INIS)

    Collier, J. G.

    1995-01-01

    In the United Kingdom, nuclear power plants are operated by three companies: Nuclear Electric (NE), Scottish Nuclear (SN), and British Nuclear Fuels plc (BNFL). The state-operated power industry was privatized in 1989 with the exception of nuclear power generation activities, which were made part of the newly founded (state-owned) NE and SN. At the same time, a moratorium on the construction of new nuclear power plants was agreed. Only Sizewell B, the first plant in the UK to be equipped with a pressurized water reactor, was to be completed. That unit was first synchronized with the power grid on February 14, 1995. Another decision in 1989 provided for a review to be conducted in 1994 of the future of the peaceful uses of nuclear power in the country. The results of the review were presented by the government in a white paper on May 9, 1995. Accordingly, NE and SN will be merged and privatized in 1996; the headquarters of the new holding company will be in Scotland. The review does not foresee the construction of more nuclear power plants. However, NE hopes to gain a competitive edge over other sources of primary energy as a result of this privatization, and advocates construction of a dual-unit plant identical with Sizewell B so as to avoid recurrent design and development costs. Outside the UK, the company plans to act jointly with the reactor vendor, Westinghouse, especially in the Pacific region; a bid submitted by the consortium has been shortisted by the future operator of the Lungmen nuclear power plant project in Taiwan. In upgrading the safety of nuclear power plants in Eastern Europe, the new company will be able to work through existing contacts of SN. (orig.) [de

  6. Does nuclear power lead to nuclear weapons

    International Nuclear Information System (INIS)

    Prawitz, J.

    1977-01-01

    It is pointed out that 'reactor grade' plutonium usually contains about 30 % Pu240 and is unsuitable for weapons. While it is possible to obtain an explosion, it is more difficult to initiate one and its effect, which will be considerably less than with bomb grade plutonium, is difficult to predict. The critical mass will be larger and more cooling required. The proliferation problem is then discussed and the four aspects, vertical, horizontal, sub-national and revolutionary, mentioned. In connection with nuclear power it is the second and third aspects which are of interest. In discussing the possibility of terrorist groups obtaining plutonium, a study by the Swedish Defence Research Institute is quoted as estimating that 10-20 qualified specialists and several years secret preparation would be necessary to make a nuclear weapon. Other authors, e.g. Ted Taylor, have maintained that it would be much easier, but examples of 'student designs' are primitive and unlikely to detonate. Even so, it is emphasised that safeguards and physical security are necessary. Horizontal proliferation is a more real problem and the NPT and IAEA safeguards are discussed in this connection. In conclusion the question of whether the proliferation of nuclear weapons via nuclear power can be prevented cannot be answered with a clear yes or no. Certain states may use nuclear weapon potential as a bargaining factor. However the decision to acquire nuclear weapons is political and while a nuclear power industry would be of help, it would not be decisively so. (JIW)

  7. Nuclear power for environmental protection

    International Nuclear Information System (INIS)

    Souza Marques de, J.A.; Bennett, L.L.

    1989-09-01

    Nuclear power does not produce CO 2 or other greenhouse gases, and also does not produce any SO 2 , NO x or other gases which contribute to acid rain. These characteristics of nuclear power are especially important in comparison to coal-fired generation of electricity. As an example, in comparison with a coal-fired power plant of the same size, with abatement systems, a 1300 MW(e) nuclear power plant eliminates annually emissions to the air of about: 2000 t of particulates; 8.5 million t of CO 2 : 12,000 t of SO 2 ; and 6,000 t of NO x , the precise quantities being dependent on coal quality, power plant design and thermal efficiency, and on the effectiveness of the abatement systems. Opponents of nuclear power concede these facts, but argue that nuclear power is such a small part of the world energy balance that it is insignificant to the big issue of CO 2 . This is hardly correct. Today, 16% of the world's electricity (and 5% of the world's total primary energy) is generated using nuclear power. If this electricity were to have been generated using coal, it would have resulted in about 1600 million tons of CO 2 annually. This is 8% of the 20,000 million tons of CO 2 now emitted annually from the burning of fossil fuels, an amount which the Toronto Conference proposed should be cut by 20% up to the year 2005. A further major difference in the two energy systems is that the relatively smaller amount of nuclear wastes is fully isolated from the environment. In addition to discussing the global contributions of nuclear power to environmental improvement, the paper presents actual results achieved in a number of countries, demonstrating the positive contribution which nuclear power has made to reducing the environmental impacts of electricity production. 7 figs, 12 tabs

  8. Nuclear power. The Windscale controversy

    International Nuclear Information System (INIS)

    Boyle, G.

    1978-01-01

    The aims of this unit are: (1) to provide a basic understanding of nuclear technology and of the associated technical and environmental problems; (2) to provide an understanding of: (a) the historical growth of the nuclear industry; (b) the arguments for the continued development of nuclear power, and the institutions promoting that development; (3) to provide a basic understanding of the mechanisms and institutions which officially regulate the nuclear power programme in the UK; (4) to provide an understanding of the main issues - technical, economic, social and political - involved in the controversy over the proposed expansion of British Nuclear Fuels Ltd's reprocessing facilities at Windscale, and the events leading up to the Public Inquiry on the proposal which began in June 1977; and (5) to examine (a) the reason for the growth in opposition to nuclear power in various countries and the different approaches taken by the opposition groups; (b) the political impact and effectiveness of that opposition. (author)

  9. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    Grimston, M.C.

    1994-01-01

    The United Kingdom Government's strategy aimed at securing sustainable development has recently been published, and is analysed here by the Energy Issues Adviser, for the British Nuclear Industry Forum. The energy framework aims to ensure secure supplies of energy at competitive prices and to minimise possible adverse environmental impacts of energy use. It is argued here that both of these aims will be promoted by the continued and growing use of nuclear power in the United Kingdom. As the cost of nuclear electricity depends chiefly on the price of uranium, which is likely to stabilize due to increased supplies from nuclear weapons destruction, uranium recycling and mixed oxide fuel reprocessing, it is unlikely that world fuel price inflation will affect these costs. Secondly, nuclear power is not associated with acid rain or the threat of global warming, so its environment protection claims can be substantiated. Indeed, unlike other fuel sources, nuclear power already pays for its waste and decommissioning procedures. (UK)

  10. Nuclear power, economy and environment

    International Nuclear Information System (INIS)

    Stoffaes, C.

    1994-01-01

    The explanations in this article aim at clarifying the background of the problem of nuclear energies. Why did countries give up developing nuclear energy? Which roles do economic political and psychological factors play in making energy political decisions? How could a balance be found in using the various energy sources which must meet the constantly increasing demand for electric power? Which preconditions must be fulfilled to return to nuclear energy world-wide (as using coal is connected with many environmental risks) and how long would it take? If, however, nuclear power is even to be included in the energy-political discussions of the governments and the public opinions in each country, there are a number of sensitive topics waiting for an answer: Safety and costs of power plants; recycling and storing nuclear wastes; the relationship between civil energy and the availability of nuclear weapons and the future plutonium economy. (orig./UA) [de

  11. The future of nuclear power

    International Nuclear Information System (INIS)

    Burtak, F.

    1993-01-01

    Nuclear power in Germany at present is confronting two challenges: On the one hand, technical innovations are required in order to meet the expectations of nuclear proponents while, on the other hand, a public stand must be taken vis-a-vis the demand to opt out of nuclear power. This means that nuclear engineers not only must perform their technical functions, but increasingly also engage themselves socially. Neglecting just one of these two challenges is likely to impair severely the future of nuclear power in Germany. In the absence of a swing in public opinion it will not be possible to build a new nuclear plant, and nuclear power will be doomed to extinction, at least in a number of countries, within a matter of decades. In the absence of technical innovation, today's LWR technology will cause the fissile uranium available naturally to be consumed, thus killing nuclear power for lack of future fissile material. In responding to the two challenges, nuclear technology must safeguard its future by not retreating into an ivory tower of pure technology; on the other hand, technical innovation is a prerequisite for its continued existence. (orig.) [de

  12. The economics of nuclear power

    International Nuclear Information System (INIS)

    Hunt, H.; Betteridge, G.

    1978-01-01

    It is stated that nuclear power stations throughout the world are now providing consumers with substantially the cheapest electricity, except in areas with extensive hydro-power or cheap, clean, local coal. Thermal nuclear power stations will continue to provide economic electricity until the cost of uranium rises to several times the present level; fast reactors have the potential to continue to stabilise the cost of electricity and by moderating demand for other fuels will keep down their cost also. Headings of this paper include -The historical perspective; methods of comparing nuclear and fossil generating costs; historical comparisons of UK nuclear and fossil generating costs; waste storage and decommissioning; future changes in costs; criteria for future investment in nuclear power; alternative methods of comparison; total system cost analysis; the economics of fast reactors; and the ultimate role of fast reactors. 13 references. (author)

  13. Nuclear power 1984: Progressive normalisation

    International Nuclear Information System (INIS)

    Popp, M.

    1984-01-01

    The peaceful use of nuclear power is being integrated into the overall concept of a safe long-term power supply in West Germany. The progress of normalisation is shown particularly in the takeover of all stations of the nuclear fuel circuit by the economy, with the exception of the final storage of radioactive waste, which is the responsibility of the West German Government. Normalisation also means the withdrawal of the state from financing projects after completion of the two prototypes SNR-300 and THTR-300 and the German uranium enrichment plant. The state will, however, support future research and development projects in the nuclear field. The expansion of nuclear power capacity is at present being slowed down by the state of the economy, i.e. only nuclear power projects being built are proceeding. (orig./HP) [de

  14. Diversification of the VVER fuel market in Eastern Europe and Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Kirst, Michael [Westinghouse EMEA, Brussels (Belgium); Benjaminsson, Ulf; Oenneby, Carina [Westinghouse Electric Sweden AB, Vaesteraes (Sweden)

    2015-03-15

    There are a total of 33 VVER active reactors in the EU and Ukraine, accounting for the largest percentage of the total electricity supply in the countries operating these. The responsible governments and utilities operating these units want too see an increased diversification of the nuclear fuel supply. Westinghouse is the only nuclear fuel producer outside Russia, which has taken the major steps to develop, qualify and manufacture VVER fuel designs - both for VVER-440 and VVER-1000 reactors. The company has delivered reloads of VVER-440 fuel to Loviisa 2 in Finland, VVER-1000 fuel for both the initial core and follow-on regions to Temelin 1-2 in the Czech Republic and more recently reloads of VVER-1000 fuel to South Ukraine 2-3. Technical challenges in form of mechanical interference with the resident fuel have been encountered in Ukraine, but innovative solutions have been developed and successfully implemented and today Ukraine has, for the first time in its history, a viable VVER-1000 fuel design alternative, representing a tremendous lever in energy security for the country.

  15. Towards sustainable nuclear power development

    International Nuclear Information System (INIS)

    Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S.

    2014-01-01

    The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

  16. Nuclear power and the environment

    International Nuclear Information System (INIS)

    Mackerron, Gordon; Berkhout, Frans

    1990-01-01

    The environmental effects of nuclear power discussed in this paper are specifically the effects of radiation on human populations, either directly or through the food chain. Controlling the environmental effects of nuclear power has two dimensions, waste management and safety. Regulatory controls aim to keep the risk of death due to man-made radiation down to what is thought to be an acceptable level; the background to the establishing of such levels is examined. The scale of the nuclear industry is outlined. In industrial countries with nuclear power, with the possible exception of the USA and USSR which have extensive nuclear weapons programmes, most radioactive wastes arise in the civil nuclear fuel cycle; medical, research and industrial users of nuclear materials produce the rest. The extreme variety of materials included in radioactive wastes is highlighted. Approaches to the management of different kinds of radioactive waste are discussed; the particular problems associated with reactor decommissioning are considered. The enormous potential harm of serious accidents at nuclear power plants through a release of large quantities of radionuclides into the environment has been a dominant influence in the design of reactors. The accidents at Three Mile Island and Chernobyl underline the need for careful examination of management issues as well as design and operational failures. Finally, the catastrophic effects of a full scale nuclear war are briefly considered within the context of nuclear proliferation and international security. (UK)

  17. Towards sustainable nuclear power development

    Energy Technology Data Exchange (ETDEWEB)

    Andrianov, Andrei A.; Murogov, Victor M.; Kuptsov, Ilya S. [Obninsk Institute for Nuclear Power Engineering of NNRU MEPhl, Obninsk, Kaluga Region (Russian Federation)

    2014-05-15

    The review of the current situation in the nuclear energy sector carried out in this article brings to light key problems and contradictions, development trends and prospects, which finally determine the role and significance of nuclear power as a factor ensuring a sustainable energy development. Authors perspectives on the most appropriate developments of nuclear power, which should be based on a balanced use of proven innovative nuclear technologies and comprehensive multilateral approaches to the nuclear fuel cycle are expressed. The problems of wording appropriate and essential requirements for new countries with respect to their preparedness to develop nuclear programs, taking into account their development level of industry and infrastructure as well as national heritages and peculiarities, are explained. It is also indicated that one of the major components of sustainability in the development of nuclear power, which legitimates its public image as a power technology, is the necessity of developing and promoting the concepts of nuclear culture, nuclear education, and professional nuclear ethics. (orig.)

  18. Nuclear power prospects in Finland

    International Nuclear Information System (INIS)

    1961-01-01

    The basic circumstances which stimulated Finland's interest in nuclear power are summarized in the report as follows: 'In Finland the main power resource has been, and still is, water power. It is clear, however, that the hydro potential is insufficient to cover the increasing consumption over a long period of time. Already about one half of this potential has been exploited. Thus the country will necessarily have to consider the utilization of thermal power to an increasingly large extent. There is no indigenous coal or oil. For this reason it has become necessary to investigate realistically the possibilities offered by nuclear power'

  19. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    1982-01-01

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

  20. Experimental support of the bleed and feed accident management measures for VVER-440/213 type reactors

    International Nuclear Information System (INIS)

    Szabados, L.

    2002-01-01

    In the original design of the VVER-440/213 type nuclear power plants event oriented emergency operating procedures (EOP) were implemented. In the last years, however, new symptom based procedures of Westinghouse-type have been developed and partly implemented for the plants in Central Europe including the Paks Nuclear Power Plant. Paper gives a short review of the experiments performed in the PMK-2 facility to study the effectiveness of the bleed and feed strategies and to get experimental data bases for the validation of thermohydraulic system codes like RELAP5, ATHLET and CATHARE.(author)

  1. Nuclear power - a reliable future

    International Nuclear Information System (INIS)

    Valeca, Serban

    2002-01-01

    The Ministry of Education and Research - Department of Research has implemented a national Research and Development program taking into consideration the following: - the requirements of the European Union on research as a factor of development of the knowledge-based society; - the commitments to the assimilation and enforcement of the recommendations of the European Union on nuclear power prompted by the negotiations of the sections 'Science and Research' and ' Energy' of the aquis communautaire; - the major lines of interest in Romania in the nuclear power field established by National Framework Program of Cooperation with IAEA, signed on April 2001; - the short and medium term nuclear options of the Romanian Government; - the objectives of the National Nuclear Plan. The major elements of the nuclear research and development program MENER (Environment, Energy, Resources) supported by the Department of Research of the Ministry of Education and Research are the following: - reactor physics and nuclear fuel management; - operation safety of the Power Unit 1 of Cernavoda Nuclear Electric Power Station; - improved nuclear technological solutions at the Cernavoda NPP; - development of technologies for nuclear fuel cycle; - operation safety of the other nuclear plants in Romania; - assessment of nuclear risks and estimation of the radiological impact on the environment; - behavior of materials under the reactor service conditions and environmental conditions; - design of nuclear systems and equipment for the nuclear power stations and nuclear facilities; - radiological safety; - application of nuclear techniques and technologies in industry, agriculture, medicine and other fields of social life. Research to develop high performance methods and equipment for monitoring nuclear impact on environment are conducted to endorse the measures for radiation protection. Also mentioned are the research on implementing a new type of nuclear fuel cycle in CANDU reactors as well as

  2. VVER fuel. Results of post irradiation examination

    International Nuclear Information System (INIS)

    Smirnov, V.P.; Markov, D.V.; Smirnov, A.V.; Polenok, V.S.; Perepelkin, S.O.; Ivashchenko, A.A.

    2005-01-01

    The present paper presents the main results of post-irradiation examination of more than 40 different fuel assemblies (FA) operated in the cores of VVER-1000 and VVER-440-type power reactors in a wide range of fuel burnup. The condition of fuel assembly components from the viewpoint of deformation, corrosion resistance and mechanical properties is described here. A serviceability of the FA design as a whole and interaction between individual FA components under vibration condition and mechanical load received primary emphasis. The reasons of FA damage fuel element failure in a wide range of fuel burnup are also analyzed. A possibility and ways of fuel burnup increase have been proved experimentally for the case of high-level serviceability maintenance of fuel elements to provide for advanced fuel cycles. (author)

  3. VVER-1000: considering its strengths and weaknesses

    International Nuclear Information System (INIS)

    Laaksonen, J.

    1994-01-01

    The safety of currently operating VVER-1000 reactors is examined. The factors considered are deviations in operation, inherent safety, safety system design, protection against internal and external hazards, equipment quality, the approach to plant operations and the safety culture. On the basis of this evaluation it is concluded that the overall safety of a VVER-1000 cannot be at the level of a modern Western PWR though there is no sound basis to make a quantitative comparison. Many of the concerns raised are being adequately addressed in the Czech Temelin which is currently under construction and in new designs which are still at the drawing board stage. Extensive back fitting programmes are planned or underway in operating plants. The creation of independent responsible operating organizations, powerful regulation and an improved economic situation are advanced as necessary criteria for real improvements in safety. (UK)

  4. Nuclear reactor power supply

    International Nuclear Information System (INIS)

    Cook, B.M.

    1982-01-01

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

  5. Hydrogen from nuclear power

    International Nuclear Information System (INIS)

    Miller, A.I.

    2006-01-01

    A few years ago, one frequently heard the view that LNG would cap the price of natural gas in North America at around 5 or 6 US$/GJ just as soon as sufficient terminal capacity could be installed. Recent experience with international LNG prices suggests that this is unlikely. While oil and gas prices have proven almost impossible to predict it seems likely that the price of gas will in future broadly track its energy equivalent in oil. Consequently, planning for natural gas at 10 $/GJ would seem prudent. Using steam-methane reforming, this produces hydrogen at 1500 $/t. If CO 2 has to be sequestered, adding another 500 $/t H 2 is a likely additional cost. So is water electrolysis now competitive? Electrolysis would deliver hydrogen at 2000$/t if electricity costs 3.7 US cents/kWh. This is lower than the Alberta Pool average supply price but very close to AECL's estimated cost for power from a new reactor. However, electricity prices in deregulated markets vary hugely and there would be large leverage on the hydrogen price in delivering a mix of electricity (when the Pool price is high) and hydrogen (when it is low). The key to that possibility - as well as other issues of interruptibility - is low-cost cavern storage, similar to that used for natural gas. One long-standing example for hydrogen storage exists in the UK. The nuclear-electrolysis route offers long-term price stability. It also has co-product possibilities if a use can be found for oxygen (equivalent to about 300 $/t H 2 ) and to produce heavy water (provided the scale is at least 100 MW)

  6. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    1991-01-01

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

  7. Nuclear power plant diagnostic system

    International Nuclear Information System (INIS)

    Prokop, K.; Volavy, J.

    1982-01-01

    Basic information is presented on diagnostic systems used at nuclear power plants with PWR reactors. They include systems used at the Novovoronezh nuclear power plant in the USSR, at the Nord power plant in the GDR, the system developed at the Hungarian VEIKI institute, the system used at the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia and systems of the Rockwell International company used in US nuclear power plants. These diagnostic systems are basically founded on monitoring vibrations and noise, loose parts, pressure pulsations, neutron noise, coolant leaks and acoustic emissions. The Rockwell International system represents a complex unit whose advantage is the on-line evaluation of signals which gives certain instructions for the given situation directly to the operator. The other described systems process signals using similar methods. Digitized signals only serve off-line computer analyses. (Z.M.)

  8. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    Lane, J.A.; Covarrubias, A.J.; Csik, B.J.; Fattah, A.; Woite, G.

    1977-01-01

    This paper is intended to be a companion to similar papers by OECD/NEA and CMEA and will summarize the nuclear power system plans of developing Member States most likely to have nuclear programmes before the year 2000. The information that is presented is derived from various sources such as the Agency 1974 study of the market for nuclear power in developing countries, the annual publication, ''Power Reactors in Member States - 1976 Edition'', various nuclear power planning studies carried out by the Agency during the period 1975 and 1976, direct correspondence with selected Member States and published information in the open literature. A preliminary survey of the prospects for nuclear power in Member States not belonging to the OECD or having centrally planned economies indicates that about 27 of these countries may have operating nuclear power plants by the end of the century. In the 1974 Edition of the ''Market Survey'' it was estimated that the installed nuclear capacity in these countries might reach 24 GW by 1980, 157 GW by 1190 and 490 GW by the year 2000. It now appears that these figures are too high for a number of reasons. These include 1) the diminished growth in electrical demand which has occurred in many Member States during the last several years, 2) the extremely high cost of nuclear plant construction which has placed financial burdens on countries with existing nuclear programmes, 3) the present lack of commercially available small and medium power reactors which many of the smaller Member States would need in order to expand their electric power systems and 4) the growing awareness of Member States that more attention should be paid to exploitation of indigenous energy sources such as hydroelectric power, coal and lignite

  9. 2006 nuclear power world report

    International Nuclear Information System (INIS)

    Anon.

    2007-01-01

    At the turn of 2006/2007, 437 nuclear power plants were available for energy supply, or were being commissioned, in 31 countries of the world. This is seven plants less than at the turn of 2005/2006. The aggregate gross power of the plants amounted to approx. 389.5 GWe, the aggregate net power, to 370.5 GWe. This indicates a slight decrease of gross power by some 0.15 GWe compared to the level the year before, while the available net power increased, also slightly, by approx. 0.2 GWe. The Tarapur 3 nuclear generating unit in India, a D 2 O PWR of 540 MWe gross power, was newly commissioned. In 2006, 8 nuclear power plants in Europe (4 in the United Kingdom, 2 in Bulgaria, 1 each in the Slovak Republic and in Spain) discontinued power operation for good. 29 nuclear generating units, i.e. 6 plants more than at the end of 2005, were under construction in late 2006 in 9 countries with an aggregate gross power of approx. 25.5 GWe. Worldwide, some 40 new nuclear power plants are in the concrete project design, planning, and licensing phases; in some of these cases, contracts have already been signed. Net electricity generation in nuclear power plants worldwide in 2006 achieved another top ranking level of approx. 2,660 billion kWh (2005: approx. 2,750 billion kWh). Since the first generation of electricity in a nuclear power plant in the EBR-1 fast breeder (USA) on December 20, 1951, cumulated gross production has reached approx. 56,875 billion kWh, and operating experience has grown to some 12,399 reactor years. (orig.)

  10. Nuclear power: status and outlook

    International Nuclear Information System (INIS)

    Rogner, H.H.; Langlois, L.M.; McDonald, A.

    2002-01-01

    Current state of the world nuclear energetics is reviewed; data on operating and nuclear power blocks under construction in different countries, data on electric power output, practice of operation are presented. New plans of energetic reactors, capitalized costs for their construction, operating cost and period of construction are treated. Problems of nuclear safety, spent fuel and radioactive waste management, non-proliferation policy are discussed. Outlook for the development of the nuclear energetics is directed and importance of the Bonn agreement in connection with economic reasons for NPP operation is noted [ru

  11. On PA of nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Present state of things relating to the nuclear power generation are described first, focusing on the Chernobyl accident, power control test, old-wave and new-wave antinuclear movements, move toward elimination of nuclear power plants, and trend in government-level argument concerning nuclear power generation. Then the importance of public relations activities for nuclear power generation is emphasized. It is stressed that information should be supplied positively to the public to obtain public understanding and confidence. Various activities currently made to promote public relations for nuclear power generation are also outlined, focusing on the improvement in the nuclear power public relations system and practical plans for these activities. Activities for improvement in the public relations system include the organization of public relations groups, establishment and effective implementation of an overall public relations plan, training of core workers for public relations, and management of the public relations system. Other practical activities include the encouragement of the public to come and see the power generation facilities and distribution of pamphlets, and use of the media. (N.K.)

  12. LDC nuclear power: Iran

    International Nuclear Information System (INIS)

    Mossavar-Rahmani, B.

    1982-01-01

    The Islamic Revolutionary Government has eliminated what had been an ambitious program to install 23,000 MWe of nuclear capacity by 1984, but the program has already become unpopular before the downfall to the Shah for economic reasons. Iran originally planned a domestic nuclear program to diversify its energy base and satisfy Western demands to recycle petrodollars, but substantial commissions for foreign contracts were also a factor. No comprehensive study of a nuclear program has been done to determine if there is a nuclear future for Iran. 8 references

  13. Dictionary of nuclear power. upd. ed.

    International Nuclear Information System (INIS)

    Koelzer, W.

    2011-10-01

    The updated dictionary on nuclear power contains definitions and explanations on nuclear physics, nuclear engineering, nuclear power, radiation effects and radiation protection in alphabetic order. Attachments on units, their conversion and physical constants are included.

  14. Greenfield nuclear power for Finland

    Energy Technology Data Exchange (ETDEWEB)

    Saarenpaa, Tapio

    2010-09-15

    In Finland, licensing for new nuclear power is ongoing. The political approval is to be completed in 2010. Fennovoima's project is unique in various ways: (i) the company was established only in 2007, (ii) its ownership includes a mixture of local energy companies, electricity-intensive industries and international nuclear competence through E.ON, and (iii) it has two alternative greenfield sites. There are five prerequisites for a successful nuclear power project in a transparent democracy of today: (1) need for additional power capacity, (2) actor prepared to invest, (3) established competence, (4) available site, (5) open communications, and (6) favorable public opinion.

  15. Partner of nuclear power plants

    International Nuclear Information System (INIS)

    Gribi, M.; Lauer, F.; Pauli, W.; Ruzek, W.

    1992-01-01

    Sulzer, the Swiss technology group, is a supplier of components and systems for nuclear power plants. Important parts of Swiss nuclear power stations, such as containments, reactor pressure vessels, primary pipings, are made in Winterthur. Sulzer Thermtec AG and some divisions of Sulzer Innotec focus their activities on servicing and backfitting nuclear power plants. The European market enjoys priority. New types of valves or systems are developed as economic solutions meeting more stringent criteria imposed by public authorities or arising from operating conditions. (orig.) [de

  16. Nuclear power. Volume 2: nuclear power project management

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The following topics are discussed: review of nuclear power plants; licensing procedures; safety analysis; project professional services; quality assurance and project organization; construction, scheduling and operation; construction, scheduling and operation; nuclear fuel handling and fuel management; and plant cost management. 116 references, 115 figures, 33 tables

  17. The economics of nuclear power

    International Nuclear Information System (INIS)

    Monto, Geethanjali

    2011-01-01

    Nuclear power is seen by some as a partial solution to climate change. The obvious supporters include nuclear establishments, but the 'surprising' supporters comprise some environmentalists like James Lovelock. One of the 15 strategies proposed by Stephen Pacala and Robert Socolow as part of their wedge model is to substitute nuclear power for coal power. The addition of 700 GW of nuclear power, i.e. roughly twice the current global capacity, would constitute one wedge and could reduce one billion tonnes of carbon by mid-century. (The other 14 strategies include: efficient vehicles; reduced use of vehicles; efficient buildings; efficient baseload coal plants; gas baseload power for coal baseload power capture CO 2 at baseload power plant capture CO 2 at H 2 plant; capture CO 2 at coal-to-synfuels plant and geological storage; wind power for coal power; PV power for coal power; wind H 2 in fuel-cell car for gasoline in hybrid car; biomass fuel for fossil fuel; reduced deforestation, plus reforestation, afforestation, and new plantations, and conservation tillage

  18. Nuclear power: An evolving scenario

    International Nuclear Information System (INIS)

    ElBaradei, Mohamed

    2004-01-01

    The past two years have found the IAEA often in the spotlight - primarily because of our role as the world's 'nuclear watchdog', as we are sometimes referred to on the evening news. The most visible, and often controversial, peaceful nuclear application is the generation of electricity, the focus of this article largely from a European perspective. At the end of last year there were 440 nuclear power units operating worldwide. Together, they supply about 16% of the world's electricity. That percentage has remained relatively steady for almost 20 years. Expansion and growth prospects for nuclear power are centred in Asia. Of the 31 units under construction worldwide, 18 are located in India, Japan, South Korea and China, including Taiwan. Twenty of the last 29 reactors to be connected to the grid are also in the Far East and South Asia. That is probably more active construction than most Europeans would guess, given how little recent growth has occurred in the West. For Western Europe and North America, nuclear construction has been a frozen playing field - the last plant to be completed being Civaux-2 in France in 1999. That should raise a question: with little to no new construction, how has nuclear power been able to keep up with other energy sources, to maintain its share of electricity generation? Interestingly enough, the answer is tied directly to efforts to improve safety performance. The accident at Chernobyl in 1986 prompted the creation of the World Association of Nuclear Operators (WANO), and revolutionized the IAEA approach to nuclear power plant safety. Some analysts believe the case for new nuclear construction in Europe is gaining new ground, for a number of reasons: efforts to limit greenhouse gas emissions and reduce the risk of climate change; security of energy supply; Comparative Public Health Risk; different set of variables when choosing Each country's and region energy strategy. Looking to the future, certain key challenges are, of direct

  19. Nuclear power generation and nuclear nonproliferation

    International Nuclear Information System (INIS)

    Walske, C.

    1978-01-01

    In the future outlook around year 2000 of nuclear power, thought must be given to fuel reprocessing and plutonium utilization. The adverse utilization of plutonium may be prevented by the means balanced with its economical value. As the method of less cost with lower effect of nonproliferation, combination of fuel reprocessing and fuel fabrication facilities and mixed plutonium/uranium processing are possible. As the method of more cost with higher effect of nonproliferation the maintenance of high radioactivity and inaccessibility of plutonium is conceivable. As for the agreeable methods in 2000, seven principles may be mentioned, such as the dependence upon the agreements among major nations and upon nuclear exporting countries. These are still inadequate, however. What is important is to provide with the sufficient safeguards to countries concerned to negate the need for nuclear weapons. Efforts are then necessary for leading nuclear countries to extend aids to other nuclear-oriented countries. (Mori, K.)

  20. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    Solito, J.

    1978-04-01

    The judicial aspects of nuclear stations licensing are presented. The licensing systems of the United States, Spain, France and Federal Republic of Germany are focused. The decree n 0 60.824 from July 7 sup(th), 1967 and the following legislation which define the systematic and area of competence in nuclear stations licensing are analysed [pt