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Sample records for bwr nuclear power

  1. Siemens Nuclear Power Corporation experience with BWR and PWR fuels

    International Nuclear Information System (INIS)

    The large data base of fuel performance parameters available to Siemens Nuclear Power Corporation (SNP), and the excellent track record of innovation and fuel reliability accumulated over the last twenty-three years, allows SNP to have a clear insight on the characteristics of future developments in the area of fuel design. Following is a description of some of SNP's recent design innovations to prevent failures and to extend burnup capabilities. A goal paramount to the design and manufacture of BWR and PWR fuel is that of zero defects from any case during its operation in the reactor. Progress has already been made in achieving this goal. This paper summarized the cumulative failure rate of SNP fuel rod through January 1992

  2. An ecological interface design for BWR nuclear power plants

    International Nuclear Information System (INIS)

    An ecological interface design was applied to realize the support function for the operator's direct perception and analytical reasoning in the development of an intelligent man-machine system for BWR nuclear power plants. The abstraction-aggregation functional hierarchy representation of the work domain is a base of the ecological interface design. Another base is the concept of the level of cognitive control. The former was mapped into the interface to externalize the operator's normative mental model of the plants, which will reduce his/her cognitive work load and support knowledge-based problem solving. In addition, the same framework can be used for the analytical evaluation of man-machine interfaces. The information content and structure of a prototype interface were evaluated. This approach seems promising from these experiences. (author)

  3. BWR 90+ - Nuclear power plant for 21st century

    International Nuclear Information System (INIS)

    BWR 90+ is a boiling water reactor, based on the previous models BWR90 and BWR75, and on the operational experiences gained with six reactors of the previous generation. The development work started in 1994 in co-operation with Teollisuuden Voima Oy (TVO). At present all the boiling water reactor owners participate the cooperation. The objectives of the development were: (1) to develop a boiling water reactor of competitive price level and short construction time, and which meets the latest safety requirements, (2) to itemize the technologies improving the security and competitivity of present plants, and (3) to maintain the expertise of the personnel of the companies participating the development work, and improving the BWR- technology. High power output and short construction time reduce the power generation costs. Large amount of fuel assemblies leads to higher safety margins. Reduction of scram groups from 18 to 16 reduces the amount of components, the assembly space and costs. The reactor technical data is as follows: Thermal power output 4250 MWth; electric power output 1500 MWe, construction time 1500 days, costs 1500 pounds/kWe, no. of fuel assemblies 872, no. of scram groups 16, turbines 1, the capacity factor 90% and the duration of service outage 3 weeks. Specific features of BWR90+ are: short construction time and low costs, risk for connection between wet and dry spaces has been minimized, reactor core remains covered by water during loss-of-coolant accident caused by fuel replacement, Passive collection and cooling of core-melt inside the containment, the containment is not the first wall against the spreading of core-melt, steam explosions and core- concrete interactions have low probabilities, high gas- volume of wet-space reduces the pressure increase during a severe accident, filter-equipped gas removal system forms the final overpressure shield, the containment is cylindrical, and the plant is equipped with digital instrumentation and control

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

    International Nuclear Information System (INIS)

    The needs of fresh water increased by rapid population growth and industrials expansion, but these demands can not be prepared naturally. Following this case, seawater desalination becomes the primer option which can fulfill the need through the nuclear desalination technology. The coupled nuclear power reactor enables to supply thermal energy for auxiliary equipment and pumps operation. The utilization study of power reactor type BWR coupled with desalination process has been performed. The goal of study is to obtain characteristic data of desalted water specification which desalination system coupling with nuclear power plant produced energy for desalination process. The study is carried out by browsing data and information, and comprehensive review of thermal energy correlation between NPP with desalination process installation. According to reviewing are found that the thermal energy and electric power utilization from the nuclear power reactor are enable to remove the seawater to produce desalted water and also to operate auxiliary equipments. The assessment results is VK-300 reactor prototype, BWR type 250 MW(e) power are cogeneration unit can supplied hot steam temperature 285 °C to the extraction turbine to empower 150 MW electric power, and a part of hot steam 130 °C is use to operate desalination process and remind heat is distribute to the municipal and offices at that region. The coupled of VK-300 reactor power type BWR with desalination installation of MED type enable to produce desalted water with high quality distillate. Based on the economic calculation that the VK-300 reactor power of BWR type produced water distillate capacity is 300.000 m3/hour with cost US$ 0.58/m3. The coupling VK-300 reactor power type BWR with MED desalination plant is competitive economically. (author)

  5. The stability analysis of LAPUR6 for Chinshan BWR nuclear power plant

    International Nuclear Information System (INIS)

    Chinshan Nuclear Power Plant (NPP) is the first NPP in Taiwan which is a BWR/4 plant. The original rated power for each unit was 1775 MWt. After the project of measurement uncertainty recovery (MUR) for Chinshan NPP, the operating power is 1805 MWt now. The Chinshan NPP Unit 2 cycle 23 stability analyses were performed by the LAPUR6 stability analysis methodology. Comparing the LAPUR6 stability analysis results and vendor's results, they are similar. (author)

  6. Validation of BWR advanced core and fuel nuclear designs with power reactor measurements

    International Nuclear Information System (INIS)

    Power reactor measurements have been important in validating the reliability, performance characteristics and economics of BWR advanced core and fuel designs. Such measurements go beyond the data obtainable from normal reactor operation and provide detailed benchmark data necessary to verify design and licensing computer design and simulation models. In some cases, such as in the validation of the performance of zirconium barrier pellet-cladding-interaction (PCI) resistant cladding, the BWR power reactor measurements have subjected the advanced fuel design to operating conditions more severe than normal operating conditions, thereby providing nuclear-thermal-mechanical-corrosion performance data for accelerated or extended conditions of operation. In some cases destructive measurements have been carried out on BWR power reactor fuel to provide microscopic and macroscopic data of importance in validating design and licensing analysis methods. There is not uniform agreement among core and fuel designers on the needs for special power reactor core and fuel measurements for validation of advanced designs. The General Electric approach has been to error on the side of extensive, detailed measurements so as to assure reliable performance licensing and economic design and predictive capability. This paper is a summary of some of the validative power reactor measurements that have been carried out on advanced BWR core and fuel designs. Some comparisons of predictions with the data are summarized

  7. Development of a dynamic model of a BWR nuclear power plant

    International Nuclear Information System (INIS)

    A dynamic model of a nuclear power plant, including a boiling water reactor, high- and low-pressure turbines, moisture separator, reheater, condenser, feedwater heaters and feedwater pump, was developed. The model is one-dimensional except for the nuclear part of the reactor, which is based on the point kinetics equation, and the condenser model and feedwater pump model. It has been used to study different transients occuring during normal operating conditions and for evaluating the control systems of a BWR nuclear power plant. Particular emphasis was laid on the reactor pressure control system and the recirculation flow control system. (author)

  8. Water chemistry management of nuclear power plant. Water chemistry management of BWR plant

    International Nuclear Information System (INIS)

    There are two kinds of nuclear power plants such as Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) in Japan. In this paper, a water chemistry management of BWR plant is explained. BWR plant makes steam produced in the reactor send to the turbine and produce power, then condensate in the main condenser and use again as feed water. The objects of water chemistry management of BWR are security of good conditions of fuel and structure materials and reduction of the dose equivalent and the radioactive waste. The volume of coolant depends on the temperature change, the concentration of boric acid for neutron absorber, lithium hydroxide for pH control and hydrogen gas for corrosion are controlled. Impurity metals in water of reactor are removed by the condensate demineralizer. The concentration of boron and lithium is controlled from 0 to 4000 ppm and from 0.2 to 2.2 ppm, respectively. On water chemistry technologies for dose reduction, oxygen injection into feed water and control operation of rate of Ni/Fe are explained. On the technologies for preventive maintenance, degassing operation of reactor and hydrogen injection into feed water are described. (S.Y.)

  9. Dry well cooling systems in BWR type nuclear power plants

    International Nuclear Information System (INIS)

    Purpose: To prevent the damages of pipeways due to salt damages at the surface of control rod drives in BWR type reactors. Constitution: In control rod drives and the lowermost area in the dry well in which surface corrosion and pitching have been resulted by the salt contents in air due to the increase in the humidity accompanying the lowering of the temperature, a blower is disposed to the upstream of the cooling coils and a portion of high temperature air returned to the lower cooler is replaced with a low temperature feed air to increase the feed temperature in the area. Further, by upwardly turning the downwarded feed air drawing port in which cold feed air has so far been descended as it is, the descendance of the cold air is suppressed. As a result, temperature lowering in the driving mechanisms and the lower area can be prevented to obtain a predetermined temperature, whereby the dewing on the surface can be prevented and thereby preventing the occurrence of corrosion and pitching. (Horiuchi, T.)

  10. The development of emergency core cooling systems in the PWR, BWR, and HWR Candu type of nuclear power plants

    International Nuclear Information System (INIS)

    Emergency core cooling systems in the PWR, BWR, and HWR-Candu type of nuclear power plant are reviewed. In PWR and BWR the emergency cooling can be catagorized as active high pressure, active low pressure, and a passive one. The PWR uses components of the shutdown cooling system: whereas the BWR uses components of pressure suppression contaiment. HWR Candu also uses the shutdown cooling system similar to the PWR except some details coming out from moderator coolant separation and expensive cost of heavy water. (author)

  11. Laguna Verde nuclear power plant: an experience to consider in advanced BWR design

    International Nuclear Information System (INIS)

    Laguna Verde is a BWR 5 containment Mark II. Designed by GE, two external re-circulation loops, each of them having two speed re-circulation pump and a flow control valve to define the drive flow and consequently the total core flow an power control by total core flow. Laguna Verde Design and operational experience has shown some insights to be considering in design for advanced BRW reactors in order to improve the potential of nuclear power plants. NSSS and Balance of plant design, codes used to perform nuclear core design, margins derived from engineering judgment, at the time Laguna Verde designed and constructed had conducted to have a plant with an operational license, generating with a very good performance and availability. Nevertheless, some design characteristics and operational experience have shown that potential improvements or areas of opportunity shall be focused in the advanced BWR design. Computer codes used to design the nuclear core have been evolved relatively fast. The computers are faster and powerful than those used during the design process, also instrumentation and control are becoming part of this amazing technical evolution in the industry. The Laguna Verde experience is the subject to share in this paper. (author)

  12. CAE advanced reactor demonstrators for CANDU, PWR and BWR nuclear power plants

    International Nuclear Information System (INIS)

    CAE, a private Canadian company specializing in full scope flight, industrial, and nuclear plant simulators, will provide a license to IAEA for a suite of nuclear power plant demonstrators. This suite will consist of CANDU, PWR and BWR demonstrators, and will operate on a 486 or higher level PC. The suite of demonstrators will be provided to IAEA at no cost to IAEA. The IAEA has agreed to make the CAE suite of nuclear power plant demonstrators available to all member states at no charge under a sub-license agreement, and to sponsor training courses that will provide basic training on the reactor types covered, and on the operation of the demonstrator suite, to all those who obtain the demonstrator suite. The suite of demonstrators will be available to the IAEA by March 1997. (author)

  13. Operational experience of human-friendly control and instrumentation systems for BWR nuclear power plants

    International Nuclear Information System (INIS)

    In recent BWR nuclear power plants in Japan, an advanced centralized monitoring and control system PODIA (Plant Operation by Displayed Information and Automation), which incorporates many operator aid functions, has been in operation since 1985. Main functions of the PODIA system as a computerized operator aid system are as follows. CRT displays for plant monitoring. Automatic controls and operation guides for plant operation. Stand-by status monitoring for engineered safety features during normal operation. Surveillance test procedure guides for engineered safety features. Integrated alarm display. The effectiveness of these functions have been proved through test and commercial operation. It has been obtained that operators have preferred PODIA much more than conventional monitoring and control systems

  14. Experimental study for quantative aging evaluation of epoxy liner in BWR nuclear power plant

    International Nuclear Information System (INIS)

    The purpose of this study is an experimental approach to quantitatively evaluate the aging status of epoxy coating onto containment structure in BWR nuclear power plant. Based on accelerated aging experiment for 64 days, adhesion test was performed to evaluate an physical bonding. To compare with adhesion data, both impedance data by UT and data by thermal gravimetric analysis were obtained during experiment. At almost 50% of adhesion force decrease, it was identified that aging phenamena of epoxy such as pine hole, blistering was discovered. Coating to establish aging status of epoxy, relations among three kinds of different data were analyze. By compatibility of these data, physical aging situation of as-built epoxy coating was figured out. The possibility to develop new methodology of time-dependent aging status on epoxy coating was identified

  15. Parameter identification of a BWR nuclear power plant model for use in optimal control

    International Nuclear Information System (INIS)

    The problem being considered is the modeling of a nuclear power plant for the development of an optimal control system of the plant. Current system identification concepts, combining input/output information with a-priori structural information are employed. Two of the known parameter identification methods i.e., a least squares method and a maximum likelihood technique, are studied as ways of parameter identification from measurement data. A low order state variable stochastic model of a BWR nuclear power plant is presented as an application of this approach. The model consists of a deterministic and a noise part. The deterministic part is formed by simplified modeling of the major plant dynamic phenomena. The moise part models the effects of input random disturbances to the deterministic part and additive measurement noise. Most of the model parameters are assumed to be initially unknown. They are identified using measurement data records. A detailed high order digital computer simulation is used to simulate plant dynamic behaviour since it is not conceivable for experimentation of this kind to be performed on the real nuclear power plant. The identification task consists in adapting the performance of the simple model to the data acquired from this plant simulation ensuring the applicability of the techniques to measurement data acquired directly from the plant. (orig.)

  16. Cooperative control scheme for an HVDC system connected to an isolated BWR nuclear power plant

    International Nuclear Information System (INIS)

    This paper describes a cooperative control system to achieve stable operation of an isolated BWR nuclear plant linked to an HVDC system. In the proposed control system, under normal conditions the power plant is controlled according to the generating power reference and the generator frequency deviation is adjusted by converter power control. Such frequency control is also effective in the case of AC-DC system faults. In addition to the frequency control, an overload control is provided with the HVDC system, where the DC transmission power in the sound poles is increased due to a fault detection signal from the faulty pole. Effects of the above mentioned control systems were studied using digital dynamic programs. The sets of simulation results confirmed that in the case of a DC single pole fault, the plant is able to continue operation without any use of the turbine speed control units even for a restarting failure in the faulty pole. In case of a DC two pole fault, the plant is able to continue operation, being assisted by turbine speed control units when restarting in the faulty poles succeeds. In case of an AC three-line to ground fault near the AC terminal of the converter at the sending or receiving end, the system is able to continue stable operation, being supplemented by the turbine control unit when the faulty section of the AC system is isolated by a main or back-up relaying system

  17. TRACE/FRAPTRAN analysis of Kuosheng (BWR/6) Nuclear Power Plant for the similar Fukushima accident

    International Nuclear Information System (INIS)

    Kuosheng nuclear power plant (NPP) is a BWR/6 type NPP and located on the northern coast of Taiwan. In order to assess Kuosheng NPP’s safety under the similar Fukushima accident conditions, Kuosheng NPP safety analysis TRACE/SNAP/FRAPTRAN models were established in this research. There were three main steps in this study. The first step was the establishment of Kuosheng NPP TRACE/SNAP model. The next step was the transient analysis of Kuosheng NPP TRACE/SNAP model under the similar Fukushima accident or more severe conditions. Besides, in order to confirm the mechanical property and integrity of fuel rods, the third step was FRAPTRAN analysis. Finally, the animation model of Kuosheng NPP was presented by using animation function of SNAP. TRACE and FRAPTRAN results depicted that zirconium-water reaction generated in SBO or SBO + LOCA transient (no water injected case). It may cause a safety issue in fuel rods. However, if the fire water (39 kg/sec) injected to the vessel at 800 sec in SBO + LOCA transient, TRACE and FRAPTRAN results implied that the integrity of fuel rod was kept. (author)

  18. Experiences with monitoring and control of microbiological growth in the standby service water system of a BWR nuclear power plant

    International Nuclear Information System (INIS)

    In 1989, the Unites States Nuclear Regulatory Commission formally recognized the potential for nuclear accidents resulting from microbiological causes. Such causes range from loss of heat transfer due to microbiological fouling, to loss of system integrity caused by microbiologically influenced corrosion (MIC). As a result of these potential problems, monitoring, mitigation, and control procedures must be developed by all regulated plants. In developing a control and mitigation strategy for the standby service water system of a boiling water reactor (BWR) nuclear power plant, numerous monitoring techniques were employed to evaluate effectiveness. This paper describes the monitoring techniques that were evaluated, and those that ultimately proved to be effective

  19. Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde

    International Nuclear Information System (INIS)

    In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

  20. Real time simulation of the main steam system of a BWR nuclear power station

    International Nuclear Information System (INIS)

    This paper presents a real time model of the main steam system for a BWR 675 MW power plant unit. The model includes the start up and shut down of the system, where the steam flow is very small or non existent and phenomena like condensation can occur, changing drastically the effects observed from those of normal operation at medium or high loads. Severe transients are also contemplated. Consistency and stability tests were done to the model, and it was validated for steady state using plant design data. During transients the model's results were compared with the predictions of the Final Safety Analysis Report (FSAR) for the prototype unit, and it was found that the model's response follow the expected trends

  1. BWR type nuclear reactor

    International Nuclear Information System (INIS)

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

  2. An application of risk-informed evaluation on MOVs and AOVs for Taiwan BWR-type nuclear power plants

    International Nuclear Information System (INIS)

    Implementing a risk-informed inservice testing (RI-IST) program provides a good aspect to the nuclear power plant licensee as an alternating program in the current ASME Section XI and 10 CFR 50.55a relevant testing programs. RI-IST concentrates testing resources on highly significant components, reduces excess testing burden, increases plant's availability, decreases dose rate on the plant's staff and also reduces cost on plant's operation and maintenance under nuclear safety expectations. Furthermore, RI-IST also gives a feature on prospective licensing change basis to a nuclear power plant's licensee. This study will focus on safety-related and PRA-molded motor-operated valves (MOVs) and air-operated valves (AOVs) under the inservice testing program in boiling water reactor (BWR)-type nuclear power plant. As MOVs and AOVs have crucial safety functions throughout the nuclear power plant's safety systems, the steady operation and performance of MOVs and AOVs will definitely ensure that the nuclear power plant operates under safety expectations; therefore, this is the key reason to implement risk-informed evaluation for MOVs and AOVs in this study and being able to provide the safety significance classification for MOVs and AOVs under the current IST program to the plant's management. As a pilot study of RI-IST, the methodology of qualitative assessment will incorporate with probabilistic risk assessment (PRA) analyzing MOVs' and AOVs' safety significance within the current PRA model. The evaluating result will then classify its safety significance into a high-safety significant component (HSSC) and a low-safety significant component (LSSC) for MOVs and AOVs based on relevant regulatory criteria. With this initiating achievement, it can provide a cornerstone for further studies on the other types of valves and pumps in RI-IST program and also provide a valuable reference as proposing license change to the licensee

  3. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Redding, J.R. [GE Nuclear Energy, San Jose, CA (United States)

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  4. Decontamination techniques for BWR power generation plant

    International Nuclear Information System (INIS)

    The present report describes various techniques used for decontamination in BWR power generation plants. Objectives and requirements for decontamination in BWR power plants are first discussed focusing on reduction in dose, prevention of spread of contamination, cleaning of work environments, exposure of equipment parts for inspection, re-use of decontaminated resources, and standards for decontamination. Then, the report outlines major physical, chemical and electrochemical decontamination techniques generally used in BWR power generation plants. The physical techniques include suction of deposits in tanks, jet cleaning, particle blast cleaning, ultrasonic cleaning, coating with special paints, and flushing cleaning. The chemical decontamination techniques include the use of organic acids etc. for dissolution of oxidized surface layers and treatment of secondary wastes such as liquids released from primary decontamination processes. Other techniques are used for removal of penetrated contaminants, and soft and hard cladding in and on equipment and piping that are in direct contact with radioactive materials used in nuclear power generation plants. (N.K.)

  5. Near-term improvements for nuclear power plant control room annunciator systems. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Rankin, W.L.; Duvernoy, E.G.; Ames, K.R.; Morgenstern, M.H.; Eckenrode, R.J.

    1983-04-01

    This report sets forth a basic design philosophy with its associated functional criteria and design principles for present-day, hard-wired annunciator systems in the control rooms of nuclear power plants. It also presents a variety of annunciator design features that are either necessary for or useful to the implementation of the design philosophy. The information contained in this report is synthesized from an extensive literature review, from inspection and analysis of control room annunciator systems in the nuclear industry and in related industries, and from discussions with a variety of individuals who are knowledgeable about annunciator systems, nuclear plant control rooms, or both. This information should help licensees and license applicants in improving their hard-wired, control room annunciator systems as outlined by NUREG-0700.

  6. MELCOR/SNAP analysis of Chinshan (BWR/4) Nuclear Power Plant spent fuel pool for the similar Fukushima accident

    International Nuclear Information System (INIS)

    Chinshan nuclear power plant (NPP), a BWR/4 plant, is the first NPP in Taiwan. After Fukushima NPP event occurred, there is more concern for the safety of NPPs in Taiwan. Therefore, in order to estimate the safety of Chinshan NPP spent fuel pool, by using MELCOR 2.1 and SNAP 2.2.7 codes, INER (Institute of Nuclear Energy Research, Atomic Energy Council, R.O.C.) performed the safety analysis of Chinshan NPP spent fuel pool (SFP). There were two main steps in this research. The first step was the establishment of Chinshan NPP SFP MELCOR/SNAP model. And the transient analysis under the SFP cooling system failure condition was performed. Besides, in order to study the detailed thermal-hydraulic performance of this transient, TRACE was used in this analysis. CFD data from INER report was used to compare with the results of MELCOR and TRACE. The next step was the fuel rod performance analysis by using FRAPTRAN and TRACE's results. Besides, the animation model of Chinshan NPP SFP was presented using the animation function of SNAP with MELCOR analysis results. (author)

  7. Development of a dynamic model of a BWR nuclear power plant

    International Nuclear Information System (INIS)

    A description is given of a one-dimensional steady-state model of a high-pressure steam turbine, a low-pressure steam turbine, a moisture separator, a reheater, a condenser, feedwater heaters and feedwater pump for a nuclear power plant. The model is contained in the program ''TURBPLANT''. The dynamic part of this model is presented in part II of this report. (author)

  8. Development of electrical cable penetration for secondary containment vessel of BWR type nuclear power plants

    International Nuclear Information System (INIS)

    The penetration holes in the walls and floors of the secondary containment vessel of the nuclear power plants must be air-tight, shielded against the radiation, and fire-resistant. At present, the penetration holes are air-tightened with iron plates and sealing material after the cables are laid. However, installation of a number of cables and its sealing work now pose a serious problem in nuclear power plant construction in relation to the installation of reactor system components. The authors have recently developed a method for electric wall penetration in an attempt to solve this problem. This method is provided with prefabricated cable portions for wall penetration, reducing field work, saving labor in wiring work through use of multicore cables, and increasing the reliability of the sealing and caulking work. This wall penetration consists of an iron sleeves to be embedded into the wall, a header-plate, and an assembly of modules in which a specified number of insulated conductors are set up, and furthermore termination boxes are installed on both ends of the penetration holes. This paper deals with the design standard and construction of the wall penetration and the results of tests which were performed under various environmental conditions, which has shown excellent properties, such as sealing quality and electric characteristics, of the wall penetration. (author)

  9. Assessment and management of ageing of major nuclear power plant components important to safety: Metal components of BWR containment systems

    International Nuclear Information System (INIS)

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must therefore be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed toward technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific

  10. Abundance and distribution of radionuclides discharged from a BWR nuclear power station into a marine bay

    International Nuclear Information System (INIS)

    This article summarizes a portion of one of a series of radiological surveillance studies conducted by the U.S. Environmental Protection Agency (EPA) at nuclear power stations. Radionuclide concentrations were measured in Barnegat Bay at the New Jersey shore during EPA's 2-year radiological surveillance study at the Oyster Creek Nuclear Generating Station. The station discharges batches of radioactive liquid waste into effluent condenser cooling water, which flows through Oyster Creek into Barnegat Bay 3 km from the point of discharge. The bay is long, narrow, and shallow, with few passages to the Atlantic Ocean. Radionuclide concentrations were measured repeatedly in water, sediment, marine vegetation, fish, clams, and crabs at various sampling points. Measured values were compared to calculated values based on bioaccumulation factors, and both sets were used to compute dose equivalent rates to the most exposed persons in the environment. The two observed critical radiation exposure pathways - fish consumption and standing on beaches - resulted in dose equivalents of less than 1 mrem/year; the critical radionucides were 90Sr and 60Co, respectively. Indicator radionuclides were identified, and environmental radiological monitoring activities were recommended

  11. Manage I and C obsolescence for GE BWR nuclear power plant life extension

    International Nuclear Information System (INIS)

    Most nuclear power plants in operation were built in the 1970's and 1980's. Parts obsolescence for instrumentation and controls (I and C) has been a continued issue for these plants. Although modern I and C could benefit a nuclear plant in terms of improved reliability, reduced maintenance, and reduced plant vulnerability, I and C upgrades are not common for nuclear plants. This is because the current economic model is such that the assessed benefits for I and C upgrades, especially for the safety related applications, seldom exceeds the modifications cost. Generally, there is no capacity loss associated with I and C problems. The plant staff is usually talented and resourceful enough to maintain the existing system. Any upgrade involving safety related instruments require extensive reviews by the regulatory body, e.g., the Nuclear Regulatory Commission. Cost/benefit analysis that focuses on the immediate pay back and discounts potential long term impact could not justify the cost of I and C upgrade. Consequently, I and C upgrade has been conducted more from a as-needed basis as opposed to being based on a strategic plan. The planning of the I and C upgrades to support plant life extension should be executed in a systematic approach. Six Sigma tools, such as Quality Function Deployment (QFD), can be used to help prioritize I and C upgrades for coming years. An example of employing such a tool would be to first list the criteria or goals for upgrades. This is also termed 'Critical to Quality (CTQ)'. The CTQ should be developed based on inputs from plant staff including engineering, maintenance, and operations. Where applicable, quality assurance, outage management, and plant strategic planning staff should be included. Examples of CTQs are: (a) reliability, (b) ease of maintenance, (c) ease of operation, (d) outage impact, (e) long tem viability, (f) ALARA, and (g) ability to support plant operation (e.g. EPU). The CTQs are then weighted based on the consensus of

  12. BWR manual control and status monitoring system for nuclear power plant

    International Nuclear Information System (INIS)

    As the unit capacity of nuclear power plants increases, the reduction of cost for construction and the improvement of operation availability have been strongly desired. The control and monitoring system with all solid-state equipments, in which the number of cables is greatly reduced by employing series transmission system as signal transmission, has been developed. The new system consists of the control rod drive control system and the control rod monitoring system. The former is composed of the control rod selector module, the control rod drive control panel, distributor module and the transponder. The latter comprises the position sensing probe, the control rod position information panel, whole core display, four control rods display and display memory module. The system operates in 3 modes of time-sharing control, scan, and automatic test. Compared with conventional systems, the new system is improved in three points. (1) The number of cables has been reduced to about 45% of that of conventional system, (2) system availability has been improved by adopting duplex circuits and on-line automatic test function, and (3) dimensions of the control panel has been reduced to about 35% of that of conventional system. In the control rod drive control system, failure diagnosing system is provided, which indicates the diagnosed results or failure positions on a plasma display by utilizing a micro-computer, and almost eliminates the necessity of searching failure positions in the complicated interior of equipments. (Wakatsuki, Y.)

  13. Study of environmental noise in a BWR plant like the Nuclear Power Plant Laguna Verde; Estudio de ruido ambiental en una planta BWR como la Central Nuclear Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Cruz G, M.; Amador C, C., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Cardel-Nautla Km. 42.5, Alto Lucero, Veracruz (Mexico)

    2013-10-15

    In all industry type the health costs generated by the noise are high, because the noise can cause nuisance and to harm the capacity to work when causing tension and to perturb the concentration, and in more severe cases to reach to lose the sense of the hearing in the long term. The noise levels in the industry have been designated for the different types of use like residential, commercial, and industrial and silence areas. The noise can cause accidents when obstructing the communications and alarm signs. For this reason the noise should be controlled and mitigated, at a low level as reasonably is possible, taking into account that the noise is an acoustic contamination. The present study determines a bases line of the environmental noise levels in a nuclear power plant BWR-5 as Laguna Verde, (like reference) to be able to determine and to give pursuit to the possible solutions to eliminate or to limit the noise level in the different job areas. The noise levels were registered with a meter of integrative noise level (sonometer) and areas of noise exposure levels mapping the general areas in the buildings were established, being the registered maximum level of 96.94 dba in the building of the Reactor-elevation 0.65 m under the operation conditions of Extended Power Up rate (EPU) of 120% PTN. Knowing that the exposition to noises and the noise dose in the job place can influence in the health and in the safety of the workers, are extensive topics that they should be analyzed for separate as they are: to) the effects in the health of the exposure to the noise, b) how measuring the noise, c) the methods and technologies to combat and to control the noise in the industry by part of engineering area and d) the function of the industrial safety bodies as delegates of the health and safety in the task against the noise in the job. (author)

  14. Nuclear transmutation characteristics of reduced moderation BWR (Thesis)

    International Nuclear Information System (INIS)

    In the present thesis, the nuclear transmutation characteristics of reduced moderation BWR, which decides the spent fuel characteristics and its safety in its nuclear fuel cycle, were investigated and compared with other types of reactors. The major conclusions were obtained as follows: The decay heat and radioactivity from FPs increases in fuel burn-up. However, they which normalized with burn-up are small for the reactor with low specific power and long operation period due to the decay during the long operation period. Breeder type of reduced moderation BWR shows low decay heat and radioactivity from FPs because of the long operation period approximately 3000 days which realized by the high conversion ratio. That also shows low decay heat and radioactivity from actinide nuclides due to the hard spectrum. MA recycling reactor of high conversion type of reduced moderation BWR was designed. The neptunium, which has large impact for environmental burden from the viewpoint of nuclide transport analysis, can be incinerated approximately 40% of loaded inventory which corresponds to 22 units of LWR per year. LLFP (99Tc, 129I, 135Cs) transmutation by breeder type of reduced moderation BWR was estimated. As a result, the support factor cannot be lower than unity for each LLFP nuclides. In other words, the reduced moderation BWR cannot reduce LLFP because the LLFP target cannot be loaded inner of the reactor core due to the small margin of core specification. It is expected that these results and the characteristics of other types of reactor shown in the present study benefit the discussion for various nuclear fuel cycle options. (author)

  15. GARLIC-B. A digital code for real-time calculation of the transient behaviour of nodal and global core and plant parameters of BWR nuclear power plants

    International Nuclear Information System (INIS)

    A program description of the code GARLIC-B is given. The code is based on a nonlinear transient model for BWR nuclear power plants which consist of a 3D-core, a top plenum, steam removal and feed water systems and a downcomer with main coolant recirculation pumps. The core is subdivided into a number of superboxes and flow channels with different coolant mass flow rates. Subcooled boiling within these channels has an important reactivity feed back effect and has to be taken also into account. The code computes the local and global core and plant transient situation as dependent on both the inherent core dynamics and external control actions, i.e., disturbances such as motions of control rod banks, changes of mass flow rates of coolant, feed water and steam outlet. The case of a pressure-controlled reactor operation is also considered. (orig./GL)

  16. Organizational analysis and safety for utilities with nuclear power plants: perspectives for organizational assessment. Volume 2. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Osborn, R.N.; Olson, J.; Sommers, P.E.; McLaughlin, S.D.; Jackson, M.S.; Nadel, M.V.; Scott, W.G.; Connor, P.E.; Kerwin, N.; Kennedy, J.K. Jr.

    1983-08-01

    This two-volume report presents the results of initial research on the feasibility of applying organizational factors in nuclear power plant (NPP) safety assessment. Volume 1 of this report contains an overview of the literature, a discussion of available safety indicators, and a series of recommendations for more systematically incorporating organizational analysis into investigations of nuclear power plant safety. The six chapters of this volume discuss the major elements in our general approach to safety in the nuclear industry. The chapters include information on organizational design and safety; organizational governance; utility environment and safety related outcomes; assessments by selected federal agencies; review of data sources in the nuclear power industry; and existing safety indicators.

  17. BWR type nuclear power plant and operation method therefor and method of forming oxide membrane on the surface of the constitutional member in contact with water

    International Nuclear Information System (INIS)

    In a BWR type nuclear power plant, an oxide membrane is formed on the surface of the constitutional members of a reactor primary system to be in contact with water while keeping the reactor water at a pH of 7.5 or less based on a room temperature and keeping a temperature of reactor water at 250degC or higher for 250 hours or more and then adding alkaline water to control the pH within a range of from 7.5 to 9.0 based on the room temperature and keeping the reactor water temperature to 250degC or higher for 100 hours or more. This process is conducted during the reactor shut down state and during the operation period from the time of the reactor shut down state to the time of the rated power operation state of the electric power generator. Then, a corrosion resistant oxide membrane with less involvement of radioactive ions can be formed, thereby enabling to improve corrosion resistance of nuclear fuel elements and suppressing the dose rate on the surface of pipelines of a primary coolant system, accordingly, operator's radiation dose rate can be reduced upon periodical inspection. (N.H.)

  18. Qualification of the TH-3DNK coupled code RELAP5/PARCSV2.7 against a BWR unstable point at peach bottom nuclear power plant

    International Nuclear Information System (INIS)

    In this work, three dimensional time domain BWR stability analysis were performed on a new analysis point (PTUPV), which is inside the exclusion region with a core mass flow of 4660.1 kg/s (34% of the core rated mass flow) and total reactor power of 1997.8 MW (60.7 of the core rated reactor power), using the coupled code RELAP5-MOD3.3/PARCSv2.7. This point is achieved departing from test point 3 by the control rod movement as it is usual performed in Nuclear Power Plants. The transient starts with the control rod movement shown. The control rods move in 6 seconds; at the end of the movement the majority of the banks are completely withdrawn and only the bank 7 is almost completely inserted. The purpose of this study is to qualify this coupled code against this kind of 3D complex accidents that take place inside the core. With the aim to make a more careful analysis of the instability recognized in the RELAP5/PARCS simulation, using the nuclear cross-sections provided by the transient calculation performed with the coupled codes, a number of analyses with the nodal modal code VALKIN has also been carried out.

  19. Development of BWR ex-core nuclear instrumentation system. Experimental verification of ex-core local power monitoring method by using neutron streaming pipes

    International Nuclear Information System (INIS)

    We study an ex-core nuclear instrumentation system for a next generation Boiling Water Reactor (BWR). For an example of existing BWRs, in an Advanced BWR (ABWR), about 210 in-core sensors are installed. About sixty penetrations of Reactor Pressure Vessel (RPV) are built for these signal cables. The core monitoring with ex-core sensors instead of in-core sensors reduces the RPV penetrations and extends the sensor life. To achieve this, we created a local power monitoring method with Neutron Streaming Pipes (NSPs), where local power is directly determined from ex-core neutrons through NSPs inserted into the core. In the previous work, applicability of this method for the ABWR was analytically shown. The most critical parameter in this evaluation was the ex-core neutron flux through the NSP. Hence, we experimentally verified validity of the previous analytical values of the flux in a research reactor, Toshiba Nuclear Critical Assembly. The verification was performed in two respects. Firstly, fundamental characteristics of the ex-core neutron flux through a NSP that do not depend on the reactor types were confirmed by measuring ex-core neutron count rates. (1) The ex-core neutron flux φ does not depend on the NSP wall thickness, when the thickness is on the order of millimeters (the measured values: independent within experimental error of 3.0% at 1 σ). (2) The ex-core neutron streaming rate (= φ x the inner cross-sectional area of the NSP) is proportional to the fourth power of the NSP inner diameter (the measured values: the 3.7 and 3.8 power). Secondly, reliability of the neutron streaming calculation was verified by comparing two independent calculations of a number of the incident ex-core neutrons at the detector. One was a neutron streaming calculation with in-core gold foil activation method. The other was a detector response calculation with measured ex-core neutron count rates. They were in good agreement within experimental and analytical error of 7.8% at

  20. Validation of LANCR01/AETNA01 BWR code package against FUBILA MOX experiments and Fukushima Daiichi Nuclear Power Plant Unit 3 MOX core

    International Nuclear Information System (INIS)

    LANCR01 assembly code and AETNA01 core simulator are the advanced BWR package developed by Global Nuclear Fuel (GNF). In order to establish the applicability of the package to the plutonium containing mixed oxide (MOX) fuel, validation tests have been conducted against BASALA, FUBILA MOX critical experiments and the operational data from Fukushima Daiichi Nuclear Power Plant Unit 3 (1F3) with MOX assemblies loaded at cycle 25. For BASALA and FUBILA, critical eigenvalue and the pin-by-pin fission rate distribution by LANCR01 were compared with the experimental data. For 1F3, AETNA01 predictions with LANCR01 assembly cross sections were compared with the measured control blade worth and the moderator temperature coefficient in the reactor physics tests, as well as the cold/hot eigenvalues and the in-core instrument readings during the operation. It is concluded that LANCR01/AETNA01 system has a comparable accuracy for the MOX cores with that for the uranium cores. (author)

  1. Study and characterization of noble metal deposits on similar rusty surfaces to those of the reactor U-1 type BWR of nuclear power station of Laguna Verde

    International Nuclear Information System (INIS)

    In the present investigation work, were determined the parameters to simulate the conditions of internal oxidation reactor circulation pipes of the nuclear power plant of Laguna Verde in Veracruz. We used 304l stainless steel cylinders with two faces prepared with abrasive paper of No. 600, with the finality to obtain similar surface to the internal circulation piping nuclear reactor. Oxides was formed within an autoclave (Autoclave MEX-02 unit B), which is a device that simulates the working conditions of the nuclear reactor, but without radiation generated by the fission reaction within the reactor. The oxidation conditions were a temperature of 280 C and pressure of 8 MPa, similar conditions to the reactor operating in nuclear power plant of Laguna Verde in Veracruz, Mexico (BWR conditions), with an average conductivity of 4.58 ms / cm and 2352 ppb oxygen to simulate normal water chemistry NWC. Were obtained deposits of noble metal oxides formed on 304l stainless steel samples, in a 250 ml autoclave at a temperature range of 180 to 200 C. The elements that were used to deposit platinum-rhodium (Pt-Rh) with aqueous Na2Pt (OH)6 and Na3Rh (NO2)6, Silver (Ag) with an aqueous solution of AgNO3, zirconium (Zr) with aqueous Zr O (NO3) and ZrO2, and zinc (Zn) in aqueous solution of Zn (NO3)2 under conditions of normal water chemistry. Also there was the oxidation of 304l stainless steel specimens in normal water chemistry with a solution of Zinc (Zn) (NWC + Zn). Oxidation of the specimens in water chemistry with a solution of zinc (Zn + NWC) was prepared in two ways: within the MEX-02 autoclave unit A in a solution of zinc and a flask at constant temperature in zinc solution. The oxides formed and deposits were characterized by scanning electron microscopy, energy dispersive X-ray analysis, elemental field analysis and X-ray diffraction. By other hand was evaluated the electrochemical behavior of the oxides formed on the surface of 304l stainless steel in normal water

  2. Procedures for using expert judgment to estimate human-error probabilities in nuclear power plant operations. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Seaver, D.A.; Stillwell, W.G.

    1983-03-01

    This report describes and evaluates several procedures for using expert judgment to estimate human-error probabilities (HEPs) in nuclear power plant operations. These HEPs are currently needed for several purposes, particularly for probabilistic risk assessments. Data do not exist for estimating these HEPs, so expert judgment can provide these estimates in a timely manner. Five judgmental procedures are described here: paired comparisons, ranking and rating, direct numerical estimation, indirect numerical estimation and multiattribute utility measurement. These procedures are evaluated in terms of several criteria: quality of judgments, difficulty of data collection, empirical support, acceptability, theoretical justification, and data processing. Situational constraints such as the number of experts available, the number of HEPs to be estimated, the time available, the location of the experts, and the resources available are discussed in regard to their implications for selecting a procedure for use.

  3. Nuclear Power in Sweden

    International Nuclear Information System (INIS)

    This book presents how Swedish technology has combined competence in planning, building, commissioning, maintenance, and operation of nuclear power and waste facilities. The items are elaborated in the following chapters: Nuclear power today and for the future, Sweden and its power supply, The history of nuclear power in Sweden, Nuclear Sweden today, Operating experience in 10 nuclear power units, Maintenance experience, Third-generation BWR-plants commissioned in five years, Personnel and training, Reactor safety, Quality assurance and quality control, Characteristic features of the ASEA-ATOM BWR, Experience of PWR steam generators, Nuclear fuel supply and management, Policy and techniques of radioactive waste management, Nuclear energy authorities and Inherently safe LWR. The publication is concluded by facts in brief and a statement by the Director General of IAEA. (G.B.)

  4. Control method for BWR type power plant

    International Nuclear Information System (INIS)

    The present invention provides a method of controlling a BWR type plant having internal pumps capable of sufficiently utilizing the performance of a whole volume turbine bypass plant to enable stable supply of electric power upon load interruption of power generator thereof. Namely, upon occurrence of load interruption of a power generator or turbine trip, a plurality of internal pumps are tripped simultaneously to abruptly reduce a reactor core flow rate by a predetermined value or more. In this case, a reactor core flow rate abruptly reduction scram signal is prevented. Alternatively, a plurality of internal pumps are tripped simultaneously to abruptly reduce the reactor core flow rate. In this case, a reactor core flow rate abrupt reduction scram set value is changed in order to inhibit the reactor core flow rate abrupt reduction scram signal. With such procedures, upon load interruption of power generator or upon trip of turbine, reactor core flow rate is abruptly reduced by trip of internal pumps for avoiding increase of neutron fluxes due to reactor pressure change. However, since reactor scram is avoided, the operation can be continued upon load interruption of power generator. As a result, performance of whole volume turbine bypass plant can be utilized sufficiently even upon occurrence of load interruption of power generator. (I.S.)

  5. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR

    International Nuclear Information System (INIS)

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  6. Inspection findings in austenitic RPV internals of German BWR plants and BWRs built in other countries and resulting measures for Isar 1 nuclear power station

    International Nuclear Information System (INIS)

    As visual examinations carried out in autumn 1994 detected cracks in a German BWR plant due to intergranular stress corrosion cracking (IGSCC) in several core shroud components manufactured from 1.4550 steel, precautionary examinations and assessments were performed for all other plants. In accordance with these analyses, it can be stated for Isar 1 that the heat treatment to which the components in question were subjected in the course of manufacture cannot have caused sensitization of the material, and that crack formation due to the damage mechanism primarily identified in the reactor vessel internals at Wuergassen Nuclear Power Station need not be feared. Although the material and corrosion-chemical assessments performed to date did not give any indications for the other crack formation mechanisms that are theoretically relevant for reactor vessel internals (IGSCC due to weld sensitization, IASCC (irradiation assisted stress corrosion cracking)), visual examinations with a limited scope will be carried out with the independant expert's agreement during the scheduled inservice inspections. The fluid-dynamic and structure-mechanical analyses showed that the individual components are subjected only to low loadings, even in the event of accidents, and that the safety objectives shutdown and residual heat removal can be fulfilled even in the case of large postulated cracks. The fracture-mechanics analyses indicated critical through-wall crack lengths which, however, can be promptly and reliably detected during random inservice inspections even when assuming stress corrosion cracking and irradiation-induced low-toughness material conditions. In addition, both the VGB and the Isar 1 plant are pursuing further prophylactic measures such as alternative water chemistry modes and an appropriate repair and replacement concept. (orig.)

  7. Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessel internals

    International Nuclear Information System (INIS)

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and ware out of components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of heavy water moderated reactors (HWRs), boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

  8. Assessment and management of ageing of major nuclear power plant components important to safety: BWR pressure vessels

    International Nuclear Information System (INIS)

    At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of the major NPP components (caused for instance by unanticipated phenomena and by operating, maintenance or manufacturing errors) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. Since the reports are written from a safety perspective, they do not address life or life cycle management of plant components, which involves economic considerations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), and water moderated, water cooled energy reactors (WWERs) are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues

  9. Reliability improvement method for BWR power plants

    International Nuclear Information System (INIS)

    The construction of the nuclear power generating facilities in Japan was commenced by the import of technological know-how from the United States, but in ten years since then, they reached the stage of improvement and standardization by the effort for the domestic production and the accumulated technological ability. But the unscheduled stop of operation was not able to avoid centering around the initially imported plants, and it cannot be said that the sufficient rate of operation was attained. In Japan, plant manufacturers deliver the whole installations including nuclear reactors in the lump, and carry out the planning, design, manufacture, construction, periodic inspection and maintenance, accordingly the feedback of the operational results can be made quickly, differing from the U.S. system. As the result, No. 1 plant of the Shimane Nuclear Power Station, Chugoku Electric Power Co., Inc., which was constructed by the domestic technology, has attained about 72% of the average rate of operation in six years, and showed the high reliability of the domestically produced plants. The measures for improving system reliability in system planning and the reliability of machinery and equipments, the method of evaluating the reliability of systems, machines and equipments, the quality of nuclear power generating facilities and the quality assurance, and the management of maintenance in Hitachi Ltd. are explained. (Kako, I.)

  10. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Executive summary: main report. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    Information is presented concerning the objectives and organization of the reactor safety study; the basic concepts of risk; the nature of nuclear power plant accidents; risk assessment methodology; reactor accident risk; and comparison of nuclear risks to other societal risks.

  11. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendices VII, VIII, IX, and X. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    Information is presented concerning the release of radioactivity in reactor accidents; physical processes in reactor meltdown accidents; safety design rationale for nuclear power plants; and design adequacy.

  12. A BWR power plant simulator for Barsebaeck

    International Nuclear Information System (INIS)

    A computer simulator of a Barsebaeck power plant unit has been developed in cooperation between Sydkraft AB, Lund Institute of Technology, and Risoe National Laboratory. The simulator is of the kind often referred to as a compact simulator, because it involves only a computer with display screens and other input/output devices plus the software needed for calculation and presentation of the plant state as a function of time, and no sort of model of the control room as in large reactor simulators for operator training. The purpose of training courses with the compact simulator is to give students a better understanding of the behaviour of the power plant under transient conditions by displaying variables, e.g. pressures, temperatures, reactivity, nuclear power, as functions of time, thereby showing the interactions between different parts of the plant during the transient and the influence of a number of possible operator actions. The present paper describes the Barsebaeck compact simulator with the emphasis on the software developed at Risoe National Laboratory. The Risoe work comprises the programming of the dynamic plant model, in the form of a number of Fortran subroutines containing the physical description of the power plant. (author)

  13. Effect of bundle size on BWR fuel bundle critical power performance

    International Nuclear Information System (INIS)

    Effect of the bundle size on the BWR fuel bundle critical power performance was studied. For this purpose, critical power tests were conducted with both 6 x 6 (36 heater rods) and 12 x 12 (144 heater rods) size bundles in the GE ATLAS heat transfer test facility located in San Jose, California. All the bundle geometries such as rod diameter, rod pitch and rod space design are the same except size of flow channel. Two types of critical power tests were performed. One is the critical power test with uniform local peaking pattern for direct comparison of the small and large bundle critical power. Other is the critical power test for lattice positions in the bundle. In this test, power of a group of four rods (2 x 2 array) in a lattice region was peaked higher to probe the critical power of that lattice position in the bundle. In addition, the test data were compared to the COBRAG calculations. COBRAG is a detailed subchannel analysis code for BWR fuel bundle developed by GE Nuclear Energy. Based on these comparisons the subchannel model was refined to accurately predict the data obtained in this test program, thus validating the code capability of handling the effects of bundle size on bundle critical power for use in the study of the thermal hydraulic performance of the future advance BWR fuel bundle design. The author describes the experimental portion of the study program

  14. Coupled BWR calculations with the numerical nuclear reactor software system

    International Nuclear Information System (INIS)

    The Numerical Nuclear Reactor (NNR) is a software suite for integrated high-fidelity reactor core simulations including neutronic and thermal-hydraulic feedback. Using solution modules with formulations to reflect the multi-dimensional nature of the system, NNR offers a comprehensive core modeling capability with pin-by-pin representation of fuel assemblies and coolant channels. Originally developed for pressurized water reactors, the NNR analysis capabilities have recently been extended for boiling water reactor (BWR) applications as part of EPRI Fuel Reliability Program. The neutronics methodology is extended to treat non-periodic structure of BWR fuel assemblies, and a new Eulerian two-phase CFD boiling heat transfer model has been integrated with the software system. This paper summarizes the experience with, and results of, the first-of-a-kind coupled calculations as demonstration of a fully-integrated, high-fidelity simulation capability for assessment of margin to crud-induced failure from fuel-duty perspective. (authors)

  15. Investigation of the load change behaviour of PWR- and BWR fuel rods at positive power ramps

    International Nuclear Information System (INIS)

    The following irradiation experiments have been performed to determine the operational behaviour of fuel rods in LWR during power ramps: a) power ramp experiment in the nuclear power plant of Obrigheim (KWO) with 6 PWR test fuel rods at a burnup of about 14 MWd/kgU. No fuel rod defects have been found. b) preirradiation of 45 segmented fuel rods in KWO and of 8 segmented fuel rods in the reactor of Wuergassen; the preirradiated segments will be ramped at HFR Petten. c) power ramp experiments at HBWR with 8 BWR test fuel rods at burnups of 4-14 MWd/kgU; ramping caused no defects. (orig.)

  16. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR; Analisis de la evolucion microestructural del dano por irradiacion neutronica en la vasija de presion de un reactor nuclear de potencia BWR

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y R, M.

    2012-07-01

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  17. Determination of BWR Spent Nuclear Fuel Assembly Effective Thermal Conductivity

    International Nuclear Information System (INIS)

    The purpose of this calculation is to provide an effective thermal conductivity for use in predicting peak cladding temperatures in boiling water reactor (BWR) fuel assemblies with 7x7,8x8, and 9x9 rod arrays. The first objective of this calculation is to describe the development and application of a finite element representation that predicts peak spent nuclear fuel temperatures for BWR assemblies. The second objective is to use the discrete representation to develop a basis for determining an effective thermal conductivity (described later) for a BWR assembly with srneared/homogeneous properties and to investigate the thermal behavior of a spent fuel assembly. The scope of this calculation is limited to a steady-state two-dimensional representation of the waste package interior region. This calculation is subject to procedure AP-3.124, Calculations (Ref. 27) and guided by the applicable technical work plan (Ref. 14). While these evaluations were originally developed for the thermal analysis of conceptual waste package designs emplaced in the potential repository at Yucca Mountain, the methodology applies to storage and transportation thermal analyses as well. Note that the waste package sketch in Attachment V depicts a preliminary design, and should not be interpreted otherwise

  18. Determination of BWR Spent Nuclear Fuel Assembly Effective Thermal Conductivity

    Energy Technology Data Exchange (ETDEWEB)

    Matthew D. Hinds

    2001-10-17

    The purpose of this calculation is to provide an effective thermal conductivity for use in predicting peak cladding temperatures in boiling water reactor (BWR) fuel assemblies with 7x7,8x8, and 9x9 rod arrays. The first objective of this calculation is to describe the development and application of a finite element representation that predicts peak spent nuclear fuel temperatures for BWR assemblies. The second objective is to use the discrete representation to develop a basis for determining an effective thermal conductivity (described later) for a BWR assembly with srneared/homogeneous properties and to investigate the thermal behavior of a spent fuel assembly. The scope of this calculation is limited to a steady-state two-dimensional representation of the waste package interior region. This calculation is subject to procedure AP-3.124, Calculations (Ref. 27) and guided by the applicable technical work plan (Ref. 14). While these evaluations were originally developed for the thermal analysis of conceptual waste package designs emplaced in the potential repository at Yucca Mountain, the methodology applies to storage and transportation thermal analyses as well. Note that the waste package sketch in Attachment V depicts a preliminary design, and should not be interpreted otherwise.

  19. BWR 90: The ABB advanced BWR design

    International Nuclear Information System (INIS)

    ABB has two evolutionary advanced fight water reactors available today - the BWR 90 boiling water reactor and the System 80+ pressurised water reactor. The BWR 90 is based on the design, construction, commissioning and operation of the BWR 75 plants. The operation experience of the six plants of this advanced design has been very good. The average annual energy availability is above 90%, and the total power generation costs have been low. In the development of BWR 90 specific changes were introduced to the reference design, to adapt to technological progress, new safety requirements and to achieve cost savings. The thermal power rating of BWR 90 is 3800 MWth (providing a nominal 1374 MWe net), slightly higher dim that of the reference plant ABB Atom has taken advantage of margins gained using a new generation of its SVEA fuel to attain this power rating without major design modifications. The BWR 90 design was completed and offered to the TVO utility in Finland in 1991, as one of the contenders for the fifth Finnish nuclear power plant project. Thus, the design is available today for deployment in new plant projects. Utility views were incorporated through co-operation with the Finnish utility TVO, owner and operator of the two Olkiluoto plants of BWR 75 design. A review against the European Utility Requirement (EUR) set of requirements has been performed, since the design, in 1997, was selected by the EUR Steering Committee to be the first BWR to be evaluated against the EUR documents. The work is scheduled for completion in 1998. It will be the subject of an 'EUR Volume 3 Subset for BWR 90' document. ABB is continuing its BWR development work with the 'evolutionary' design BWR 90+. The primary design goal is to develop the BWR as a competitive option for the anticipated revival of the market for new nuclear plants beyond the turn of the century, as well as feeding ideas and inputs to the continuous modernisation efforts at operating plants. The development is

  20. Nuclear power

    International Nuclear Information System (INIS)

    The subject is covered in chapters entitled: nuclear power certainties and doubts; nuclear power in the Western World to 2000; the frequency of core meltdown accidents; hidden costs of the accident at Three Mile Island; costs of nuclear accidents - implications for reactor choice; defining the risks of nuclear power; the uncertain economics of a nuclear power program; the economics of enabling decisions (Sizewell B as an enabling decision); trade in nuclear electricity; some pointers to the future. (U.K.)

  1. Low power level safety management of Finnish BWR

    International Nuclear Information System (INIS)

    Good practices in work coordination and safety management have contributed to short refueling outage duration in Finnish BWR plants. Human and organizational factors are considered especially important in the low paper states, which consist of start-up, shut-down and the outage period itself. This originates from the use of external labour during the outage, the number of both contemporary and sequentially linked human actions and the variety of potential ways the personnel can affect the plant state. While the containment barrier does not exist, more organizational and administrative means have to be used in risk management. To promote the safety further, special studies have been carried out. This paper discusses both the low power mode PSA and the studies of work orientation and competence among the operating staff in Olkiluoto BWR plant. An advanced outage control requires also open-minded consideration of potential risks and the means for their reduction. Good results in low power risk management can be reached only by the involvement of both the plant operating and the maintenance staff. A profound safety management is a prerequisite for safe low power states. (author)

  2. Nuclear power

    OpenAIRE

    Waller, David; McDonald, Alan; Greenwald, Judith; Mobbs, Paul

    2005-01-01

    David Waller and Alan McDonald ask whether a nuclear renaissance can be predicted; Judith M. Greenwald discusses keeping the nuclear power option open; Paul Mobbs considers the availability of uranium and the future of nuclear energy.

  3. Nuclear power

    International Nuclear Information System (INIS)

    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

  4. Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendices III and IV. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1975-10-01

    The items listed below summarize the detail sections which follow: a listing of definitions and a discussion of the general treatment of data within the random variable approach as utilized by the study; a tabulation of the assessed data base containing failure classifications, final assessed ranges utilized in quantification and reference source values considered in determining the ranges; a discussion of nuclear power plant experience that was used to validate the data assessment by testing its applicability as well as to check on the adequacy of the model to incorporate typical real incidents; an expanded presentation of the data assessment giving information on applicability considerations; a discussion of test and maintenance data including comparisons of models with experience data; and special topics, including assessments required for the initiating event probabilities and human error data and modeling.

  5. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR

    International Nuclear Information System (INIS)

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  6. Fuel gases generation in the primary contention during a coolant loss accident in a nuclear power plant with reactor type BWR

    International Nuclear Information System (INIS)

    During an accident design base of coolant loos, the hydrogen gas can accumulate inside the primary contention as a result of several generation mechanisms among those that are: 1) the reaction metal-water involving the zirconium of the fuel cladding and the reactor coolant, 2) the metals corrosion for the solutions used in the emergency cooling and dew of the contention, and 3) the radio-decomposition of the cooling solutions of post-accident emergency. In this work the contribution of each generation mechanism to the hydrogen total in the primary contention is analyzed, considering typical inventories of zirconium, zinc, aluminum and fission products in balance cycle of a reactor type BWR. In the analysis the distribution model of fission products and hydrogen production proposed in the regulator guide 1.7, Rev. 2 of the US NRC was used. The results indicate that the mechanism that more contributes to the hydrogen generation at the end of a period of 24 hours of initiate the accident is the radio-decomposition of the cooling solutions of post-accident emergency continued by the reaction metal-water involving the zirconium of the fuel cladding with the reactor coolant, and lastly the aluminum and zinc oxidation present in the primary contention. However, the reaction metal-water involving the zirconium of the fuel cladding and the reactor coolant is the mechanism that more contributes to the hydrogen generation in the first moments after the accident. This study constitutes the first part of the general analysis of the generation, transport and control of fuel gases in the primary contention during a coolant loss accident in BWRs. (Author)

  7. Nuclear power

    International Nuclear Information System (INIS)

    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. Design and axial optimization of nuclear fuel for BWR reactors

    International Nuclear Information System (INIS)

    In the present thesis, the modifications made to the axial optimization system based on Tabu Search (BT) for the axial design of BWR fuel type are presented, developed previously in the Nuclear Engineering Group of the UNAM Engineering Faculty. With the modifications what is mainly looked is to consider the particular characteristics of the mechanical design of the GE12 fuel type, used at the moment in the Laguna Verde Nucleo electric Central (CNLV) and that it considers the fuel bars of partial longitude. The information obtained in this thesis will allow to plan nuclear fuel reloads with the best conditions to operate in a certain cycle guaranteeing a better yield and use in the fuel burnt, additionally people in charge in the reload planning will be favored with the changes carried out to the system for the design and axial optimization of nuclear fuel, which facilitate their handling and it reduces their execution time. This thesis this developed in five chapters that are understood in the following way in general: Chapter 1: It approaches the basic concepts of the nuclear energy, it describes the physical and chemical composition of the atoms as well as that of the uranium isotopes, the handling of the uranium isotope by means of the nuclear fission until arriving to the operation of the nuclear reactors. Chapter 2: The nuclear fuel cycle is described, the methods for its extraction, its conversion and its enrichment to arrive to the stages of the nuclear fuel management used in the reactors are described. Beginning by the radial design, the axial design and the core design of the nuclear reactor related with the fuel assemblies design. Chapter 3: the optimization methods of nuclear fuel previously used are exposed among those that are: the genetic algorithms method, the search methods based on heuristic rules and the application of the tabu search method, which was used for the development of this thesis. Chapter 4: In this part the used methodology to the

  9. Nuclear power

    International Nuclear Information System (INIS)

    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

  10. Experimental evaluation of an operator decision aid system for BWR power plants

    International Nuclear Information System (INIS)

    An experiment was carried out to evaluate the effectiveness of an integrated operator decision aid (IODA) system for boiling water reactor (BWR) power plants. The IODA was developed to enhance the operating safety, reliability and quality of plants. It assists an operator's monitoring and diagnostic capabilities under adverse plant situations using computers and color CRT display devices. Three functions - a standby systems management system (SSMS), a disturbance analysis system (DAS), and a post-trip operational guidance (PTOG) system - have been developed as aids corresponding to the operator's various roles in the safe operation of a nuclear power plant. These functions were designed with full consideration of the operator's problem-solving process, and they have been integrated into a comprehensive IODA system for abnormal BWR power plant conditions. To ensure the applicability of the test results to real-life situations, emphasis was placed on establishing realistic test conditions - including a fully equipped experimental control room, a full-scope plant simulator, participation of experienced operating crews, and well-designed test transient scenarios. Experimental data were collected by means of computers and audio-visual devices, and were processed and summarized to facilitate analysis. Qualitative analysis of the test results was performed with emphasis on the decision-making process of an operator. The analysis points to the utility of the IODA as an operator aid, especially in diagnosing adverse plant situations and in formulating strategies for countermeasures. (orig.)

  11. Investigation of control rod worth and nuclear end of life of BWR control rods

    Energy Technology Data Exchange (ETDEWEB)

    Magnusson, Per

    2008-01-15

    This work has investigated the Control Rod Worth (CRW) and Nuclear End of Life (NEOL) values for BWR control rods. A study of how different parameters affect NEOL was performed with the transport code PHOENIX4. It was found that NEOL, expressed in terms of {sup 10}B depletion, can be generalized beyond the conditions for which the rod is depleted, such as different power densities and void fractions, the corresponding variation in the NEOL will be about 0.2-0.4% {sup 10}B. It was also found that NEOL results for different fuel types and different fuel enrichments have a variation of about 2-3% in {sup 10}B depletion. A comparative study on NHOL and CRW was made between PHOENIX4 and the stochastic Monte Carlo code MCNP. It was found that there is a significant difference, both due to differences in the codes and to limitations in the geometrical modeling in PHOENIX4. Since MCNP is considered more physically correct, a methodology was developed to calculate the nuclear end of life of BWR control rods with MCNP. The advantages of the methodology are that it does not require other codes to perform the depletion of the absorber material, it can describe control rods of any design and it can deplete the control rod absorber material without burning the fuel. The disadvantage of the method is that is it time-consuming.

  12. Investigation of control rod worth and nuclear end of life of BWR control rods

    International Nuclear Information System (INIS)

    This work has investigated the Control Rod Worth (CRW) and Nuclear End of Life (NEOL) values for BWR control rods. A study of how different parameters affect NEOL was performed with the transport code PHOENIX4. It was found that NEOL, expressed in terms of 10B depletion, can be generalized beyond the conditions for which the rod is depleted, such as different power densities and void fractions, the corresponding variation in the NEOL will be about 0.2-0.4% 10B. It was also found that NEOL results for different fuel types and different fuel enrichments have a variation of about 2-3% in 10B depletion. A comparative study on NHOL and CRW was made between PHOENIX4 and the stochastic Monte Carlo code MCNP. It was found that there is a significant difference, both due to differences in the codes and to limitations in the geometrical modeling in PHOENIX4. Since MCNP is considered more physically correct, a methodology was developed to calculate the nuclear end of life of BWR control rods with MCNP. The advantages of the methodology are that it does not require other codes to perform the depletion of the absorber material, it can describe control rods of any design and it can deplete the control rod absorber material without burning the fuel. The disadvantage of the method is that is it time-consuming

  13. Design and axial optimization of nuclear fuel for BWR reactors; Diseno y optimizacion axial de combustible nuclear para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A

    2006-07-01

    In the present thesis, the modifications made to the axial optimization system based on Tabu Search (BT) for the axial design of BWR fuel type are presented, developed previously in the Nuclear Engineering Group of the UNAM Engineering Faculty. With the modifications what is mainly looked is to consider the particular characteristics of the mechanical design of the GE12 fuel type, used at the moment in the Laguna Verde Nucleo electric Central (CNLV) and that it considers the fuel bars of partial longitude. The information obtained in this thesis will allow to plan nuclear fuel reloads with the best conditions to operate in a certain cycle guaranteeing a better yield and use in the fuel burnt, additionally people in charge in the reload planning will be favored with the changes carried out to the system for the design and axial optimization of nuclear fuel, which facilitate their handling and it reduces their execution time. This thesis this developed in five chapters that are understood in the following way in general: Chapter 1: It approaches the basic concepts of the nuclear energy, it describes the physical and chemical composition of the atoms as well as that of the uranium isotopes, the handling of the uranium isotope by means of the nuclear fission until arriving to the operation of the nuclear reactors. Chapter 2: The nuclear fuel cycle is described, the methods for its extraction, its conversion and its enrichment to arrive to the stages of the nuclear fuel management used in the reactors are described. Beginning by the radial design, the axial design and the core design of the nuclear reactor related with the fuel assemblies design. Chapter 3: the optimization methods of nuclear fuel previously used are exposed among those that are: the genetic algorithms method, the search methods based on heuristic rules and the application of the tabu search method, which was used for the development of this thesis. Chapter 4: In this part the used methodology to the

  14. Nuclear power

    International Nuclear Information System (INIS)

    Nuclear power has been seen as an answer to the energy problems of the Third World and Third World markets have been seen as an answer to the problems of the nuclear power industry. For some years during the 1970s both views seemed tenable. This paper examines the progress and setbacks of nuclear power in developing countries. In concentrates mainly on the four countries with real nuclear power commitments (as opposed to all-but-abandoned ambitions) - South Korea and Taiwan, where the interest has been mainly in obtaining cheaper and reliable electricity supplies, and Argentina and India, where the main interest has been in developing indigenous nuclear technological capabilities. A number of possibilities are examined which could influence future nuclear ordering, including smaller reactors to suit Third World electricity grids and a possible way round the constraint of large external debts. (author)

  15. Manufacturing industry and nuclear power

    International Nuclear Information System (INIS)

    The manufacturing industry and nuclear power is discussed at two levels. There is the supplier level where the problems tend to be orthodox but take on a special peculiarity when applied to the nuclear market, and there is the level that may be termed nuclear politics and which has a number of aspects including energy policy, choice of reactor system, efficient uses of industrial resources and public acceptability. The role of the supplier is seen as searching for new orders, having secured an order performing the contract, and finally looking at the long term requirements of the industry. The choice of thermal reactor system, PWR, AGR, or BWR is discussed. (author)

  16. Fuel design with low peak of local power for BWR reactors with increased nominal power

    International Nuclear Information System (INIS)

    The Federal Commission of Electricity recently announcement the beginning of the works related with the increase of the power to 120% of the original nominal one in the Boiling Water Reactors (BWR) of the Laguna Verde Central (CLV): In the National Institute of Nuclear Research (ININ) are carried out studies of the impact on the design of the recharge of derived fuel of this increase. One of the main effects of the power increase type that it is promoting, is the increment of the flow of generated vapor, what takes, to a bigger fraction of vacuum in the core presenting increased values of the maximum fraction to the limit, so much of the ratio of lineal heat generation (XFLPD) as of the ratio of critic power (MFLCPR). In the made studies, it is found that these fractions rise lineally with the increase of the nominal power. Considering that the reactors of the CLV at the moment operate to 105% of the original nominal power, it would imply an increment of the order of 13.35% in the XFLPD and in the MFLCPR operating to a nominal power of 120% of the original one. This would propitiate bigger problems to design appropriately the fuel cycle and the necessity, almost unavoidable, of to resort to a fuel assembly type more advanced for the recharges of the cores. As option, in the ININ the feasibility of continuing using the same type of it fuel assembles that one has come using recently in the CLV, the type GE12 is analyzed. To achieve it was outlined to diminish the peak factor of local power (LPPF) of the power cells that compose the fuel recharge in 13.35%. It was started of a fuel design previously used in the recharge of the unit 1 cycle 12 and it was re-design to use it in the recharge design of the cycle 13 of the unit 1, considering an increase to 120% of the original power and the same requirements of cycle extension. For the re-design of the fuel assembly cell it was used the PreDiCeldas computer program developed in the ININ. It was able to diminish the LPPF

  17. Development of neural network simulating power distribution of a BWR fuel bundle

    International Nuclear Information System (INIS)

    A neural network model is developed to simulate the precise nuclear physics analysis program code for quick scoping survey calculations. The relation between enrichment and local power distribution of BWR fuel bundles was learned using two layers neural network (ENET). A new model is to introduce burnable neutron absorber (Gadolinia), added to several fuel rods to decrease initial reactivity of fresh bundle. The 2nd stages three layers neural network (GNET) is added on the 1st stage network ENET. GNET studies the local distribution difference caused by Gadolinia. Using this method, it becomes possible to survey of the gradients of sigmoid functions and back propagation constants with reasonable time. Using 99 learning patterns of zero burnup, good error convergence curve is obtained after many trials. This neural network model is able to simulate no learned cases fairly as well as the learned cases. Computer time of this neural network model is about 100 times faster than a precise analysis model. (author)

  18. Nuclear power

    International Nuclear Information System (INIS)

    After three decades of commercial development, nuclear power has failed to fulfil its promise. Why, and what does that failure imply for the future of energy policy? One reason for nuclear power's slow growth is that rich countries have repeatedly found they needed less electricity than they had forecast. Part of the problem is, as it always has been, public unease. Worries about safety affect costs. They make it harder and more time-consuming to find sites for new plants or for storing waste. Complex safety devices mean complex plants, which are more expensive to build (and to relicense when they grow old). The true cost of nuclear power is hard to calculate. However nuclear power now seems to be less economically favourable when compared with its main rival, coal. The only hope for nuclear power is that, apart from hydropower, it is the only commercial alternative to fossil fuels. Concerns over carbon dioxide emissions may tip the balance in nuclear's favour. (Author)

  19. Development of neural network for analysis of local power distributions in BWR fuel bundles

    International Nuclear Information System (INIS)

    A neural network model has been developed to learn the local power distributions in a BWR fuel bundle. A two layers neural network with total 128 elements is used for this model. The neural network learns 33 cases of local power peaking factors of fuel rods with given enrichment distribution as the teacher signals, which were calculated by a fuel bundle nuclear analysis code based on precise physical models. This neural network model studied well the teacher signals within 1 % error. It is also able to calculate the local power distributions within several % error for the different enrichment distributions from the teacher signals when the average enrichment is close to 2 %. This neural network is simple and the computing speed of this model is 300 times faster than that of the precise nuclear analysis code. This model was applied to survey the enrichment distribution to meet a target local power distribution in a fuel bundle, and the enrichment distribution with flat power shape are obtained within short computing time. (author)

  20. Pool swell in a nuclear containment wetwell. [BWR

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, T.

    1976-04-01

    A brief description is presented of scale model tests conducted to study LOCA induced wetwell pool swelling in the BWR Mk 1 containment pressure suppression system. The Mk 1 containment configuration is described together with the scale model design, the conduct of the tests, and the experimental results. (DG)

  1. BWR 90 and BWR 90+: Two advanced BWR design generations from ABB

    International Nuclear Information System (INIS)

    ABB has two evolutionary advanced light water reactors available today - the BWR 90 boiling water reactor and the System 80+ pressurised water reactor. The BWR 90 is based on the design, construction, commissioning and operation of the BWR 75 plants. The operation experience of the six plants of this advanced design has been very good. The average annual energy availability is above 90%, and total power generation costs have been low. When developing the BWR 90 specific changes were introduced to a reference design, to adapt to technological progress, new safety requirements and to achieve cost savings. The thermal power rating of BWR 90 is 3800 MWth (providing a nominal 1374 MWe net), slightly higher than that of the reference plant ABB Atom has taken advantage of margins gained using a new generation of its SVEA fuel to attain this power rating without major design modifications. The BWR 90 design was completed and offered to the TVO utility in Finland in 1991, as one of the contenders for the fifth Finnish nuclear power plant project. Hence, the design is available today for deployment in new plant projects. Utility views were incorporated through co-operation with the Finnish utility TVO, owner and operator of the two Olkiluoto plants of BWR 75 design. A review against the European Utility Requirement (EUR) set of requirements has been performed, since the design, in 1997, was selected by the EUR Steering Committee to be the first BWR to be evaluated against the EUR documents. The review work was completed in 1998. It will be the subject of an 'EUR Volume 3 Subset for BWR 90' document. ABB is continuing its BWR development work with an 'evolutionary' design called BWR 90+, which aims at developing the BWR as a competitive option for the anticipated revival of the market for new nuclear plants beyond the turn of the century, as well as feeding ideas and inputs to the continuous modernisation efforts at operating plants. The development is performed by ABB Atom

  2. Development of advanced BWR

    International Nuclear Information System (INIS)

    The Japanese technology and domestic production of BWR type nuclear power plants have been established through the experiences in the construction and operation of BWRs in addition to the technical agreement with the General Electric Co. In early days, the plants experienced some trouble such as stress corrosion cracking and some inconvenience in the operation and maintenance. The government, electric power companies and BWR manufacturers have endeavored to standardize and improve the design of LWRs for the purpose of improving the safety, reliability and the rate of operation and reducing the radiation exposure dose of plant workers. The first and second stages of the standardization and improvement of LWRs have been completed. Five manufacturers of BWRs in the world have continued the conceptual design of a new version of BWR power plants. It was concluded that this is the most desirable version of BWR nuclear power stations, but the technical and economic evaluation must be made before the commercial application. Six electric power companies and three manufacturers of BWRs in Japan set up the organization to develop the technology in cooperation. The internal pump system, the new control rod drive mechanism and others are the main features. (Kako, I.)

  3. The synergies of PLiM, PLEX, and power uprates: Lessons learned from recent BWR experience

    International Nuclear Information System (INIS)

    Full text: Increasing electricity demand due to population growth and redistribution, high oil and gas prices, concerns for greenhouse gas emissions, and a positive trend in public opinion and government support for nuclear power provide tremendous opportunity for growth in the nuclear industry throughout the world. This can be accomplished in two ways, (1) new plants can be built and (2) the performance of existing plants can be improved through increased reliability and increased in generation capacity known as power uprates. In addition, the operating and design life of existing units can be extended for twenty or even forty years through plant life extension (PLEX). However. these uprates and life extensions are only viable if the plant reliability and capacity factor gains made in recent years continue through the extended operating domainlperiod. A growing number of US and international BWR's have successfully improved economic viability while increasing generation within existing facilities through implementation of uprates and PLEX efforts. The evolution of these efforts is the transition to a synergistic approach of plant modernization (including digital I and C upgrades), Life Cycle Management (LCM), margin recapture, and reliability improvement included in the overall plan with power uprates and PLEX. As the experience base with these programs grows suppliers, like GE, and utilities continue to build on the experience of prior projects, improve project execution, and maximize the investment returns. This paper will present the results of several recent GE BWR projects in the US that have implemented combined efforts of reliability management programs with strategic projects such as power uprates. The paper will focus on the lessons learned froin these efforts to help plants prepare for planning and implementing their own integrated reliability programs. Specific areas to be discussed include project initiation and scoping, project planning, project team

  4. BWR Spent Nuclear Fuel Interfacial Bonding Efficiency Study

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jiang, Hao [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-30

    The objective of this project is to perform a systematic study of spent nuclear fuel (SNF, also known as “used nuclear fuel” [UNF]) integrity under simulated transportation environments using the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL) in August 2013. Under Nuclear Regulatory Commission (NRC) sponsorship, ORNL completed four benchmark tests, four static tests, and twelve dynamic or cycle tests on H. B. Robinson (HBR) high burn-up (HBU) fuel. The clad of the HBR fuels was made of Zircaloy-4. Testing was continued in fiscal year (FY) 2014 using Department of Energy (DOE) funds. Additional CIRFT testing was conducted on three HBR rods; two specimens failed, and one specimen was tested to over 2.23 × 107 cycles without failing. The data analysis on all the HBR SNF rods demonstrated that it is necessary to characterize the fatigue life of the SNF rods in terms of (1) the curvature amplitude and (2) the maximum absolute of curvature extremes. The maximum extremes are significant because they signify the maximum tensile stress for the outer fiber of the bending rod. CIRFT testing has also addressed a large variation in hydrogen content on the HBR rods. While the load amplitude is the dominant factor that controls the fatigue life of bending rods, the hydrogen content also has an important effect on the lifetime attained at each load range tested. In FY 15, eleven SNF rod segments from the Limerick BWR were tested using the ORNL CIRFT equipment; one test under static conditions and ten tests under dynamic loading conditions. Under static unidirectional loading, a moment of 85 N·m was obtained at a maximum curvature of 4.0 m-1. The specimen did not show any sign of failure during three repeated loading cycles to a similar maximum curvature. Ten cyclic tests were conducted with amplitudes varying from 15.2 to 7.1 N·m. Failure was observed in nine of

  5. Analysis of a BWR direct cycle forced circulation power plants operation

    International Nuclear Information System (INIS)

    First, it is established a general view over the operational problems of the BWR direct cycle forced circulation power plants, and then it is analysed the possibility of the utilization of the energy purged from the turbine as an additional energy for the electrical generation. To simulate the BWR power plant and to obtain the solution of the mathematical model it was developed a computer code named ATOR which shows the feasibility of the proposed method. In this way it is shown the possibility to get a better maneuvering allowance for the BWR power plant whenever it is permitted a convenient use of the vapor extracted from the turbine for the feedwater pre-heaters of the reactor. (author)

  6. Alpha-nuclides in nuclear power plants

    International Nuclear Information System (INIS)

    The behaviour of alpha-nuclides in nuclear power plants is subject of the investigations presented. The source of alpha-nuclides is a contamination with fissile material (so called tramp uranium or tramp fuel) which deposits on fuel rod surfaces and leads to the build-up of transuranium nuclides. The determination of a defect situation with fuel release as well as the quantification of the fissile material contamination background is given for BWR and PWR plants. The quantification of the fuel release and the tramp uranium background can be calculated with different, measurable nuclides in BWR and PWR plants. (orig.)

  7. 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.

  8. MOX fuel use in a BWR with extended power up-rate

    International Nuclear Information System (INIS)

    Highlights: ► Use of MOX fuel is assessed for a BWR under a extended power uprate (EPU). ► EPU conditions reduce the maximum amount of MOX fuel to be loaded. ► The use of MOX fuel affects mainly the core neutronics and not to the thermal hydraulics. ► Start up of an equilibrium mixed UO2–MOX core under EPU does not present stability problems. -- Abstract: Although MOX fuel coming from reprocessed depleted uranium fuels has been used as a recycling strategy by countries like France and Japan it is not a common policy in the 30 countries that uses nuclear power, nowadays it seems to be a more direct alternative to reduce the depleted fuel interim storage. Previously, the spent fuel pools of Laguna Verde Nuclear Power plant were redesigned to host the total operating life depleted fuel under its original nominal power condition, however the plant has been up-rated to 120% of its original nominal power increasing the number of depleted fuel forecasted. This new situation makes necessary the analysis of alternatives, being one of them recycling. The current paper assesses the viability of using MOX fuel in the up-rated Power Plant; the design of the boiling water reactor MOX fuel addresses the two main constraints of its use: shutdown margin and reactor stability. Fuel design proposed sets the appropriate MOX enrichment and the maximum MOX fuel batch reload that does not imply any modification to the reactor control systems to avoid an extra economical cost due to its use.

  9. Data list of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    The PPD (Nuclear Power Plant Data Base) has been under development in JAERI since 1983 as a six-year program to provide useful information for reactor safety regulation and reactor safety research. Information source of the PPD is mainly based on SAR's (Safety Analysis Reports) of 35 nuclear power plants which are operating, under construction or under licensing review in Japan. The report BWR edition consists of several data lists stored in the PPD, concerning safety design such as performances, equipments and installations of 18 BWR plants in Japan. The informations are based on SAR Attachment Chapter 8 ''Nuclear Reactor Facility Safety Design''. (author)

  10. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR; BUTREN-RC un sistema hibrido para la optimizacion de recargas de combustible nuclear en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J.; Castillo M, J.A. [ININ, Carretera Mexico-Toluca Km. 36.5, 52045 Estado de Mexico (Mexico); Valle G, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  11. Nuclear power data 2016

    International Nuclear Information System (INIS)

    The brochure on nuclear power data 2016 covers the following topics: (I) nuclear power in Germany: nuclear power plants in Germany; shut-down and decommissioned nuclear power plants, gross electricity generation, primary energy consumption; (II) nuclear power worldwide: nuclear electricity production, nuclear power plants.

  12. Results of the benchmarking in radiological protection practices during fuel reloads in the nuclear power plants of Limerick (BWR) and Ginna (PWR) in the United States of North America

    International Nuclear Information System (INIS)

    The nuclear power plant of Laguna Verde, unique in our country, has been imposed several goals related with the continuous improvement of their acting; increase in the quantity of continuous days for operation cycle, improvement in the chemical indexes of the reactor coolant, improvement in the indexes of nuclear security, improvement in the indicators of industrial security, improvement in the standards of radiological protection, etc.; in this last item is precisely where is necessary to search creative solutions to be able to maintain the collective doses of the personnel so low as reasonably it is possible (ALARA) especially due to the last projects of extension of useful life of the nuclear power plant (zinc injection, noble metals and hydrogen) and of power increment of the nuclear power plant of Laguna Verde, same that represent in the short period an increment of collective dose and of exposition levels (until 200%) in very specific points of the primary systems of the reactor. (Author)

  13. Pumps for nuclear power stations

    International Nuclear Information System (INIS)

    16 nuclear power plants are in commercial operation in Japan, and nuclear power generation holds the most important position among various substitute energies. Hereafter also, it is expected that the construction of nuclear power stations will continue because other advantageous energy sources are not found. In this paper, the outline of the pumps used for BWR plants is described. Nuclear power stations tend to be large scale to reduce the construction cost per unit power output, therefore the pumps used are those of large capacity. The conditions to be taken in consideration are high temperature, high pressure, radioactive fluids, high reliability, hydrodynamic performances, aseismatic design, relevant laws and regulations, and quality assurance. Pumps are used for reactor recirculation system, control rod driving hydraulic system, boric acid solution injecting system, reactor coolant purifying system, fuel pool cooling and purifying system, residual heat removing system, low pressure and high pressure core spraying systems, and reactor isolation cooling system, for condensate, feed water, drain and circulating water systems of turbines, for fresh water, sea water, make-up water and fire fighting services, and for radioactive waste treating system. The problems of the pumps used for nuclear power stations are described, for example, the requirement of high reliability, the measures to radioactivity and the aseismatic design. (Kako, I.)

  14. Aging and service wear of control rod drive mechanisms for BWR nuclear plants

    International Nuclear Information System (INIS)

    This Phase I Nuclear Plant Aging Research (NPAR) study examines the aging phenomena associated with BWR control rod drive mechanisms (CRDMs) and assesses the merits of various methods of ''managing'' this aging. Information for this study was acquired from (1) the results of a special CRDM aging questionnaire distributed to each US BWR utility, (2) a first-of-its-kind workshop held to discuss CRDM aging and maintenance concerns, (3) an analysis of the Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to the control rod drive (CRD) system, and (4) personal information exchange with nuclear industry CRDM maintenance experts. Nearly 23% of the NPRDS CRD system component failure reports were attributed to the CRDM. The CRDM components most often requiring replacement due to normal wear and aging are the Graphiter seals. The predominant causes of aging for these seals are mechanical wear and thermally induced embrittlement More than 59% of the NPRDS CRD system failure reports were attributed to components that comprise the hydraulic control unit (HCU). The predominant HCU components experiencing the effects of service wear and aging are valve seals, discs, seats, stems, packing, and diaphragms. Since CRDM changeout and rebuilding is one of the highest dose, most physically challenging, and complicated maintenance activities routinely accomplished by BWR utilities, this report also highlights recent innovations in CRDM handling equipment and rebuilding tools that have resulted in significant dose reductions to the maintenance crews using them

  15. Design, construction and erection of the biological shield wall for the Caorso nuclear power station

    International Nuclear Information System (INIS)

    This article describes the major aspects of the design, construction and erection of the biological shield wall encircling the reactor pressure vessel of the Caorso nuclear power station (Italy) (BWR-Mark 2, 840MWe)

  16. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    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

  17. Data list of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    The development of the database called PPD (Nuclear Power Plant Database) has started in 1983 at JAERI as a six-year program to provide useful information for reactor safety regulation and reactor safety research. In 1988 the program has been accomplished, and since then the data in the database has been updating and adding. Information source of the PPD is based on SAR's (Safety Analysis Report) of 47 nuclear power plants which are operating, under construction or under licensing review in Japan. The report, BWR edition, consists of lists of major data stored in the PPD, relating to safety design of 25 BWR plants in Japan. (author)

  18. Flex concept for US-A BWR extended loss of AC power events

    International Nuclear Information System (INIS)

    The US-Advanced Boiling Water Reactor (US-A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (Stp 3 and 4) Combined License Application (Cola) and incorporates numerous design and technology enhancements for improved safety performance. Nuclear Innovation North America (NINA) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The Stp 3 and 4 project has finished the US NRC technical review of the Cola, and the final safety evaluation report (FSER) is scheduled to be issued by the US NRC in 2015. Following the accident at the Fukushima Dai-ichi plant, the US-A BWR was reviewed for Beyond Design Basis Event (BDBE) safety using industry and regulatory guidance for US NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation of Beyond Design Basis External Events (BDBEE). By virtue of the design approach, the US-A BWR is capable of providing an indefinite coping period for a station blackout. The use of installed systems with extended coping times is a significant advantage of the US-A BWR compared to most of the plants currently operating in the U.S. In addition, the Stp 3 and 4 design incorporates enhancements consistent with the current US industry Diverse and Flexible Coping Strategies (Flex) initiative. The final technical topic requiring review by the US NRC Advisory Committee on Reactor Safeguards was the Flex Integrated Plan submitted by NINA, and this review was successfully completed. This paper summarizes the progress of the US-A BWR in licensing the Flex Integrated Plan for the project, and describes the technology and features of the US-A BWR design that contribute to safety post-Fukushima. It also provides an informational comparison of the design capabilities of the US-A BWR for extreme external events, and relates these capabilities to re

  19. Flex concept for US-A BWR extended loss of AC power events

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Aoyagi, Y.; Kataoka, K. [Toshiba Corporation, Kawasaki, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (US-A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (Stp 3 and 4) Combined License Application (Cola) and incorporates numerous design and technology enhancements for improved safety performance. Nuclear Innovation North America (NINA) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The Stp 3 and 4 project has finished the US NRC technical review of the Cola, and the final safety evaluation report (FSER) is scheduled to be issued by the US NRC in 2015. Following the accident at the Fukushima Dai-ichi plant, the US-A BWR was reviewed for Beyond Design Basis Event (BDBE) safety using industry and regulatory guidance for US NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation of Beyond Design Basis External Events (BDBEE). By virtue of the design approach, the US-A BWR is capable of providing an indefinite coping period for a station blackout. The use of installed systems with extended coping times is a significant advantage of the US-A BWR compared to most of the plants currently operating in the U.S. In addition, the Stp 3 and 4 design incorporates enhancements consistent with the current US industry Diverse and Flexible Coping Strategies (Flex) initiative. The final technical topic requiring review by the US NRC Advisory Committee on Reactor Safeguards was the Flex Integrated Plan submitted by NINA, and this review was successfully completed. This paper summarizes the progress of the US-A BWR in licensing the Flex Integrated Plan for the project, and describes the technology and features of the US-A BWR design that contribute to safety post-Fukushima. It also provides an informational comparison of the design capabilities of the US-A BWR for extreme external events, and relates these capabilities to re

  20. Nuclear power plants

    International Nuclear Information System (INIS)

    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.)

  1. BWR type nuclear plant and start-up operation method

    International Nuclear Information System (INIS)

    During start-up operation of a reactor, the concentration of dissolved oxygen, hydrogen peroxide or ions in primary coolants is controlled at a low level. In addition, hydrogen is injected to the primary coolants to form a stable oxide membrane on the surface of nuclear elements in contact with water. Further, the flow rate of the primary coolants to be supplied to a reactor clean-up system is determined to not less than 2.1% of the feedwater flow rate during rated power operation, and the flow rate of the reactor clean-up system is controlled so that the electroconductivity of the primary coolants is not more than 0.15μS/cm at the upstream of the clean-up device of the reactor clean-up system. Then, the oxidation rate is suppressed and the concentration of ions in water intaken to the oxide membrane is controlled by decreasing the oxide membrane forming speed on the surface of a zirconium alloy and controlling the concentration of ions in the primary coolants. The ingredients which form a tetragonal or cubic crystal structure if they are involved into the oxide membrane can be incorporated in the primary coolants during start-up operation by the control of the ion concentration. (N.H.)

  2. Reviewing nuclear power station achievement

    International Nuclear Information System (INIS)

    For measurement of nuclear power station achievement against original purchase the usual gross output figures are of little value since the term loosely covers many different definitions. An authentically designed output figure has been established which relates to net design output plus house load at full load. Based on these figures both cumulative and moving annual load factors are measured, the latter measuring the achievement over the last year, thus showing trends with time. Calculations have been carried out for all nuclear stations in the Western World with 150 MW(e) gross design output and above. From these are shown: moving annual load factor indicating relative station achievements for all the plants; cumulative load factors from which return of investment can be calculated; average moving annual load factors for the four types of system Magnox, PWR, HWR, and BWR; and a relative comparison of achievement by country in a few cases. (U.K.)

  3. Development of remote automatic equipment for BWR power plants

    International Nuclear Information System (INIS)

    The development of remote control, automatic equipment for nuclear power stations has been promoted to raise the rate of operation of plants by shortening regular inspection period, to improve the safety and reliability of inspection and maintenance works by mechanization, to reduce the radiation exposure dose of workers and to reduce the manpower required for works. The taking-off of control rod drives from reactors and fixing again have been mechanized, but the disassembling, cleaning, inspection and assembling of control rod drives are manually carried out. Therefore, Hitachi Ltd. has exerted effort to develop the automatic equipment for this purpose. The target of development, investigation, the construction and function of the equipment, the performance and the effect of adopting it are reported. The equipment for the volume reduction of spent fuel channel boxes and spent control rods is developed since these are major high level radioactive solid wastes, and their apparent volume is large. Also the target of development, investigated things, the construction and function of the equipment, the performance and the effect of adopting it are reported. (Kako, I.)

  4. Nuclear power. 2010 world report. Evaluation

    International Nuclear Information System (INIS)

    At the end of 2010, 443 nuclear power plants were available for power supply in 30 countries, 6 plants more than in 2009. Seven units were commissioned for the first time, 1 nuclear power plant was decommissioned for good in 2010. At a cumulated gross power of 396,126 MWe and a cumulated net power of 375,947 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 361 plants. By the end of 2010, in 15 countries 64 nuclear power plants with an aggregate gross power of 65,110 MWe and an aggregate net power of 61,097 MWe were under construction. Of these, 58 are light water reactors, 2 are CANDU-type reactors, 3 are fast breeder and 1 D2O-PWR. 128 commercial reactors with a 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 1980ies and 1990ies. The energy availability and operating availability factors of the nuclear power plants reached good levels: 80.20% for operating availability. Finland with its' four nuclear power plants continues to be in the lead worldwide with a cumulated average operating capacity factor of 91,51%. (orig.)

  5. Operator training simulator for nuclear power plant

    International Nuclear Information System (INIS)

    In nuclear power plants, training of the operators is important. In Japan, presently there are two training centers, one is BWR operation training center at Okuma-cho, Fukushima Prefecture, and another the nuclear power generation training center in Tsuruga City, Fukui Prefecture, where the operators of PWR nuclear power plants are trained. This report describes the BWR operation training center briefly. Operation of a nuclear power plant is divided into three stages of start-up, steady state operation, and shut down. Start-up is divided into the cold-state start-up after the shut down for prolonged period due to periodical inspection or others and the hot-state start-up from stand-by condition after the shut down for a short time. In the cold-state start-up, the correction of reactivity change and the heating-up control to avoid excessive thermal stress to the primary system components are important. The BWR operation training center offers the next three courses, namely beginner's course, retraining course and specific training course. The training period is 12 weeks and the number of trainees is eight/course in the beginner's course. The simulator was manufactured by modeling No. 3 plant of Fukushima First Nuclear Power Station, Tokyo Electric Power Co. The simulator is composed of the mimic central control panel and the digital computer. The software system comprises the monitor to supervise the whole program execution, the logic model simulating the plant interlock system and the dynamic model simulating the plant physical phenomena. (Wakatsuki, Y.)

  6. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    International Nuclear Information System (INIS)

    The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is

  7. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    Energy Technology Data Exchange (ETDEWEB)

    Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mertyurek, Ugur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scaglione, John M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is

  8. Construction and operation of nuclear power plants

    International Nuclear Information System (INIS)

    How does a nuclear power plant work. Which reactor types are in use. What safety measures are being taken. These questions and the like are frequently asked by those interested in nuclear power generation. The respective answers are to be found in the report ''Construction and Operation of Nuclear Power Plants''. Nuclear-physical fundamentals and the basic safety measures are explained, and four reactor types that are most common in the Federal Republic of Germany are described: PWR-, BWR-, HTR-type and faster breeder reactors. For each reactor type, the principle of operation, steam generator system, auxiliary and service buildings as well as the respective safety devices are indicated, and visualized by means of numerous illustrations. The report is meant to be instrumental to the purpose of getting objectiveness into the public discussion on the peaceful use of nuclear energy. (orig.)

  9. Nuclear power economic database

    International Nuclear Information System (INIS)

    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

  10. Effect of void dependent reactivity modeling bias on BWR axial power tilt - 256

    International Nuclear Information System (INIS)

    Inspired by a Pennsylvania State University study reported in the PHYSOR08 conference related to BWR axial power tilt, an investigation is made as to if there could be any intrinsic deficiency in the conventional nodal diffusion theory leading to a tilt in BWR axial power prediction. It is found that the two-group nodal diffusion theory itself does not cause axial power tilt compared to multigroup deterministic 3D transport calculation. However, the usual practice of flat source approximation in 2D lattice codes based on the Collision Probability (CP) method or the Method of Characteristics (MOC) can cause a void dependent reactivity bias when used to generate the node homogenized cross-sections, if the same geometry meshing modeling is used for all the axial sections over which the void fraction varies severely. The reactivity bias can be removed by using lattice code models based on SN method or MOC method with linear instead of flat source approximation. In absence of the void dependent reactivity bias, there is no axial power tilt between two-group nodal diffusion calculation and multi-group deterministic 3D transport calculation. Therefore there is no intrinsic deficiency in the nodal diffusion theory that causes BWR axial power tilt. But one has to be careful with using the flat source approximation and the generic-meshing modeling in generating homogenized nodal diffusion cross-sections for high void cases. As for any possible axial power tilt between multi-group deterministic 3D transport calculation and continuous energy Monte Carlo 3D simulation, that would be a different issue. (authors)

  11. Analysis of the integrity of the pressure vessel of the BWR type nuclear reactor

    International Nuclear Information System (INIS)

    The presssure vessel of a BWR type reactor was monitored for cracking during alternating events of its in-service life. The monitoring was to determine criticality of fractures catastrophic fractures and the velocity of fracture propagation. Detected cracks were evaluated as specified in ASME code section XI, of a minimum wall thickness of 2.5% crack growths were compared a) of 1/10 of the critical maximum size and b) at in-service inspection intervals according to ASME recommendations to be established at the Laguna Verde nuclear plant. Finally conclusions are made and discussed. (author)

  12. Ozone for purification of water in nuclear power stations

    International Nuclear Information System (INIS)

    Visibility problems are uncommon in BWR reactors of the German type but they do occur occasionally. At KRB A nuclear power station, the water in the storage pond became turbid in shutdown conditions, which slowed down the work. The authors describe attempts to solve the problem. Ozone treatment was successful

  13. Nuclear power plant control system

    International Nuclear Information System (INIS)

    Purpose: To effectively transfer the operation of a nuclear power plant including a bwr type reactor to single load operation in the station with no increase in the neutron flux and water level in the reactor by the combined use of recycle pump trip and feedwater pump trip. Method: Upon rapid load decrease in a turbine generator, at least one of usually operated feedwater pumps and a recycle pump are tripped and the starting for a stand-by feedwater pump is inhibited. This rapidly decreases the recycling flow rate to thereby lower the neutron flux before generation of pressure increase and also decreases the feedwater flow rate to thereby suppress the increase in the water level due to increase in voids, whereby the operation is smoothly transferred to the single load operation in the station. (Horiuchi, T.)

  14. Nuclear power - anyone interested

    International Nuclear Information System (INIS)

    The subject is discussed under the following headings, with illustrative strip cartoons: uranium mining (uranium exploration in Orkney); radiation (hazards); nuclear power and employment; transport (of radioactive materials); nuclear reactor safety (reference to the accident to Three Mile Island-2 reactor); energy in the future; sources of energy; nuclear weapons; suggestions for action; insulation and heating buildings; nuclear security; working in a nuclear power station; nuclear waste; the anti-nuclear movement; nuclear power and politics. (U.K.)

  15. HVDC transmission from nuclear power plant

    International Nuclear Information System (INIS)

    The HVDC transmission directly from nuclear power plants is one of the patterns of long distance and large capacity HVDC transmission systems. In this report, the double pole, two-circuit HVDC transmission from a BWR nuclear power plant is considered, and the dynamic response characteristics due to the faults in dc line and ac line of inverter side are analyzed, to clarify the dynamic characteristics of the BWR nuclear power plant and dc system due to system faults and the effects of dc power control to prevent reactor scram. (1) In the instantaneous earthing fault of one dc line, the reactor is not scrammed by start-up within 0.8 sec. (2) When the earthing fault continues, power transmission drops to 75% by suspending the faulty pole, and the reactor is scrammed. (3) In the instantaneous ground fault of 2 dc lines, the reactor is not scrammed if the faulty dc lines are started up within 0.4 sec. (4) In the existing control of dc lines, the reactor is scrammed when the ac voltage at an ac-dc connection point largely drops due to ac failure. (J.P.N.)

  16. Basic evaluation on nuclear characteristics of BWR high burnup MOX fuel and core

    International Nuclear Information System (INIS)

    MOX fuel will be used in existing commercial BWR cores as a part of reload fuels with equivalent operability, safety and economy to UO2 fuel in Japan. The design concept should be compatible with UO2 fuel design. High burnup UO2 fuels are being developed and commercialized step by step. The MOX fuel planned to be introduced in around year 2000 will use the same hardware as UO2 8 x 8 array fuel developed for a second step of UO2 high burnup fuel. The target discharge exposure of this MOX fuel is about 33 GWd/t. And the loading fraction of MOX fuel is approximately one-third in an equilibrium core. On the other hand, it becomes necessary to minimize a number of MOX fuels and plants utilizing MOX fuel, mainly due to the fuel economy, handling cost and inspection cost in site. For the above reasons, it needed to developed a high burnup MOX fuel containing much Pu and a core with a large amount of MOX fuels. The purpose of this study is to evaluate basic nuclear fuel and core characteristics of BWR high burnup MOX fuel with batch average exposure of about 39.5 GWd/t using 9 x 9 array fuel. The loading fraction of MOX fuel in the core is within a range of about 50% to 100%. Also the influence of Pu isotopic composition fluctuations and Pu-241 decay upon nuclear characteristics are studied. (author). 3 refs, 5 figs, 3 tabs

  17. Nuclear coupled flow instability study for natural circulation BWR startup transient

    International Nuclear Information System (INIS)

    Natural circulation Boiling Water Reactor (BWR) startup transient was investigated in Purdue University Multidimensional Test Assembly (PUMA) facility based on a natural circulation BWR design. Strategy and results of the experiments, which consider the effects of void-reactivity and fuel heat conduction time constant, are discussed. Total reactivity is treated to be composed of two components: external reactivity due to control rod motion and void-reactivity. A detailed analysis for heat conduction problem is performed to derive dimensionless groups. Based on area-averaged heat conduction equations for pellet and clad regions, Fourier and Biot numbers are derived to simulate wall heat flux response. Power transient, which has been used for startup transient investigation without void-reactivity feedback is used to derive the control rod reactivity. Twelve conductivity probes are used to measure local void fraction inside core at three axial locations. The local void-fraction data is used to calculate volume average void fraction, which is used to calculate the voil-reactivity. A real-time Point Kinetic Model solver is implemented to PUMA heater power control program to determine power transient during startup. The results demonstrate that the inclusion of void-reactivity feedback worsen the scenario for startup instabilities and may cause large amplitude neutron flux oscillations. (author)

  18. Management of Spent Nuclear Fuel from Nuclear Power Plant Reactor

    International Nuclear Information System (INIS)

    Management of spent nuclear fuel from Nuclear Power Plant (NPP) reactor had been studied to anticipate program of NPP operation in Indonesia. In this paper the quantity of generated spent nuclear fuel (SNF) is predicted based on the national electrical demand, power grade and type of reactor. Data was estimated using Pressurized Water Reactor (PWR) NPP type 1.000 MWe and the SNF management overview base on the experiences of some countries that have NPP. There are four strategy nuclear fuel cycle which can be developed i.e: direct disposal, reprocessing, DUPlC (Direct Use of Spent PWR Fuel In Candu) and wait and see. There are four alternative for SNF management i.e : storage at the reactor building (AR), away from reactor (AFR) using wet centralized storage, dry centralized storage AFR and prepare for reprocessing facility. For the Indonesian case, centralized facility of the wet type is recommended for PWR or BWR spent fuel. (author)

  19. Prediction of the local power factor in BWR fuel cells by means of a multilayer neural network

    International Nuclear Information System (INIS)

    To the beginning of a new operation cycle in a BWR reactor the reactivity of this it increases by means of the introduction of fresh fuel, the one denominated reload fuel. The problem of the definition of the characteristics of this reload fuel represents a combinatory optimization problem that requires significantly a great quantity of CPU time for their determination. This situation has motivated to study the possibility to substitute the Helios code, the one which is used to generate the new cells of the reload fuel parameters, by an artificial neuronal network, with the purpose of predicting the parameters of the fuel reload cell of a BWR reactor. In this work the results of the one training of a multilayer neuronal net that can predict the local power factor (LPPF) in such fuel cells are presented. The prediction of the LPPF is carried out in those condition of beginning of the life of the cell (0.0 MWD/T, to 40% of holes in the one moderator, temperature of 793 K in the fuel and a moderator temperature of 560 K. The cells considered in the present study consist of an arrangement of 10x10 bars, of those which 92 contains U235, some of these bars also contain a concentration of Gd2O3 and 8 of them contain only water. The axial location inside the one assembles of recharge of these cells it is exactly up of the cells that contain natural uranium in the base of the reactor core. The training of the neuronal net is carried out by means of a retro-propagation algorithm that uses a space of training formed starting from previous evaluations of cells by means of the Helios code. They are also presented the results of the application of the neuronal net found for the prediction of the LPPF of some cells used in the real operation of the Unit One of the Laguna Verde Nuclear Power station. (Author)

  20. Nuclear power in Canada

    International Nuclear Information System (INIS)

    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)

  1. Nuclear power and nuclear insurance

    International Nuclear Information System (INIS)

    Fanned by the Chernobyl reactor accident the discussion about the safety and insurability of nuclear power plants has also been affecting the insurance companies. The related analyses of the safety concepts of German nuclear power plants have been confirming the companies' risk philosophy of maintaining the insurability of nuclear power plants either meeting German safety standards or equivalent safety standards. Apart from the technical evaluation of the safety of nuclear power plants the fundamental discussion about the pros and cons of nuclear power has also been stressing the damages and liability problem. The particular relevance of possible considerable transfrontier contaminations clearly reveals the urgency of establishing internationally standardized reactor accident liability regulations. (orig./HP)

  2. U.S. Department Of Energy's nuclear engineering education research: highlights of recent and current research-II. 7. Hybrid Reactor Simulation and 3-D Information Display of BWR Out-of-Phase Oscillation

    International Nuclear Information System (INIS)

    The real-time hybrid reactor simulation (HRS) capability of the Penn State TRIGA reactor has been recently expanded for BWR out-of-phase behavior. Out-of-phase oscillation is a phenomenon that occurs at BWRs. During this kind of event, half of the core can significantly oscillate out of phase with the other half, while the average power reported by the neutronic instrumentation may show a much lower amplitude for the oscillations. The HRS will be used for development and validation of stability monitoring and control techniques as part of an ongoing U.S. Department of Energy Nuclear Engineering Education and Research grant. The Penn State TRIGA reactor is used to simulate BWR fundamental mode power dynamics. The first harmonic mode power, together with detailed thermal hydraulics of boiling channels of both fundamental mode and first harmonic mode, is simulated digitally in real time with a computer. Simulations of boiling channels provide reactivity feedback to the TRIGA reactor, and the TRIGA reactor's power response is in turn fed into the channel simulations and the first harmonic mode power simulation. The combination of reactor power response and the simulated first harmonic power response with spatial distribution functions thus mimics the stability phenomena actually encountered in BWRs. The digital simulations of the boiling channels are performed by solving conservation equations for different regions in the channel with C-MEX S-functions. A fast three-dimensional (3-D) reactor power display of modal BWR power distribution was implemented using MATLAB graphics capability. Fundamental mode, first harmonic, together with the total power distribution over the reactor cross section, are displayed. Because of the large amount of computation for BWR boiling channel simulation and real-time data processing and graph generation, one computer is not sufficient to handle these jobs in the hybrid reactor simulation environment. A new three-computer setup has been

  3. Development of neural network for predicting local power distributions in BWR fuel bundles considering burnable neutron absorber

    International Nuclear Information System (INIS)

    A neural network model is under development to predict the local power distribution in a BWR fuel bundle as a high speed simulator of precise nuclear physical analysis model. The relation between 235U enrichment of fuel rods and local peaking factor (LPF) has been learned using a two-layered neural network model ENET. The training signals used were 33 patterns having considered a line symmetry of a 8x8 assembly lattice including 4 water rods. The ENET model is used in the first stage and a new model GNET which learns the change of LPFs caused by burnable neutron absorber Gadolinia, is added to the ENET in the second stage. Using this two-staged model EGNET, total number of training signals can be decreased to 99. These training signals are for zero-burnup cases. The effect of Gadolinia on LPF has a large nonlinearity and the GNET should have three layers. This combined model of EGNET can predict the training signals within 0.02 of LPF error, and the LPF of a high power rod is predictable within 0.03 error for Gadolinia rod distributions different from the training signals when the number of Gadolinia rods is less than 10. The computing speed of EGNET is more than 100 times faster than that of a precise nuclear analysis model, and EGNET is suitable for scoping survey analysis. (author)

  4. Prospects for Nuclear Power

    OpenAIRE

    Davis, Lucas W.

    2011-01-01

    Nuclear power has long been controversial because of concerns about nuclear accidents, storage of spent fuel, and how the spread of nuclear power might raise risks of the proliferation of nuclear weapons. These concerns are real and important. However, emphasizing these concerns implicitly suggests that unless these issues are taken into account, nuclear power would otherwise be cost effective compared to other forms of electricity generation. This implication is unwarranted. Throughout the h...

  5. Nuclear Power in China

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    China’s vigorous efforts to propel development of nuclear power are paying off as the country’s nuclear power sector advances at an amazing pace. At present, China has set up three enormous nuclear power bases, one each in Qinshan of Zhejiang Province, Dayawan of Guangdong

  6. Nuclear power economics

    International Nuclear Information System (INIS)

    As a petroleum substitute, the nuclear power in Japan possesses the following four features. (1) Stability in supply: The import of nuclear fuel resources is performed from politically stable advanced countries and in long-term contracts. And, nuclear power can be of semi-domestic energy source due to the nuclear fuel cycle. (2) Low cost of nuclear power generation. (3) Contribution of nuclear power technology to other advanced industries. (4) Favorable effects of nuclear power siting upon the region concerned, such as labor employment and social welfare. Electricity charges are high in Japan, as compared with those in the United States and others where coal and water power are relatively abundant. For Japan without such natural resources, nuclear energy is important in lowering the power rates. (Mori, K.)

  7. Nuclear power training programmes in Spain

    International Nuclear Information System (INIS)

    The introduction of nuclear power in Spain is developing very rapidly. At present 1.1GW(e) are installed in Spain and this is expected to increase to 8GW(e) in 1980 and to 28GW(e) in 1990. Spanish industry and technology are also rapidly increasing their participation in building nuclear stations, in manufacturing the necessary components and in the activities related to the nuclear fuel cycle. All of this requires properly trained personnel, which is estimated to become approximately 1200 high-level technicians, 1100 medium-level technicians and 1500 technical assistants by 1980. This personnel is trained: (a) in engineering schools; (b) in the Nuclear Studies Institute; (c) in the electric companies with nuclear programmes. The majority of the high-level engineering schools in the country include physics and basic nuclear technology courses in their programmes. Some of them have an experimental low-power nuclear reactor. The Nuclear Studies Institute is an official organism dependent on the Nuclear Energy Commission and responsible, among other subjects, for training personnel for the peaceful use and development of nuclear energy in the country. The electric companies also participate in training personnel for future nuclear stations and they plan to have advanced simulators of PWR and BWR type stations for operator training. The report deals with the personnel requirement forecasts and describes the training programmes. (author)

  8. Trouble shooting fuel leak at Shika Nuclear Power Station Unit No.2

    International Nuclear Information System (INIS)

    Power Suppression Testing (PST) is recommend for BWR in fuel leak occur. Operation by PST allows to identify leaked fuel bundle, suppresses its power and continue plant operation safely. Shika Nuclear Power Station Unit No.2 (Shika-2) has an experience fuel leak in its 2nd operation cycle, April 2009. This paper describes experience of trouble shooting fuel leak at Shika-2. (author)

  9. Neutron noise analysis techniques in nuclear power reactors

    International Nuclear Information System (INIS)

    The main techniques used in neutron noise analysis of BWR and PWR nuclear reactors are reviewed. Several applications such as control of vibrations in both reactor types, determination of two phase flow parameters in BWR and stability control in BWR are discussed with some detail. The paper contains many experimental results obtained by the main author of this paper. (author)

  10. Nuclear power prospects

    International Nuclear Information System (INIS)

    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

  11. Development of a computer program of fast calculation for the pre design of advanced nuclear fuel 10 x 10 for BWR type reactors

    International Nuclear Information System (INIS)

    In the National Institute of Nuclear Research (ININ) a methodology is developed to optimize the design of cells 10x10 of assemble fuels for reactors of water in boil or BWR. It was proposed a lineal calculation formula based on a coefficients matrix (of the change reason of the relative power due to changes in the enrichment of U-235) for estimate the relative powers by pin of a cell. With this it was developed the computer program of fast calculation named PreDiCeldas. The one which by means of a simple search algorithm allows to minimize the relative power peak maximum of cell or LPPF. This is achieved varying the distribution of U-235 inside the cell, maintaining in turn fixed its average enrichment. The accuracy in the estimation of the relative powers for pin is of the order from 1.9% when comparing it with results of the 'best estimate' HELIOS code. With the PreDiCeldas it was possible, at one minimum time of calculation, to re-design a reference cell diminishing the LPPF, to the beginning of the life, of 1.44 to a value of 1.31. With the cell design with low LPPF is sought to even design cycles but extensive that those reached at the moment in the BWR of the Laguna Verde Central. (Author)

  12. Hydrogen uptake of BWR fuel rods. Power history effects at long irradiation times

    International Nuclear Information System (INIS)

    AREVA LTP (Low Temperature Process) Zircaloy-2 cladding for Boiling Water Reactors (BWR) in both RXA (Recrystallized Annealed) and CWSR (Cold Worked Stress Relieved) metallurgical states, has an optimized microstructure with an optimum size of SPP (Secondary Phase Particles) that has reduced the nodular corrosion to a minimum while maintaining a good uniform corrosion performance with acceptable hydrogen pickup. Classically hydrogen uptake is described by the Hydrogen Pick-Up Fraction (HPUF), which is the ratio of the hydrogen generated by uniform oxidation that is eventually picked up by the metal to the total hydrogen generated by oxidation. In the past, the hydrogen uptake database showed a low HPUF with hydrogen concentration close to the saturation value of the metal at operating temperature and correspondingly little hydride formation. The hydrogen concentration was correlated with irradiation time via the HPUF (at an almost constant corrosion and hydrogen production rate). Recently, some significantly higher hydrogen concentration values (300 wppm and more) have been measured for medium and high burnup rods. This effect was also observed on four AREVA fuel rods from BWR (Boiling Water Reactors). This prompted a thorough analysis of the hydrogen pickup database as well as material and environmental factors influencing corrosion and hydrogen uptake. The most important outcome of the investigation was that a low power – low steam condition is associated with increased hydrogen pickup. The linear power is a proxy variable for low heat flux and low steam quality in the coolant, which were identified as important parameters for physical processes that could explain the enhanced hydrogen uptake in some cases. The paper will present the database of the enhanced hydrogen uptake measured in European power reactors and demonstrate the effect of power history on the uptake process. Power histories with high hydrogen uptake included extended low power periods later in

  13. RETHINKING NUCLEAR POWER SAFETY

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The Fukushima nuclear accident sounds alarm bells in China’s nuclear power industry In the wake of the Fukushima nucleara ccident caused by the earthquake andt sunami in Japan,the safety of nuclearp ower plants and the development of nuclear power have raised concerns,

  14. Energy investment in nuclear power plants

    International Nuclear Information System (INIS)

    The energy investment in terms of electrical and thermal energy requirements for nuclear power plants is examined. The total lifetime energy inputs required for a 1000-MW(e) plant based on a 30-year plant lifetime and 0.75 plant factor are presented for several pressurized-water-reactor (PWR) and boiling-water-reactor (BWR) systems, two high-temperature gas-cooled reactor (HTGR) systems, and one heavy-water-reactor (HWR) system. The energy analyses reviewed here have demonstrated that the energy expenditures for the various reactor systems are very much less than the energy produced by the reactors and that the initial energy investments are recovered in a short time after startup--several months to 2 years. The energy requirements associated with the individual processes, such as mining, enrichment, construction, and waste disposal, are tabulated for two different fuel cycles for a PWR and a BWR. The enriching process is by far the largest component of the electrical requirements, representing 85 to 90% of the total electrical energy investment. The energy used in constructing and operating the reactor constitutes the largest single investment of thermal energy, representing 50% of the total thermal energy requirements. Results of several analyses are examined and comparisons made between nuclear power plants, a coal plant, and a solar thermal-conversion plant

  15. Sustainable development of nuclear power

    International Nuclear Information System (INIS)

    A treatise consisting of the following sections: Economic efficiency of nuclear power (Growth of nuclear power worldwide; State of the art in the development of nuclear power reactors; Competitiveness of contemporary nuclear power); Environmental acceptability of nuclear power (Non-proliferation of nuclear weapons; Nuclear safety and radioactive waste disposal; Environmental awareness and environmental movements). (P.A.)

  16. Stability and vibration analyses of high power BWR using large assembly with small pins

    International Nuclear Information System (INIS)

    The Large Assembly with Small Pins (LASP) is an evolutionary fuel assembly concept to improve BWRs' economic attractiveness by increasing the core power density. It replaces four traditional assemblies with a single 22x22 large assembly. Previously published steady-state and transient analyses show that, when operating under the same power to flow ratio, the LASP core allows for 20% higher power density than the traditional fuel assemblies while maintaining the same dryout margin. In this study, mechanical vibrations and thermal-hydraulics stability analyses of the LASP core are presented. The modified Paidoussis correlation was used to calculate the vibration amplitude ratio to the fuel pin diameter and to the pin-to-pin gap of the LASP fuel and the reference fuel. The vibration ratios of the LASP are found to be higher than those of the reference core, but well below the acceptable limits. It is possible to add two spacers to the LASP assemblies to preserve the vibration ratios of the reference core. Given a more negative void reactivity coefficient than traditional BWR cores, unstable power and flow oscillations are a potential concern. Characteristics of density-wave oscillations in the LASP core and their sensitivity to operating parameters have been investigated with a linear perturbation analysis. Although the decay ratios for the LASP core are higher than those of a reference core, they are well within the traditional limits. Thus, stability is maintained in the LASP core at 20% higher reactor thermal power than the reference core. (author)

  17. Nuclear power development

    Energy Technology Data Exchange (ETDEWEB)

    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.

  18. Nuclear power and safety

    International Nuclear Information System (INIS)

    The paper deals with the problem of necessity to develop nuclear power, conceivable consequences of this development, its disadvantages and advantages. It is shown that the nuclear power is capable of supplying the world's economy with practically unlimited and the most low-cost energy resources providing the transition from the epoch of organic fuel to the epoch with another energy sources. The analysis of various factors of nuclear power effects on population and environment is presented. Special attention is focused on emergency situations at NPPs. The problem of raising the nuclear power safety is considered. 11 refs.; 5 figs.; 2 tabs

  19. Nuclear power debate

    International Nuclear Information System (INIS)

    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

  20. Safety Evalution Report related to the final design approval of the GESSAR II BWR/6 nuclear island design (Docket No. 50-447)

    International Nuclear Information System (INIS)

    This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. The review is carried out in accordance with the procedures for demonstrating the acceptability of the design for the severe-accident concerns described in draft NUREG-1070, NRC Policy on Future Reactor Designs: Decisions on Severe Accident Issues in Nuclear Power Plant Regulation. Supplement 2 also provides more recent information regarding resolution or update of the confirmatory items and FDA-1 conditions identified in SSER 1. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  1. Evaluation of the thermal-mechanical performance of fuel rods of a BWR during a power ramp using the FUELSIM code

    International Nuclear Information System (INIS)

    To avoid the risk to environment due to release of radioactive material, because of occurrence of an accident, it is the priority of the design and performance of the diverse systems of safety of a commercial nuclear power plant. The safety of nuclear power plants requires, therefore, monitoring those parameters having some direct or indirect effect on safety. The thermal limits are values set for those parameters considered having most impact on the safe operation of a nuclear power reactor. Some thermal limits monitoring requires the thermal-mechanical analysis of the rods containing the nuclear fuel. The fuel rod thermal-mechanical behavior under irradiation is a complex process in which there exists a great deal of interrelated physical and chemical phenomena, so that the fuel rod performance analysis in the core of a nuclear power reactor is generally accomplished by using computer codes, which integrate several of the phenomena that are expected to occur during the lifetime of the fuel rod in the core. The main application of the thermal-mechanical analysis codes is the prediction of occurrence of conditions and/or phenomena that could lead to the deterioration or even mechanical failure of the fuel rod cladding, as, for example, the pellet-cladding interaction. In the operation of a nuclear power reactor, fuel preconditioning operations refer to the operational procedures employed to reduce the fuel rod failure probability due to fuel-cladding interaction, specially during reactor startup. Preconditioning simulations are therefore necessary to determine in advance limit values for the power that can be generated in a fuel rod, and thus avoiding any rod damage. In this work, a first analysis of the thermal-mechanical performance of typical fuel rods used in nuclear reactors of the type BWR 5/6, as those two nuclear reactors in Laguna Verde, Veracruz, is performed. This study includes two types of fuel rods: one from a fuel assembly design with an array 8 x 8

  2. Fuel design with low peak of local power for BWR reactors with increased nominal power; Diseno de un combustible con bajo pico de potencia local para reactores BWR con potencia nominal aumentada

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia C, R.; Montes, J.L.; Hernandez, J.L.; Ortiz, J.J.; Castillo, A. [ININ, 52750 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: mrpc@nuclear.inin.mx

    2006-07-01

    The Federal Commission of Electricity recently announcement the beginning of the works related with the increase of the power to 120% of the original nominal one in the Boiling Water Reactors (BWR) of the Laguna Verde Central (CLV): In the National Institute of Nuclear Research (ININ) are carried out studies of the impact on the design of the recharge of derived fuel of this increase. One of the main effects of the power increase type that it is promoting, is the increment of the flow of generated vapor, what takes, to a bigger fraction of vacuum in the core presenting increased values of the maximum fraction to the limit, so much of the ratio of lineal heat generation (XFLPD) as of the ratio of critic power (MFLCPR). In the made studies, it is found that these fractions rise lineally with the increase of the nominal power. Considering that the reactors of the CLV at the moment operate to 105% of the original nominal power, it would imply an increment of the order of 13.35% in the XFLPD and in the MFLCPR operating to a nominal power of 120% of the original one. This would propitiate bigger problems to design appropriately the fuel cycle and the necessity, almost unavoidable, of to resort to a fuel assembly type more advanced for the recharges of the cores. As option, in the ININ the feasibility of continuing using the same type of it fuel assembles that one has come using recently in the CLV, the type GE12 is analyzed. To achieve it was outlined to diminish the peak factor of local power (LPPF) of the power cells that compose the fuel recharge in 13.35%. It was started of a fuel design previously used in the recharge of the unit 1 cycle 12 and it was re-design to use it in the recharge design of the cycle 13 of the unit 1, considering an increase to 120% of the original power and the same requirements of cycle extension. For the re-design of the fuel assembly cell it was used the PreDiCeldas computer program developed in the ININ. It was able to diminish the LPPF

  3. Sydkraft and nuclear power

    International Nuclear Information System (INIS)

    This article summarizes the report made by G. Ekberg for the Swedish Sydkraft Power Co. at the company's annual meeting in June 1976. The report comprises the year 1975 and the first five months of 1976 and largely discusses nuclear power. Experience with the running of Oskarshamn and Barsebaeck nuclear power stations is reported. Nuclear power has enabled production in the oil-fired power stations at Karlshamn and Malmoe to be reduced. 750 000 tons of oil have been saved. In the first five months of 1976, nuclear power accounted for 48% of Sydkraft's electricity production, water power 36% and oil only 16%. In 1975, Sydkraft produced 13% of Sweden's electricity. (H.E.G.)

  4. Experience of MOX-fuel operation in the Gundremmingen BWR plant: Nuclear characteristics and in-core fuel management

    International Nuclear Information System (INIS)

    After 4 years of good experience with MOX-fuel operation in the BWR plants Gundremmingen units B and C the number of inserted MOX-FAs will be increased in the future continuously. Until now all MOX-FAs are in good condition. Furthermore calculations and measurements concerning zero power tests and tip measurements are in good agreement as expected: all results lead to the conclusion that MOX-FAs can be calculated with the same precision as uranium-FAs. (author)

  5. The nuclear power decisions

    International Nuclear Information System (INIS)

    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)

  6. Nuclear power in Belgium

    International Nuclear Information System (INIS)

    In the energy sector Belgium is 90% dependent on imports. This was clearly felt by the electricity generating economy when the share of hydrocarbons in the energy resources used for electricity generation increased to more than 85% in 1973 as a consequence of rising electricity consumption. Although Belgium had been early to start employing nuclear power for peaceful purposes, only little use had initially been made of this possibility. After the first oil price crisis the Belgian electricity utilities turned more attention to nuclear power. To this day, seven nuclear power plants have been started up, and Belgian utilities hold a fifty percent share in a French nuclear power plant, while the French EdF holds fifty percent in one Belgian nuclear generating unit. The Belgian nuclear power plants, which were built mostly by Belgian industries, have an excellent operating record. Their availabilities are considerably above the worldwide average and they contributed some 60% to the electricity production in Belgium in 1985. Thanks to nuclear power, the cumulative percentage shares of heating oil and gas in electricity production were reduced to well over 15%, compared to 1973, thus meeting the objectives of using nuclear power, i.e., to save foreign exchange and become self-sufficient in supplying the country's needs. The use of nuclear power allowed the Belgian utilities to reduce the price per kilowatthour of electricity and, in this way, remain competitive with other countries. The introduction of nuclear power continues to have a stabilizing influence on electricity generating costs. In the light of the forecast future development of consumption it is regarded as probable that another nuclear power plant of 1390 MWe will have to be built and commissioned before the year 2000. (orig.)

  7. Nuclear power economics

    International Nuclear Information System (INIS)

    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)

  8. Balakovo nuclear power station

    International Nuclear Information System (INIS)

    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

  9. 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…

  10. Talk About Nuclear Power

    Science.gov (United States)

    Tremlett, Lewis

    1976-01-01

    Presents an overview of the relation of nuclear power to human health and the environment, and discusses the advantages and disadvantages of nuclear power as an energy source urging technical educators to inculcate an awareness of the problems associated with the production of energy. Describes the fission reaction process, the hazards of…

  11. Economics of nuclear power

    International Nuclear Information System (INIS)

    A comparison of the economics of nuclear and coal-fired power plants operated by Commonwealth Edison was developed. In this comparison, fuel costs, total busbar costs and plant performance were of particular interest. Also included were comparisons of construction costs of nuclear and coal-fired power plants over the past two decades

  12. Nuclear power status 1998

    International Nuclear Information System (INIS)

    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

  13. Nuclear power plant outages

    International Nuclear Information System (INIS)

    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

  14. Nuclear Power Day '86

    International Nuclear Information System (INIS)

    The proceedings in two volumes of the event ''Nuclear Power Day '86'' held in the Institute of Nuclear Research, contain full texts of 13 papers which all fall under the INIS Scope. The objective of the event was to acquaint broad technical public with the scope of the State Research and Development Project called ''Development of Nuclear Power till the Year 2000''. The papers were mainly focused on increased safety and reliability of nuclear power plants with WWER reactors, on the development of equipment and systems for disposal and burial of radioactive wastes, the introduction of production of nuclear power facilities of an output of 1,000 MW, and on the construction of nuclear heat sources. (Z.M.)

  15. Actinides record, power calculations and activity for present isotopes in the spent fuel of a BWR; Historial de actinidos y calculos de potencia y actividad para isotopos presentes en el combustible gastado de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Enriquez C, P.; Ramirez S, J. R.; Lucatero, M. A., E-mail: pastor.enriquez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    The administration of spent fuel is one of the more important stages of the nuclear fuel cycle, and this has become a problem of supreme importance in countries that possess nuclear reactors. Due to this in this work, the study on the actinides record and present fission products to the discharge of the irradiated fuel in a light water reactor type BWR is shown, to quantify the power and activity that emit to the discharge and during the cooling time. The analysis was realized on a fuel assembly type 10 x 10 with an enrichment average of 3.69 wt % in U-235 and the assembly simulation assumes four cycles of operation of 18 months each one and presents an exposition of 47 G Wd/Tm to the discharge. The module OrigenArp of the Scale 6 code is the computation tool used for the assembly simulation and to obtain the results on the actinides record presents to the fuel discharge. The study covers the following points: a) Obtaining of the plutonium vector used in the fuel production of mixed oxides, and b) Power calculation and activity for present actinides to the discharge. The results presented in this work, correspond at the same time immediate of discharge (0 years) and to a cooling stage in the irradiated fuel pool (5 years). (Author)

  16. Nuclear power in India

    International Nuclear Information System (INIS)

    Claim for economic superiority of the nuclear power over the coal-based thermal power is advanced on various grounds by the authorities concerned with organization of atomic energy in India. This claim is critically examined. At the outset, it is pointed out that data on cost of nuclear power available to the Indian researchers for detailed and rational analysis of the problem are limited only to whatever appears in official publications and are not adequate for working out reasonable cost estimates for scrutiny. Available official data are summarised. Taking into account the cost factors related to capital outlay, fuel input, transportation of fuel supplies and disposal of nuclear wastes from nuclear power plants, it is shown that the superiority of the nuclear power over the thermal one on economic grounds is not established in India in the present context. (M.G.B.)

  17. The nuclear power station

    International Nuclear Information System (INIS)

    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)

  18. Nuclear power under strain

    International Nuclear Information System (INIS)

    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)

  19. Nuclear power constructions

    International Nuclear Information System (INIS)

    The feasibility study and the project design and their role in the process of nuclear power plant construction are analyzed in detail. From the point of view of systems aspects of scientific management, the nuclear power plant is considered to be an element of the power generation and transmission system as well as an intersection of capital investment, scientific and technical development and project designing. Foreign experience is summed up with the planning, designing and building of nuclear power plants. Attention is centred to the feasibility study and project design stages of nuclear power plant construction in the CSSR. The questions are discussed of capital investment, territorial planning activities, pre-project and project documentation; a survey is presented of legislative provisions involving the project design and capital investment spheres. Briefly outlined are topics for further rationalization of feasibility studies, such as standardization and complex project designs of WWER type nuclear power plants, the introduction of data processing in capital investment provision of WWER type nuclear power plants, and international scientific and technical cooperation including the establishment of a international consultancy centre for the designing and methodology of controlling the building, repairs, reconstruction and the decommissioning of WWER type nuclear power plants. (Z.M.). 81 figs., 2 tabs., 12 refs

  20. Digital implementation, simulation and tests in MATLAB of the models of Steam line, the turbines, the pressure regulator of a BWR type nucleo electric power plant

    International Nuclear Information System (INIS)

    In this phase of the project they were carried out exhaustive tests to the models of the steam lines, turbines and pressure regulator of a BWR type nucleo electric central for to verify that their tendencies and behaviors are it more real possible. For it, it was necessary to also analyze the transfer functions of the different components along the steam line until the power generator. Such models define alone the dominant poles of the system, what is not limitation to reproduce a wide range of anticipated transitoriness of a power station operation. In the same manner, it was integrated and proved the integrated model form with the models of feeding water of the SUN-RAH, simulating the nuclear reactor starting from predetermined entrances of the prospective values of the vessel. Also it was coupled with the graphic interface developed with the libraries DirectX implementing a specific monitoring panel for this system. (Author)

  1. Training of nuclear power plant personnel practices in Finland

    International Nuclear Information System (INIS)

    Four nuclear power units are in commercial operation in Finland. TVO operates two 735 MW BWR units of Swedish design and IVO two 465 PWR units of Soviet design. Good availability figures have been reached during the last five years for all plants. Many different factors have been contributing to the success of nuclear power in Finland. The advanced training of the plant personnel combined with a high educational level of plant personnel is undoubtedly one of the most important factors. Another important factor has been the low turnover rate of the staff at the plant and in the nuclear industry in general. The favorable regulatory climate in Finland with open and trustworthy relations between the power companies and the authorities has also been an important contribution to the success. The paper gives an overview of the training of nuclear power plant personnel as seen from authorities', the power companies' and the research institutions' points of view

  2. Nuclear Power in Space

    Science.gov (United States)

    1994-01-01

    In the early years of the United States space program, lightweight batteries, fuel cells, and solar modules provided electric power for space missions. As missions became more ambitious and complex, power needs increased and scientists investigated various options to meet these challenging power requirements. One of the options was nuclear energy. By the mid-1950s, research had begun in earnest on ways to use nuclear power in space. These efforts resulted in the first radioisotope thermoelectric generators (RTGs), which are nuclear power generators build specifically for space and special terrestrial uses. These RTGs convert the heat generated from the natural decay of their radioactive fuel into electricity. RTGs have powered many spacecraft used for exploring the outer planets of the solar system and orbiting the sun and Earth. They have also landed on Mars and the moon. They provide the power that enables us to see and learn about even the farthermost objects in our solar system.

  3. The nuclear power cycle

    International Nuclear Information System (INIS)

    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.)

  4. Commercial nuclear power 1990

    International Nuclear Information System (INIS)

    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

  5. Extension of integrated neutronic and thermal-hydraulic analysis capabilities of the 'numerical nuclear reactor' software system for BWR applications

    Energy Technology Data Exchange (ETDEWEB)

    Weber, D.; Sofa, T.; Pointer, D.; Tentner, A.; Zhong, Z. [Argonne National Laboratory, 9700 S. Cass Ave., Argonne, IL 60439 (United States); Downar, T.; Thomas, J. [Purdue Univ., 1290 Nuclear Engineering Building, West Lafayette, IN 47907-1290 (United States); Lo, S.; Splawski, A. [CD-adapco, 200 Shepherds Bush Road, London W6 7NL (United Kingdom)

    2006-07-01

    The Numerical Nuclear Reactor is a software analysis system based on the integration of high fidelity models of neutronic, thermal-hydraulic and thermo-mechanical phenomena. Originally developed for pressurized water reactors (PWRs), the current version has been extended to treat neutronic and thermal-hydraulic issues in boiling water reactors (BWRs). The neutronic module is an extension of the DeCART whole core neutron transport code, which is capable of generating three-dimensional sub-pin level power distributions with the thermal feedback effect incorporated directly during the whole core calculation. The original cell based modular ray tracing scheme has been extended to an assembly modular ray tracing to address the complex geometry of a BWR. Thermal-hydraulic analyses are performed with computational fluid dynamics (CFD) solutions based on the STAR-CD code which has been extended to treat boiling two-phase flow, along with conjugate heat transfer, for expected BWR conditions. Verification and validation of the neutronics and thermal-hydraulics modules are described. Results of integrated calculations are illustrated. A review of the numerical performance on parallel computing system is also provided. (authors)

  6. Development of nuclear power

    International Nuclear Information System (INIS)

    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

  7. Nuclear power experience

    International Nuclear Information System (INIS)

    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

  8. 600 MW nuclear power database

    International Nuclear Information System (INIS)

    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

  9. Nuclear power's dim future

    International Nuclear Information System (INIS)

    The future of nuclear power in the United States is behind us. At the end of 1992, about one-fifth of the U.S. supply of baseload electric power was generated by nuclear plants. The percentage of the nation's electricity produced by nuclear power will decline and the industry's prospects will remain dim. A main damper on the industry's clear plants for the United States in the last 15 years, and none are expected. Other factors that have hurt the American nuclear power industry include escalating capital and operating costs, lengthening licensing and construction times (which contributed substantially to capital cost escalation), allegations of questionable management at several facilities, and seemingly intractable technical problems that include the storage and disposal of increasing amounts of high- and low-level radioactive wastes

  10. Future nuclear power

    International Nuclear Information System (INIS)

    There is no future without nuclear power. Although this view is contested vehemently by dyed-in-the-wool nuclear opponents, more and more indications pointing to a future with nuclear power can be derived from international developments, but are also evident from first principles of the connection between technical development and power supply, especially in the light of global changes over very long periods of time. A qualitative comparison is made of pre-industrial, industrial and post-industrial modes of technical production; the characteristics of the latter are derived from the need for consistency with the unlimited technical possibilities of automation of human labor. It is seen that future requirements to be met in energy supply will be determined chiefly by contraints of reproducing nature. Given proper further development, nuclear power will be able to meet these requirements quickly and extensively. Other sources of primary energy are indispensable over interim periods of time. (orig.)

  11. Safeguarding nuclear power stations

    International Nuclear Information System (INIS)

    The basic features of nuclear fuel accounting and control in present-day power reactors are considered. Emphasis is placed on reactor operations and spent-fuel characteristics for Light-Water Reactors (LWRs) and Heavy-Water Reactors (HWRs)

  12. Nuclear power plant construction

    International Nuclear Information System (INIS)

    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.)

  13. Safety and nuclear power

    International Nuclear Information System (INIS)

    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.)

  14. Usage of industrial robots in nuclear power industry

    International Nuclear Information System (INIS)

    Japan is now at the top level in the world in robot technology.Its application to nuclear power field is one of the most expected. However, their usage spreads over various types of nuclear power plants, their manufacture and operation, and other areas such as fuel reprocessing plants and reactor plant decommissioning. The robots as used for the operation of BWR nuclear power plants, already developed and under development, are described: features in the nuclear-power usage of robots, the robots used currently for automatic fuel exchange, the replacement of control rod drives and in-service inspection; the robots under development for travelling inspection device and the inspection of main steam-relief safety valves, future development of robots. By robot usage, necessary personnel, work period and radiation exposure can be greatly reduced, and safety and reliability are also raised. (Mori, K.)

  15. Serpent: an alternative for the nuclear fuel cells analysis of a BWR; SERPENT: una alternativa para el analisis de celdas de combustible nuclear de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Silva A, L.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Gomez T, A. M., E-mail: lidi.s.albarran@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In the last ten years the diverse research groups in nuclear engineering of the Universidad Nacional Autonoma de Mexico and Instituto Politecnico Nacional (UNAM, IPN), as of research (Instituto Nacional de Investigaciones Nucleares, ININ) as well as the personnel of the Nuclear Plant Management of the Comision Federal de Electricidad have been using the codes Helios and /or CASMO-4 in the generation of cross sections (X S) of nuclear fuel cells of the cores corresponding to the Units 1 and 2 of the nuclear power plant of Laguna Verde. Both codes belong to the Studsvik-Scandpower Company who receives the payment for the use and their respective maintenance. In recent years, the code Serpent appears among the nuclear community distributed by the OECD/Nea which does not has cost neither in its use neither in its maintenance. The code is based on the Monte Carlo method and makes use of the processing in parallel. In the Escuela Superior de Fisica y Matematicas of the IPN, the personnel has accumulated certain experience in the use of Serpent under the direction of personal of the ININ; of this experience have been obtained for diverse fuel burned, the infinite multiplication factor for three cells of nuclear fuel, without control bar and with control bar for a known thermodynamic state fixed by: a) the fuel temperature (T{sub f}), b) the moderator temperature (T{sub m}) and c) the vacuums fraction (α). Although was not realized any comparison with the X S that the codes Helios and CASMO-4 generate, the results obtained for the infinite multiplication factor show the prospective tendencies with regard to the fuel burned so much in the case in that is not present the control bar like when it is. The results are encouraging and motivate to the study group to continue with the X S generation of a core in order to build the respective library of nuclear data as a following step and this can be used for the codes PARCS, of USA NRC, DYN3D of HZDR, or others developed locally

  16. Globalization and nuclear power

    International Nuclear Information System (INIS)

    Different aspects of the experience of nuclear power as recounted by well-known commentators and new contributors are included in two special issues. In general, the discussions are historical and theoretical and most are retrospective. The current position of nuclear power world wide is considered. Its future seems less than secure especially as it will have to compete alongside other energy sources with many problems of control of its materials still unresolved. (UK)

  17. Commercial nuclear power 1989

    International Nuclear Information System (INIS)

    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

  18. Nuclear power plant erection

    International Nuclear Information System (INIS)

    The erection of a nuclear power plant covers all the installation operations related to mechanical and electrical equipment in buildings designed for this specific purpose. Some of these operations are described: erection of the nuclear boiler, erection work carried out in the building accomodating the nuclear auxiliary and ancillary equipment and the methods and the organization set up in order to carry out this work satisfactorily are analyzed

  19. Indian experience in nuclear power generation

    International Nuclear Information System (INIS)

    Nuclear power generation in India commenced in 1969 with the operation of Tarapur Atomic Power Station, which consists of two boiling-water reactor units of 210 MW(e) each. However, an early decision was made in favour of the pressurized-heavy-water reactor as the principal type of power reactor to be set up in the country and the first pressurized-heavy-water reactor unit commenced commercial operation in 1973. The second unit at this station was synchronized to the grid for the first time on 1st November 1980 and began commercial operation in April 1981. The paper describes the operational experience gained from thirteen years of operation of the BWR units at Tarapur and eight years of operation of the PHWR units at Rajasthan. Certain aspects of nuclear power generation are highlighted which are peculiar to a developing country, such as problems faced in operating relatively big nuclear units in medium and small grids, long lead times required for recruitment and training of personnel for manning the stations and spares management, especially in an environment of insufficient industrial infrastructure. The need for operation and maintenance staff to be self-sufficient in the absence of adequate external support is emphasized. A large number of design modifications are described that were carried out to improve the performance of the station and the safety of the plant, and to safeguard the environment and the health of the personnel. (author)

  20. The Korean nuclear power program

    International Nuclear Information System (INIS)

    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

  1. Specimen sampling system in a BWR type nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To accurately determine the impurity concentration in primary coolants. Constitution: Gold or platinum coating is applied to the inner surface of pipeways for a condensate specimen sampling system led out between a condensator and a low pressure condensate pump, a feed water specimen sampling system branched from a feed water pipeway at the downstream of a feed water heater and a reactor water specimen sampling system connected to a reactor water clean up line lead out from a reactor pressure vessel. Since these pipeways have inner diameter of about 6 mm and length of about 100 mm, stainless steel pipeways applied with platings to the inner surface are preferably used in view of the strength. Since gold or platinum is very much stable chemically at high temperature or low temperature, it neither adsorbs metal ions in the specimen water nor erode to leach out impurities, whereby errors due to the pipeway can be eliminated. (Sekiya, K.)

  2. Planning guidance for nuclear-power-plant decontamination. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Munson, L.F.; Divine, J.R.; Martin, J.B.

    1983-06-01

    Direct and indirect costs of decontamination are considered in the benefit-cost analysis. A generic form of the benefit-cost ratio is evaluated in monetary and nonmonetary terms, and values of dollar per man-rem are cited. Federal and state agencies that may have jurisiction over various aspects of decontamination and waste disposal activities are identified. Methods of decontamination, their general effectiveness, and the advantages and disadvantages of each are outlined. Dilute or concentrated chemical solutions are usually used in-situ to dissolve the contamination layer and a thin layer of the underlying substrate. Electrochemical techniques are generally limited to components but show high decontamination effectiveness with uniform corrosion. Mechanical agents are particularly appropriate for certain out-of-system surfaces and disassembled parts. These processes are catagorized and specific concerns are discussed. The treatment, storage, and disposal or discharge or discharge of liquid, gaseous, and solid wastes generated during the decontamination process are discussed. Radioactive and other hazardous chemical wastes are considered. The monitoring, treatment, and control of radioactive and nonradioactive effluents, from both routine operations and possible accidents, are discussed. Protecting the health and safety of personnel onsite during decontamination is of prime importance and should be considered in each facet of the decontamination process. The radiation protection philosophy of reducing exposure to levels as low as reasonably achievable should be stressed. These issues are discussed.

  3. Nuclear power and leukaemia

    International Nuclear Information System (INIS)

    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)

  4. Turkey's nuclear power effort

    International Nuclear Information System (INIS)

    This paper discusses the expected role of nuclear energy in the production of electric power to serve the growing needs of Turkey, examining past activities and recent developments. The paper also reviews Turkey's plans with respect to nuclear energy and the challenges that the country faces along the way

  5. No to nuclear power

    International Nuclear Information System (INIS)

    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

  6. 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)

  7. Nuclear power in space

    International Nuclear Information System (INIS)

    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

  8. BWR 90 - the advanced BWR of the 1990s

    International Nuclear Information System (INIS)

    The future global role of nuclear power will be determined by its ability to provide economical and safe energy. Nuclear power, like any other substantial contributor to the world's energy needs, must be generated at an acceptable cost and with negligible environmental effects. Besides, it must achieve and maintain a socially reasonable level of public acceptance, which in turn is not necessarily governed by rational assessments of the true safety and environmental impact of nuclear power. The ABB Atom approach to this situation can best be characterized as a 'cautious evolution'; for the next decade the company will largely base its offerings to the market on its 'evolutionary' light water reactor design, the BWR 90. This design builds closely on the experience from successful construction and operation of its predecessor, the BWR 75 design. In 1995 and 1996, plants of this design achieved an average load factor greater than the 87% set by EUR; the two BWR units at Olkiluoto in Finland are among the very best performing plants in the world, with an average load factor of 94% over the last 7 years. The continued LWR design development focuses on meeting requirements from utilities as well as new regulatory requirements. A particular emphasis is put on the consequences of severe accidents; there shall be no large releases to the environment. Other design improvements involve: all-digital I and C systems and enhanced human factors engineering to improve work environment for operators, optimization of buildings and containment design to decrease construction time and costs, and selection of materials as well as maintenance and operating procedures to even further reduce occupational radiation exposures. (orig.)

  9. Nuclear power for tomorrow

    International Nuclear Information System (INIS)

    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

  10. Country nuclear power profiles

    International Nuclear Information System (INIS)

    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

  11. Status report on the application of process noise technique in nuclear power plants

    International Nuclear Information System (INIS)

    The report gives a survey of applications of noise technique reported for nuclear power plants. The scope has been limited to areas of interest for BWR and PWR plants of the types found in Sweden and with an emphasis on cases where the practical applicability has been clearly demonstrated. (author)

  12. The reality of nuclear power

    International Nuclear Information System (INIS)

    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.)

  13. France without nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Charmant, A.; Devezeaux de Lavergne, J.-G.; Ladoux, N.; Vielle, M. (Atomic Energy Commission, Paris (France))

    1993-01-01

    As environmental issues (particularly questions associated with the greenhouse effect) become a matter of increasing current concern, so 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 has been 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 1937 to 47% in 1989). The French nuclear industry is also a source of exports, contributing FF 20 billion to the credit side of the balance of payments in 1989. The authors therefore feel that a numerical assessment of the macroeconomic impact of the nuclear power programme is essential to any accurate evaluation of the environmental consequences of that programme. This assessment is set out in the paper using the Micro-Melodie macroeconomic and energy supply model developed by the CEA (Atomic Energy Commission). An assessment of the role of nuclear power in combatting the greenhouse effect is made. 9 refs., 13 figs., 13 tabs.

  14. Future nuclear power generation

    International Nuclear Information System (INIS)

    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.

  15. The nuclear power alternative

    International Nuclear Information System (INIS)

    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

  16. Nuclear power in perspective

    International Nuclear Information System (INIS)

    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

  17. Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, William BJ J [ORNL; Ade, Brian J [ORNL; Bowman, Stephen M [ORNL; Gauld, Ian C [ORNL; Ilas, Germina [ORNL; Mertyurek, Ugur [ORNL; Radulescu, Georgeta [ORNL

    2015-01-01

    Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission have initiated a multiyear project to investigate application of burnup credit for boiling-water reactor (BWR) fuel in storage and transportation casks. This project includes two phases. The first phase (1) investigates applicability of peak reactivity methods currently used in spent fuel pools (SFPs) to storage and transportation systems and (2) evaluates validation of both reactivity (keff) calculations and burnup credit nuclide concentrations within these methods. The second phase will focus on extending burnup credit beyond peak reactivity. This paper documents the first phase, including an analysis of lattice design parameters and depletion effects, as well as both validation components. Initial efforts related to extended burnup credit are discussed in a companion paper. Peak reactivity analyses have been used in criticality analyses for licensing of BWR fuel in SFPs over the last 20 years. These analyses typically combine credit for the gadolinium burnable absorber present in the fuel with a modest amount of burnup credit. Gadolinium burnable absorbers are used in BWR assemblies to control core reactivity. The burnable absorber significantly reduces assembly reactivity at beginning of life, potentially leading to significant increases in assembly reactivity for burnups less than 15–20 GWd/MTU. The reactivity of each fuel lattice is dependent on gadolinium loading. The number of gadolinium-bearing fuel pins lowers initial lattice reactivity, but it has a small impact on the burnup and reactivity of the peak. The gadolinium concentration in each pin has a small impact on initial lattice reactivity but a significant effect on the reactivity of the peak and the burnup at which the peak occurs. The importance of the lattice parameters and depletion conditions are primarily determined by their impact on the gadolinium depletion. Criticality code validation for BWR burnup

  18. LDC nuclear power: Egypt

    International Nuclear Information System (INIS)

    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

  19. Nuclear power in Japan

    International Nuclear Information System (INIS)

    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

  20. Steps to nuclear power

    International Nuclear Information System (INIS)

    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

  1. Space technology needs nuclear power

    International Nuclear Information System (INIS)

    Space technology needs nuclear power to solve its future problems. Manned space flight to Mars is hardly feasible without nuclear propulsion, and orbital nuclear power lants will be necessary to supply power to large satellites or large space stations. Nuclear power also needs space technology. A nuclear power plant sited on the moon is not going to upset anybody, because of the high natural background radiation level existing there, and could contribute to terrestrial power supply. (orig./HP)

  2. Nuclear power: Europe report

    International Nuclear Information System (INIS)

    Last year, 2002, 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 213 plants with an aggregate net capacity of 171 814 MWe and an aggregate gross capacity of 181 135 MWe were in operation. One unit, i.e. Temelin-2 in the Czech Republic went critical for the first time and started test operation after having been connected to the grid. Temelin-2 adds about 1 000 MWe (gross) and 953 MWe (net) to the electricity production capacity. The operator of the Bradwell A-1 and Bradwell A-2 power plants in the United Kingdom decided to permanently shut down the plants due to economical reasons. The units Kozloduj-1 and Kozloduj-2 in Bulgaria were permanently shut down due to a request of the European Union. Last year, 9 plants were under construction in Romania (1), Russia (4), Slovakia (2), 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. It is the first decision to build a new nuclear power plant in Western Europe since ten years. In eight countries of the European Union 141 nuclear power plants have been operated with an aggregate gross capacity of 128 580 MWe and an aggregate net capacity of 122 517 MWe. Net electricity production in 2002 in the EU amounts to approx. 887.9 TWh gross, which means a share of about 34 per cent of the total production in the whole EU. Shares of nuclear power differ widely among the operator countries. They reach 81% in Lithuania, 78% in France, 58% in Belgium, 55% in the Slovak Republic, and 47% in Sweden. Nuclear power also provides a noticeable share in the electricity supply of countries, which operate no own nuclear power plants, e.g. Italy

  3. Ambitious growth programs for nuclear power in Europe - key aspects and expectations

    International Nuclear Information System (INIS)

    RWE experience in projectswithPWR, FBR, BWR and HTR technologies is presented. New nuclear power plant projects in Europe are expected to be safe, climate-friendly and cost-efficient. Success factors for new Nuclear Power Plants to ensure successful investments Sustainable commercial projects are discussed. RWE's involvement in new-build projects in Europe, and in particular 2 units in Cernavoda NPP in Romania and 2 units in Belene NPP in Bulgaria, is presented

  4. 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.

  5. Improvement of fire protection measures for nuclear power plants

    International Nuclear Information System (INIS)

    Improvements of fire protection measures for nuclear power plants were performed as following items: Collection of necessary data and evaluation of parameters, Walk down in the typical BWR and PWR plants, Application of developed analysis method to actual plants, Development of fire hazard analysis manual. With regard to fire tests for the fire data acquisition, the test plan was made about cable fire, oil fire and electric cabinet fire in the concrete test facilities. Implementation of fire hazard analysis model and simulation were performed as following items: Fire analysis codes FDS, CFAST were implemented in order to analyze the fire progression phenomena, Trial calculation of fire hazard for typical NPP by FDS were performed for the Auxiliary feed water pump room (PWR) and the High pressure coolant flooder pump room (BWR). (author)

  6. BWR control blade replacement strategies

    International Nuclear Information System (INIS)

    The reactivity control elements in a BWR, the control blades, perform three significant functions: provide shutdown margin during normal and accident operating conditions; provide overall core reactivity control; and provide axial power shaping control. As such, the blades are exposed to the core's neutron flux, resulting in irradiation of blade structural and absorber materials. Since the absorber depletes with time (if B4C is used, it also swells) and the structural components undergo various degradation mechanisms (e.g., embrittlement, corrosion), the blades have limits on their operational lifetimes. Consequently, BWR utilities have implemented strategies that aim to maximize blade lifetimes while balancing operational costs, such as extending a refuelling outage to shuffle high exposure blades. This paper examines the blade replacement strategies used by BWR utilities operating in US, Europe and Asia by assembling information related to: the utility's specific blade replacement strategy; the impact the newer blade designs and changes in core operating mode were having on those strategies; the mechanical and nuclear limits that determined those strategies; the methods employed to ensure that lifetime limits were not exceeded during operation; and blade designs used (current and replacement blades). (author)

  7. Nuclear power industry

    International Nuclear Information System (INIS)

    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.)

  8. Nuclear power. Europe report

    International Nuclear Information System (INIS)

    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

  9. Nuclear power's burdened future

    International Nuclear Information System (INIS)

    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

  10. France without nuclear power

    International Nuclear Information System (INIS)

    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

  11. Nuclear Power after Fukushima

    International Nuclear Information System (INIS)

    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)

  12. Reviewing nuclear power

    International Nuclear Information System (INIS)

    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)

  13. France without nuclear power

    International Nuclear Information System (INIS)

    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

  14. Prediction of the local power factor in BWR fuel cells by means of a multilayer neural network; Prediccion del factor local de potencia en celdas de combustible BWR mediante una red neuronal multicapas

    Energy Technology Data Exchange (ETDEWEB)

    Montes, J.L.; Ortiz, J.J.; Perusquia C, R. [ININ, Carretera Mexico-Toluca s/n, 52750 La Marquesa, Ocoyoacac, Estado de Mexico (Mexico); Francois, J.L.; Martin del Campo M, C. [Departamento de Sistemas Energeticos, Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: jlmt@nuclear.inin.mx

    2007-07-01

    To the beginning of a new operation cycle in a BWR reactor the reactivity of this it increases by means of the introduction of fresh fuel, the one denominated reload fuel. The problem of the definition of the characteristics of this reload fuel represents a combinatory optimization problem that requires significantly a great quantity of CPU time for their determination. This situation has motivated to study the possibility to substitute the Helios code, the one which is used to generate the new cells of the reload fuel parameters, by an artificial neuronal network, with the purpose of predicting the parameters of the fuel reload cell of a BWR reactor. In this work the results of the one training of a multilayer neuronal net that can predict the local power factor (LPPF) in such fuel cells are presented. The prediction of the LPPF is carried out in those condition of beginning of the life of the cell (0.0 MWD/T, to 40% of holes in the one moderator, temperature of 793 K in the fuel and a moderator temperature of 560 K. The cells considered in the present study consist of an arrangement of 10x10 bars, of those which 92 contains U{sup 235}, some of these bars also contain a concentration of Gd{sub 2}O{sub 3} and 8 of them contain only water. The axial location inside the one assembles of recharge of these cells it is exactly up of the cells that contain natural uranium in the base of the reactor core. The training of the neuronal net is carried out by means of a retro-propagation algorithm that uses a space of training formed starting from previous evaluations of cells by means of the Helios code. They are also presented the results of the application of the neuronal net found for the prediction of the LPPF of some cells used in the real operation of the Unit One of the Laguna Verde Nuclear Power station. (Author)

  15. The politics of nuclear power

    International Nuclear Information System (INIS)

    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.)

  16. Environment and nuclear power

    International Nuclear Information System (INIS)

    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)

  17. Nuclear power production costs

    International Nuclear Information System (INIS)

    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)

  18. Thai Nuclear Power Program

    International Nuclear Information System (INIS)

    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

  19. Present situation of floating nuclear power plants

    International Nuclear Information System (INIS)

    The present situation of investigation and the future problems of floating nuclear power plants in Japan are examined, referring to those in USA. The committee report on a new power generation system in 1970 is quoted. In this report, the site conditions are supposed to be 5 km offshore, 100m water depth, 60 m/sec wind velocity, 10 m wave height, 200 m wave length, 12 seconds wave period 0.2 g earthquake acceleration, and 2.5 knots tide current. The semisubmersible hull of double construction 15 m under water is employed. A pair of 1,000,000 kW BWR reactors are utilized. A sea water desalting unit using bleed steam from turbines is installed. The solid radioactive wastes packed in drums are disposed in sea. The design and cost estimation were made. The names of the organizations who have made investigation in this field, namely the Civil Engineering Society, the Sience and Technology Agency and other several centers, are reported. The Chubu Electric Power Company is forwarding its project. Referring to the investigations in USA, the project of Atlantic nuclear power station unit is described. A report of plant design has been submitted by O.P.S. to United States Atomic Energy Commission in 1973. The Coastal Area Facilities Act was instituted in New Jersey in 1973. Although the Atlantic nuclear power station has been postponed, it is the most feasible project. For the realization of a floating nuclear power plant in Japan, investigation must be started on the ground construction that can endure the construction of breakwater in water depth of 14 to 30 meter. (Iwakiri, K.)

  20. Effect of fraction of voids in the nuclear fuel burned for a 10 X 10 assembly of a BWR

    International Nuclear Information System (INIS)

    A major source of uncertainty in BWR reactor physics is associated with the properties of moderation and coolant bypass regions with a very significant impact on nuclear parameters such as: the finite multiplication factor (k∞), area migration of neutrons (M2) and the void coefficient of reactivity (aν). In this work, we assess the effect caused by the presence of voids in the moderator during the burning of fuel in a fuel assembly type SVEA-96 for a BWR; the codes uses as a tool were INTERPIN-3 and CASMO-4. The geometry SVEA-96 is characterized by an assembly subdivided in four sub-bundles, through an internal bypass cross-shaped gap that allows a more uniform distribution of the moderator, providing a better distribution in the neutrons flux, and thus provide a better distribution of energy and burned. This study was conducted for a wide range of void fractions, from 0% (pure liquid) to 100% (pure steam) and covered: 1) The effect caused by the presence of voids during the burning of nuclear fuel 2) the effects of the structure of energy groups including libraries of cross sections based on ENDF/B-4, and 3) the impact of the presence of control rod. The burning range is from 0 G Wd/Mt to 50 G Wd/Mt. (Author)

  1. Nuclear power plants

    International Nuclear Information System (INIS)

    Before the economical adaptability of nuclear power plants was achieved, many ways were tried to technically use nuclear fission. In the course of a selection process, of numerous types of reactors, only a few have remained which are now taking part in the competition. The most important physical fundamentals, the occurence of various reactor concepts and the most important reactor types are the explained. (orig./TK)

  2. Nuclear power in Germany

    International Nuclear Information System (INIS)

    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

  3. Nuclear power: Europe report

    International Nuclear Information System (INIS)

    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.)

  4. How nuclear power began

    International Nuclear Information System (INIS)

    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)

  5. Impact analysis of modifying the composition of the nuclear fuel of a BWR with beryllium oxide; Analisis del impacto de modificar la composicion del combustible nuclear de un BWR con oxido de berilio

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo V, J. M.; Morales S, J. B., E-mail: euqrop@hotmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2013-10-15

    The beryllium oxide (Be O) presents excellent physical properties, especially its high thermal conductivity that contrasts clearly with that of the uranium dioxide (UO{sub 2}) used at the present as fuel in a great number of nuclear plants. The present work models a nuclear reactor cooled by light water in boiling with two external recirculation loops (BWR/5) using the code for the transitory analysis and postulated accidents Trac-B F1, implementing a UO{sub 2} mixture and different fractions of Be O, with the objective of improving the thermal conductivity of the fuel. The numeric results and the realized analyses indicate that when adding a fraction in volume of 10% the central temperature decreases in 30.4% in stationary state, while during the large break loss of coolant accident the peak cladding temperature diminishes in 7%. Although the real interaction of the mixture has not been determined experimentally, the obtained results are promising. (Author)

  6. Swedes repair BWR thermal fatigue cracks

    International Nuclear Information System (INIS)

    The discovery of cracks in the feedwater and shutdown cooling systems of Sweden's Barseback 2 BWR in 1980 led to investigations in other Swedish nuclear power stations. Similar cracks were found and the defective parts repaired or replaced before being returned to service. The cause of the cracks has been evaluated and efforts are being made to prevent a recurrence. Experience with Ringhals 1, Orkarsham 2 and Forsmark 1 systems are also described. (author)

  7. Nuclear power energy mixes

    International Nuclear Information System (INIS)

    The report contains the papers presented at the conference held on 23/24 February 1994 at the RWTH in Aachen. The goal of this conference was to analyse key issues of future energy management from different viewpoints and to attempt to achieve objective estimations. This VDI Report treats the following main themes: - is the climate question relevant? - chances and limits of renewable energy sources - does nuclear power have a future? - are the nuclear and non-nuclear waste problems solvable? - external costs in energy management -company and energy management decision criteria. (orig.)

  8. Physics of BWR MOX fuel results of an international benchmark study by the OECD/NEA nuclear science committee

    International Nuclear Information System (INIS)

    The results of a theoretical benchmark of boiling water reactor (BWR) assembly containing MOX fuel rods are summarised. This study was carried out by the OECD/NEA Working Party on Physics of Plutonium Fuels and Innovative Fuel Cycles (WPPR). A modern 10 x 10 BWR design with large internal water structure was chosen for this exercise. It corresponds to an ATRIUM 10 (10-9Q) type with symmetrical water gaps. About 30 solutions were submitted by approximately 20 participants using a dozen different code systems with data from well-known state-of-the-art evaluated nuclear data files, a response which underlines the widespread interest in BWR MOX physics. The discrepancies between the participants for the infinite multiplication factor from beginning of life through burn-ups up to 50 MWd/kg are relatively small (less than 1%). The effect due to diverse evaluated data libraries, e.g. JEF and ENDF represents about 1%. The peaking factor is a local value, more dependent on the methods used in the codes, and with lower compensation effects than for reactivity. The discrepancies are larger in value and there are inconsistencies in the location of the peak. The average values with and without the extreme values differ by 2%, implying that the extreme values could be outside the acceptable range. Other parameters examined include the behaviour of the peaking factor under cold conditions, the evolution of peaking factor with burn-up and the effect of voiding the assembly. Close attention was also paid to the depletion behaviour of gadolinia and the burn-up evolution of the heavy metals. The paper describes the results from this benchmark study and draws conclusions on the consistency of the different solutions provided and provides recommendations for the most effective methods. (author)

  9. Japan's nuclear power tightrope

    International Nuclear Information System (INIS)

    This paper reports that early in February, just as Japan's nuclear energy program was regaining a degree of popular support after three years of growing opposition, an aging pressurized-water reactor at Mihama in western Japan sprang a leak in its primary cooling system. The event occasioned Japan's first nontest use of an emergency core-cooling system. It also elicited a forecast of renewed public skepticism about nuclear power form the Ministry of International Trade and Industry (MITI), the Government body responsible for promoting and regulating Japan's ambitious nuclear power program. Public backing for this form of energy has always been a delicate flower in Japan, where virtually every school child visits the atomic bomb museums at Hiroshima and Nagasaki. Yet the country, which imports 80 percent of its energy and just about all its oil, is behind only the United States, France, and the Soviet Union in installed nuclear capacity. In fiscal 1989, which started in April, Japan's 39 nuclear power stations accounted for 25.5 percent of electricity generated - the largest contribution - followed b coal and natural gas. Twelve more plants are under construction

  10. Nuclear Power in Japan.

    Science.gov (United States)

    Powell, John W.

    1983-01-01

    Energy consumption in Japan has grown at a faster rate than in any other major industrial country. To maintain continued prosperity, the government has embarked on a crash program for nuclear power. Current progress and issues/reactions to the plan are discussed. (JN)

  11. Biblis nuclear power station

    International Nuclear Information System (INIS)

    A short constructive description of the components of the Biblis nuclear power station is given here. In addition to the heat flow diagram, the coolant cycle and the turbine control system, some details of construction and reactor safety are presented. (TK/AK)

  12. Fessenheim nuclear power station

    International Nuclear Information System (INIS)

    The Fessenheim nuclear power plant includes two PWR type units each with net electrical output of 890MW(e). The site and layout of the station, geological features and cooling water characteristics are described. Reference is made to other aspects of the environment such as population density and agronomy. (U.K.)

  13. The abuse of nuclear power

    International Nuclear Information System (INIS)

    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

  14. Labor and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Logan, R.; Nelkin, D.

    1980-03-01

    The AFL-CIO is officially pro-nuclear, but tensions within unions are taking issue over ideological differences. The Labor movement, having looked to nuclear power development as an economic necessity to avoid unemployment, has opposed efforts to delay construction or close plants. As many as 42% of union members or relatives of members, however, were found to oppose new power plants, some actively working against specific construction projects. The United Mine Workers and Teamsters actively challenged the nuclear industry while the auto workers have been ambivalent. The differences between union orientation reflects the history of unionism in the US and explains the emergence of social unionism with its emphasis on safety and working conditions as well as economic benefits. Business union orientation trends to prevail during periods of prosperity; social unions during recessions. The labor unions and the environmentalists are examined in this conext and found to be hopeful. 35 references. (DCK)

  15. Expansion of nuclear power in Mexico

    International Nuclear Information System (INIS)

    Full text: Mexico has a Nuclear Power Plant located at Laguna Verde Veracruz. It has two General Electric BWR reactors of 680 MWe each, The first reactor started operating in 1990 and the second one in 1995. Nuclear power contributes about 4.4 % of the total electricity produced in Mexico. The Mexican regulatory body has given the two reactors an operation license of 30 years. The Laguna Verde Nuclear Plant was uprated to 5% of its nominal capacity in 1999 and at the moment there is an ongoing project to uprate it to 20%, this however, implies changing major components such as the turbines. At the present time there are not government official plans to built new NPPs in Mexico; however studies about de technical and economical feasibility new nuclear capacity are being carried out by the CFE and the Mexican Nuclear Research Institute. In Mexico the production of nuclear power is reserved to the state trough Federal Electricity Commission (CFE). The Program of Works and Investment of the Electrical Sector (POISE) is an annual national electricity program prepared by CFE taking into account the electricity needs for the following 10 years. The Mexican government has stated in the POISE 2009-2018 plans to install close to 18,000 MWe by the year 2018 of new electricity capacity, of this amount 15,500 MWe will be produced using conventional sources and 2,500 MWe will be defined in the future considering technologies that can include nuclear power. The most viable option to increase nuclear capacity in Mexico besides the current reactors uprate program is to build new reactors in the same site of Laguna Verde. This site was originally planed to house up to 4 reactors. Another very important issue is the operational license extension to at least 60 years, this can only be archived through a life extension program which is currently underway. The Mexican Nuclear Research Institute has been carrying out a materials surveillance program to determine the current state of the

  16. Nuclear power and nuclear safety 2007

    International Nuclear Information System (INIS)

    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 2007 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)

  17. Nuclear power and nuclear safety 2006

    International Nuclear Information System (INIS)

    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)

  18. Nuclear power and nuclear safety 2005

    International Nuclear Information System (INIS)

    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)

  19. Nuclear power and nuclear safety 2004

    International Nuclear Information System (INIS)

    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)

  20. Nuclear power and nuclear safety 2008

    International Nuclear Information System (INIS)

    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)

  1. Nuclear power plant simulator

    International Nuclear Information System (INIS)

    In this paper, real time nuclear power plant simulator for student education is described. The simulator is composed of a hybrid computer and an operating console. Simulated power plant is a 36 MWt PWR plant, and the average temperature of the primary coolant within the reactor is controlled to be constant. Reactor Kinetics, fuel temperature, primary coolant temperature, temperature and pressure of steam within the steam generator, steam flow, control rod driving system, and feed water controlling system are simulated. The use of the hybrid computer made it possible to simulate a relatively large scale power plant with a comparatively small size computing system. (auth.)

  2. BWR internal cracking issues

    International Nuclear Information System (INIS)

    The regulatory issues associated with cracking of boiling water reactor (BWR) internals is being addressed by the Nuclear Regulatory Commission (NRC) staff and is the subject of a voluntary industry initiative. The lessons learned from this effort will be applied to pressurized water reactor (PWR) internals cracking issues

  3. Facts about nuclear power

    International Nuclear Information System (INIS)

    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)

  4. Economics of nuclear power

    International Nuclear Information System (INIS)

    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.)

  5. Nuclear Power Prospects

    International Nuclear Information System (INIS)

    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

  6. Space Nuclear Power Systems

    Science.gov (United States)

    Houts, Michael G.

    2012-01-01

    Fission power and propulsion systems can enable exciting space exploration missions. These include bases on the moon and Mars; and the exploration, development, and utilization of the solar system. In the near-term, fission surface power systems could provide abundant, constant, cost-effective power anywhere on the surface of the Moon or Mars, independent of available sunlight. Affordable access to Mars, the asteroid belt, or other destinations could be provided by nuclear thermal rockets. In the further term, high performance fission power supplies could enable both extremely high power levels on planetary surfaces and fission electric propulsion vehicles for rapid, efficient cargo and crew transfer. Advanced fission propulsion systems could eventually allow routine access to the entire solar system. Fission systems could also enable the utilization of resources within the solar system.

  7. Infinite fuel element simulation of pin power distributions and control blade history in a BWR fuel assembly

    International Nuclear Information System (INIS)

    Pellet-Cladding Interaction (PCI) is a well known effect in fuel pins. One possible reason for PCI-effects could be local power excursions in the fuel pins, which can led to a rupture of the fuel cladding tube. From a reactor safety point of view this has to be considered as a violence of the barrier principal in order to retain fission products in the fuel pins. This paper focuses on the pin power distributions in a 2D infinite lattice of a BWR fuel element. Lots of studies related PCI effect can be found in the literature. In this compact, coupled neutronic depletion calculations taking the control history effect into account are described. Depletion calculations of an infinite fuel element of a BWR were carried out with controlled, uncontrolled and temporarily controlled scenarios. Later ones are needed to describe the control blade history (CBH) effect. A Monte-Carlo approach is mandatory to simulate the neutron physics. The VESTA code was applied to couple the Monte-Carlo-Code MCNP(X) with the burnup code ORIGEN. Additionally, CASMO-4 is also employed to verify the method of simulation results from VESTA. The cross sections for Monte Carlo and burn-up calculations are derived from ENDF/B-VII.0. (orig.)

  8. Nuclear power for desalination

    International Nuclear Information System (INIS)

    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 1/5th 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 m3/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)

  9. Economics of nuclear power projects

    International Nuclear Information System (INIS)

    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

  10. RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume I. RELAP4/MOD5 description. [PWR and BWR

    Energy Technology Data Exchange (ETDEWEB)

    1976-09-01

    RELAP4 is a computer program written in FORTRAN IV for the digital computer analysis of nuclear reactors and related systems. It is primarily applied in the study of system transient response to postulated perturbations such as coolant loop rupture, circulation pump failure, power excursions, etc. The program was written to be used for water-cooled (PWR and BWR) reactors and can be used for scale models such as LOFT and SEMISCALE. Additional versatility extends its usefulness to related applications, such as ice condenser and containment subcompartment analysis. Specific options are available for reflood (FLOOD) analysis and for the NRC Evaluation Model.

  11. Monitoring method for nuclear power plant

    International Nuclear Information System (INIS)

    In a BWR type nuclear power plant, a critical value to be allowed in view of the operation is determined relative to a minimum critical power ratio (MCPR) and a linear power density in order to keep fuel integrity. The present invention concerns monitoring for the MCPR. That is, CPR is calculated periodically based on each of process data inputted from the plant. An operation limit value is determined based on calculated CPR and each of process data used for the calculation. The operation limit value is corrected, as a function of the control rod position and the reactor flow rate upon CPR calculation and at present. Corrected operation limit value and a low power range monitor (LPRM) signal inputted from the plant are compared to monitor the minimum CPR, that is MCPR. With such procedures, MCPR can be monitored continuously. Further, since the operation limit value is corrected at an insertion position before and after the control rod withdrawal, the non-linear change of the MCPR due to withdrawal of the control rod can be evaluated appropriately. As a result, there is no more necessary to provide unnecessary margin. (I.S.)

  12. P.R. Halls in Tokai and Tsuruga Nuclear Power Stations of The Japan Atomic Power Company

    International Nuclear Information System (INIS)

    (1) P.R. (Public Relations) Hall in Tokai Nuclear Power Station, JAPC. The P.R. Hall in Tokai Nuclear Power Station is in Tokai Village, Ibaraki Prefecture. On the site are the GCR Plant of 166 MWe and a BWR plant of 1,100 MWe. The P.R. Hall is visited especially by local people around nuclear power stations all over Japan. Explanation of nuclear power generation, exhibitions, movies, etc. are presented in the hall. The P.R. Hall is a two-story ferro-concrete building with floor space of 880 m2. (2) The P.R. Hall in Tsuruga Nuclear Power Station, JAPC. The P.R. Hall in Tsuruga Nuclear Power Station is in Tsuruga City, Fukui Prefecture. A BWR plant of 357 MWe is on the site. The P.R. Hall is visited as sightseeing as well as the survey on nuclear power generation. It is a one-story steel frame building with floor space of about 600 m2. (J.P.N.)

  13. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    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

  14. Severe accident management program at Cofrentes Nuclear Power Plant

    International Nuclear Information System (INIS)

    Cofrentes Nuclear Power Plant (GE BWR/6) has implemented its specific Severe Accident Management Program within this year 2000. New organization and guides have been developed to successfully undertake the management of a severe accident. In particular, the Technical Support Center will count on a new ''Severe Accident Management Team'' (SAMT) which will be in charge of the Severe Accident Guides (SAG) when Control Room Crew reaches the Emergency Operation Procedures (EOP) step that requires containment flooding. Specific tools and training have also been developed to help the SAMT to mitigate the accident. (author)

  15. Robots cut risks and costs in nuclear power plants

    International Nuclear Information System (INIS)

    The electric utility industry, the third largest user of computers in the United States, is realizing the value of a relatively new computer-related technology; robotics. Since its use in the cleanup of Three Mile Island, 44 utility companies have used robotic devices to save radiation exposure to their employees and to achieve measurable and often significant cost savings. This paper reports on the use of robots to reduce risk and cost in electric utilities especially in PWR and BWR nuclear power plants

  16. Connected analysis nuclear-thermo-hydraulic of parallel channels of a BWR reactor using distributed computation; Analisis acoplado nuclear-termohidraulico de canales paralelos de un reactor BWR empleando computacion distribuida

    Energy Technology Data Exchange (ETDEWEB)

    Campos Gonzalez, Rina Margarita

    2007-07-15

    This work consists of the integration of three models previously developed which are described widely in Literature: model of the thermo-hydraulic channel, model of the modal neutronic and the model of the recirculation bows. The tool used for this connection of models is the PVM system, Parallel Virtual Machine that allowed paralleling the model by means of the concept of distributed computation. The purpose of making this connection of models is the one of obtaining a more complete tool than better represents the real configuration and the phenomenology of the nucleus of a BWR reactor, thus obtaining better results. In addition to maintaining the flexibility to improve the resulting model at any time, since the very complex or sophisticated models are difficult to improve being impossible to modify the equations they use and can include variables that are not of primary importance in the tackled problem or that mask relations among variables due to the excess of results. Also maintaining the flexibility for adding component of models or systems of the BWR reactor, all of this following the modeling needs. The Swedish Ringhals power plant was chosen to characterize the resulting connected model for counting on a Stability Benchmark that offers the opportunity to count on real plant data. Besides that in case 9 of cycle 14 of this Benchamark oscillations outside phase appeared, which are from great interest because the detection systems that register the average of the power of the nucleus do not detect them. Additionally in this work the model of the recirculation bows as an independent module is obtained in an individual way, since this model belongs to another work and works connected to the reactor vessel. The model of the recirculation bows is able to model several transients of interest, as it is shown in the Appendix A of this work, among which are found the tripping of recirculation pumps or the transference at low or high velocity of them. The scope of the

  17. Nuclear power and ethics

    International Nuclear Information System (INIS)

    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)

  18. Nuclear turbine power plant

    International Nuclear Information System (INIS)

    Purpose : To improve the heat cycle balance in a nuclear turbine power plant or the like equipped with a moisture separating and reheating device, by eliminating undesired overcooling of the drains in the pipes of a heat transmission pipe bundle. Constitution : A high pressure turbine is driven by main steams from a steam generator. The steams after driving the high pressure turbine are removed with moistures by way of a moisture separator and then re-heated. Extracted steams from the steam generator or the high pressure turbine are used as a heating source for the reheating. In the nuclear turbine power plant having such a constitution, a vessel for separating the drains and the steams resulted from the heat exchange is provided at the outlet of the reheating device and the steams in the vessel are introduced to the inlet of the moisture separator. (Aizawa, K.)

  19. Kruemmel nuclear power plant

    International Nuclear Information System (INIS)

    This short description of the site and the nuclear power plant with information on the presumable effects on the environment and the general public is to provide some data material to the population in a popular form so that the citizens may in form themselves about the plant. In this description which shall be presented to the safety report, the site, the technical design and the operation mode of the nuclear power plant are described. Some problems of the emission and the effects of radioactive materials as well as other issues related to the plant which are of interest to the public are dealt with. The supposed accidents and their handling are discussed. The description shows that the selected site is suitable for both setting-up and operation of the plant without affecting the safety of the people living there and that in admissible burdens of the environment shall not have to be expected. (orig./HP)

  20. Jobs and nuclear power

    International Nuclear Information System (INIS)

    To guarantee the existence of Germany as an industrialized country, and to protect jobs, the country needs a comprehensive energy consensus not restricted to the solution of the debate about the future of nuclear power. From the point of view of IGBCE, the Mining, Chemistry and Energy Workers Union, striving for continuity remains a basic prerequisite. The energy mix currently existing offers the best preconditions for a future energy supply in the light of the worldwide development to be expected. Nuclear power cannot be replaced for a foreseeable time without this giving rise to considerable damage to the national economy and ecology alike. An overall objective should be to keep electricity generation in the country. Consistent resource conservation, more efficient energy use, and stricter energy conservation must further enhance the environmental acceptability of energy generation and energy consumption. (orig.)

  1. Nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To suppress corrosion at the inner surfaces of equipments and pipeways in nuclear power plants. Constitution: An injection device comprising a chemical injection tank and a plunger type chemical injection pump for injecting hydrazine as an oxygen remover and ammonia as a pH controller is disposed to the downstream of a condensate desalter column for primary coolant circuits. Since dessolved oxygen in circuit water injected with these chemicals is substantially reduced to zero and pH is adjuted to about 10 - 11, occurrence of stress corrosion cracks in carbon steels and stainless steels as main constituent materials for the nuclear power plant and corrosion products are inhibited in high temperature water, and of corrosion products are inhibited from being introduced as they are through leakage to the reactor core, by which the operators' exposure does can be decreased significantly. (Sekiya, K.)

  2. Nuclear power generation

    International Nuclear Information System (INIS)

    The case for nuclear power, from both a world and a British standpoint, is first discussed, with particular reference to oil supply and demand. It is considered that oil and gas should in future be used as a feedstock for the chemical industry, for transportation purposes, and as a starting point for protein food for animals and later for humans; to squander so much by burning simply as a crude fuel cannot be right. It is considered that Britain should continue constructing nuclear stations at a steady modest rate, and that the fast reactor should receive increasing attention, despite the anti-nuclear lobby. The case for the fast breeder reactor is discussed in detail, including its development at UKAEA Harwell and Dounreay. Accusations against the fast reactor are considered, particularly those concerned with safety, and with the use or misuse of Pu. Public debates are discussed. (U.K.)

  3. Pragmatics of nuclear power

    International Nuclear Information System (INIS)

    In context of depletion of fossil fuels and continuous increase of global warming, nuclear power is highly solicited by world energy congress for solving energy crisis for ever. No doubt, a small amount of nuclear fuel can provide immense amount of energy but in exchange of what? Safety, security, large compensation and huge risk of lives, gift of radio-activity to environment and so many adverse effects. Yet are we in a position to reject or neglect it exclusively? Can we show such luxury? Again are we capable to control such a demon for the benefit of human being. Either is it magic lamp of Aladdin or a Frankenstein? Who will give the answer? Likely after nuclear war, is there anybody left in this planet to hide or is there any place available to hide. Answers are not yet known. (author)

  4. US nuclear power programs

    International Nuclear Information System (INIS)

    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

  5. Preparedness against nuclear power accidents

    International Nuclear Information System (INIS)

    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.)

  6. Initiative against nuclear power plants

    International Nuclear Information System (INIS)

    This publication of the Initiative of Austrian Nuclear Power Plant Opponents contains articles on radiactive waste dispoasal in Austria and and discusses safety issues of the nuclear power plant 'Zwentendorf'. (kancsar)

  7. Nuclear power and public perceptions

    International Nuclear Information System (INIS)

    This text presents and analyzes a survey dealing with public opinion about nuclear power. The author suggests ways to improve communication and information in order to lead people to have a better opinion concerning nuclear power. (TEC)

  8. Nuclear Power: Epilogue or Prologue?

    OpenAIRE

    Harold R. Denton

    1983-01-01

    Judging by the continuing stream of nuclear power plant cancellations and downward revisions of nuclear energy forecasts, there is nothing riskier than predicting the future of commercial nuclear power. U.S. Nuclear Regulation Commissioner John Ahearne (1981) likens the recent events affecting the nuclear power industry in the United States to a Greek tragedy. Others, particularly other nations, take a different view about the future.

  9. Ethical aspects of nuclear power

    International Nuclear Information System (INIS)

    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 CO2 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)

  10. Vietnam and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, N.T.; Hong, L.V. [Viet Nam Atomic Energy Commission (VAEC), Hanoi (Viet Nam)

    1997-12-31

    Economy of Vietnam is developing fast and the electricity demand is growing drastically, last five years about 12.5% per year. The Government puts high target for the future with GDP rating about 8% per year up to 2020. In this case, the electricity demand in 2020 will be tenfold bigger in comparison with 1995`s level. The deficient of domestic resources and the security of energy supply invoke the favorable consideration on nuclear power. (author)

  11. Nuclear power in Sweden

    International Nuclear Information System (INIS)

    The lecture describes the energy-political situation in Sweden after the change of Government in October 1976. The present announced nuclear power plant-hostile energy politic, has to face the viewpoints of a technical and economical dependent reality. Disagreements and transgressions of political competences must be reduced, due to the fact that a constructive cooperation between politicians and energy producing corporations is a necessity, to guarantee a safe energy supply in Sweden. (orig.)

  12. Vietnam and nuclear power

    International Nuclear Information System (INIS)

    Economy of Vietnam is developing fast and the electricity demand is growing drastically, last five years about 12.5% per year. The Government puts high target for the future with GDP rating about 8% per year up to 2020. In this case, the electricity demand in 2020 will be tenfold bigger in comparison with 1995's level. The deficient of domestic resources and the security of energy supply invoke the favorable consideration on nuclear power. (author)

  13. Nuclear power generation device

    International Nuclear Information System (INIS)

    In a PWR type reactor, a free piston type stirling engine is disposed instead of a conventional steam generator and a turbine. Since the stirling engine does not cause radiation leakage in view of the structure, safety and reliability of the nuclear power generation are improved. Further, the thermal cycle, if it operates theoretically, is equivalent with a Carnot cycle having the highest thermodynamical heat efficiency, thereby enabling to obtain a high heat efficiency in an actual engine. (N.H.)

  14. Nuclear power in Italy

    International Nuclear Information System (INIS)

    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

  15. World status: nuclear power

    International Nuclear Information System (INIS)

    The nuclear power situation in 1988 in briefly reviewed. The prospects for the 1990s are then considered. Apart from the use of nuclear power to fuel spacecraft the prospects are not that bright. The European fast breeder programme is coming to a premature end with the winding down of the fast breeder research centre at Dounreay and the delay with the French programme because of the sodium leak at Superphenix. If plutonium is no longer needed to fuel the fast breeder reactors, the reprocessing of spent fuels is less attractive. However, seven new reprocessing plants are due to be commissioned in the next six years. The THORP plant in Britain may be affected by the privatization plans for the electricity supply industry. Decommissioning and waste storage/disposal are issues which will have to be resolved in the 1990s. The risk of accidents especially from aircraft crashes is discussed. Altogether the prospects for nuclear power are not very good. The keynote of the decade will be cleaning up rather than expansion. (U.K.)

  16. Submarine nuclear power plant

    International Nuclear Information System (INIS)

    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.)

  17. Cavitation preventing device in a nuclear power plant

    International Nuclear Information System (INIS)

    Purpose: To prevent the generation of cavitation upon loss of feedwater flow rate in BWR nuclear power plant by reliably and rapidly tripping a recycling pump. Constitution: Two phase streams from a nuclear reactor are divided into main steams and saturated water in a steam drum. The deviation between the corresponding flow rate of the main steams and the feedwater flow rate of the feedwater pump sending condensates to the steam drum, as well as the continuing period of the deviation are monitored. Then, if it is detected that both of the deviation and the continuing period thereof exceed specified levels, the recycling pump feeding the saturated water to the reactor is tripped. In this way, the recycling pump can be tripped rapidly and reliably upon loss of feedwater flow rate, whereby the generation of the cavitation can be prevented and the normal operation of the nuclear power plant can be insured. (Moriyama, K.)

  18. The future of nuclear power

    International Nuclear Information System (INIS)

    Nuclear power is an extremely sensitive issue and its future has been hotly debated. Conflicting arguments have been put forward regarding the viability of nuclear power. The question of whether the world should look to nuclear power for its electricity generating needs is addressed. 2 ills

  19. Overview paper on nuclear power

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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

  1. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant

    International Nuclear Information System (INIS)

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  2. Nuclear eclectic power.

    Science.gov (United States)

    Rose, D J

    1974-04-19

    The uranium and thorium resources, the technology, and the social impacts all seem to presage an even sharper increase in nuclear power for electric generation than had hitherto been predicted. There are more future consequences. The "hydrogen economy." Nuclear power plants operate best at constant power and full load. Thus, a largely nuclear electric economy has the problem of utilizing substantial off-peak capacity; the additional energy generation can typically be half the normal daily demand. Thus, the option of generating hydrogen as a nonpolluting fuel receives two boosts: excess nuclear capacity to produce it, plus much higher future costs for oil and natural gas. However, the so-called "hydrogen economy" must await the excess capacity, which will not occur until the end of the century. Nonelectric uses. By analyses similar to those performed here, raw nuclear heat can be shown to be cheaper than heat from many other fuel sources, especially nonpolluting ones. This will be particularly true as domestic natural gas supplies become more scarce. Nuclear heat becomes attractive for industrial purposes, and even for urban district heating, provided (i) the temperature is high enough (this is no problem for district heating, but could be for industry; the HTGR's and breeders, with 600 degrees C or more available, have the advantage); (ii) there is a market for large quantities (a heat rate of 3800 Mw thermal, the reactor size permitted today, will heat Boston, with some to spare); and (iii) the social costs become more definitely resolved in favor of nuclear power. Capital requirements. Nuclear-electric installations are very capital-intensive. One trillion dollars for the plants, backup industry, and so forth is only 2 percent of the total gross national product (GNP) between 1974 and 2000, at a growth rate of 4 percent per year. But capital accumulation tends to run at about 10 percent of the GNP, so the nuclear requirements make a sizable perturbation. Also

  3. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    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.)

  4. Management of radioactive waste from a major core damage in a BWR power plant

    International Nuclear Information System (INIS)

    Large amounts of fission products would be released in case of a major core damage in a nuclear power reactor. In this theoretical study the core damage is caused by a loss of coolant accident followed by a complete loss of all electric power for about 30 minutes resulting in the release of 10% of the core inventory of noble gases. A second case has also been briefly studied, in which the corresponding core damage is supposed to be created merely by the complete loss of electric power during a limited time period. It appears from the study that the radioactive waste generated as a consequence of an accident of the extent can be managed in the reference reactor with only minor modifications required in the waste plant. The detailed results of the study are reactor specific, but many of the findings and recommendations are generally applicable. (author) 28 refs

  5. Development of a rapid prediction technique for the radioactive release rate in nuclear emergency preparedness. Comparison calculation of radioactivity release for BWR plants

    International Nuclear Information System (INIS)

    When a nuclear disaster occurs in Japan, execution of public protection measures are required before or immediately after (i.e. in the early stage of) radioactive material releases. In particular, in order to carry out sequential protection measures in the urgent protective action planning zone (UPZ), it is important to predict the released amounts of radioactive materials and their influence on the environment. However, in the Fukushima Dai-ich Nuclear Power Plant accident, the emergency response support system (ERSS) and the system for prediction of environmental emergency dose information (SPEEDI) which are used for public protection did not enough achieve their function. Therefore, a quick prediction technique (the technique completed the prediction calculation within 3 minutes, including data input time) was developed using limited information about the amounts of radioactive materials that might be released during accident progression in order to predict appropriate public protection measures at an early stage and to avoid excessive dependence on a complex calculation code. It has been applied to typical PWR plants. Now, in this paper, we extended application of this technique to BWR plants, and we verified that the prediction results of the released total amount of radioactive materials were almost greater than the analysis result using the Incident Progress Prediction System based on the severe accident analysis code MAAP. (author)

  6. Serpent: an alternative for the nuclear fuel cells analysis of a BWR

    International Nuclear Information System (INIS)

    In the last ten years the diverse research groups in nuclear engineering of the Universidad Nacional Autonoma de Mexico and Instituto Politecnico Nacional (UNAM, IPN), as of research (Instituto Nacional de Investigaciones Nucleares, ININ) as well as the personnel of the Nuclear Plant Management of the Comision Federal de Electricidad have been using the codes Helios and /or CASMO-4 in the generation of cross sections (X S) of nuclear fuel cells of the cores corresponding to the Units 1 and 2 of the nuclear power plant of Laguna Verde. Both codes belong to the Studsvik-Scandpower Company who receives the payment for the use and their respective maintenance. In recent years, the code Serpent appears among the nuclear community distributed by the OECD/Nea which does not has cost neither in its use neither in its maintenance. The code is based on the Monte Carlo method and makes use of the processing in parallel. In the Escuela Superior de Fisica y Matematicas of the IPN, the personnel has accumulated certain experience in the use of Serpent under the direction of personal of the ININ; of this experience have been obtained for diverse fuel burned, the infinite multiplication factor for three cells of nuclear fuel, without control bar and with control bar for a known thermodynamic state fixed by: a) the fuel temperature (Tf), b) the moderator temperature (Tm) and c) the vacuums fraction (α). Although was not realized any comparison with the X S that the codes Helios and CASMO-4 generate, the results obtained for the infinite multiplication factor show the prospective tendencies with regard to the fuel burned so much in the case in that is not present the control bar like when it is. The results are encouraging and motivate to the study group to continue with the X S generation of a core in order to build the respective library of nuclear data as a following step and this can be used for the codes PARCS, of USA NRC, DYN3D of HZDR, or others developed locally in the IPN

  7. 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.

  8. The need for nuclear power

    International Nuclear Information System (INIS)

    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.)

  9. A method for performing zero-power BWR rod worth analyses in 2-D

    International Nuclear Information System (INIS)

    A method is presented by which BWR control rod worth analyses are performed in 2-D, using as input collapsed cross-section data from reference all-rods-in (ARI) and all-rods-out (ARO) 3-D calculations. This model was developed as an alternative to the more conventional analytic control rod worth estimator models offered with the Scandpower PRESTO-B nodal simulator code. The major premise behind this model is that the reduction to two dimensions can be performed based on only two reference 3-D calculations, and that rodded and unrodded cross-section data can be combined to accurately model any number of control rod configurations

  10. The outlook for nuclear power in Europe by 2030

    International Nuclear Information System (INIS)

    A 57% increase in the world consumption of electricity is expected between 2004 and 2030. According to the alternative policy scenario of the world energy outlook 2006, the contribution of nuclear power would be +300 GW for a total increase of +4600 GW in power production. The economic outlook for nuclear power appears to be favorable over a long period. Between 2006 and 2030, about 30 countries will order the construction of nuclear power plants but only 5 countries (Usa, China, Japan, Russia and India) will concentrate the 2/3 of this demand. This demand will be met mostly with 10 commercial offers representing reactors of third generation (6 PWR-types + 3 BWR-types + 1 Candu-type). The existing resources of natural uranium (about 15*106 tonnes) are sufficient to ensure in 2040 a global nuclear power as high as 3 to 4 times the today's nuclear power. As for Europe, 2 scenarios are considered: an evolution of -60 GW in case of no decision concerning the construction of new nuclear plants and a likely +120 GW scenario including the replacement of 64 GW. The second scenario will lead to an installed capacity of 229 GW in 2030 compared to today's 172 GW. (A.C.)

  11. Economics of nuclear power

    International Nuclear Information System (INIS)

    Difficulties of nuclear power include higher than expected generating costs, rising construction costs, problems of safety and waste disposal, and the general level of excess capacity in the electric utilities sector. Recently, the debate has turned to cost effectiveness, with critics proposing that nuclear power is not competitive with other generating technologies. Despite the importance of costs in evaluating the nuclear option, there has never been a careful examination of the cost structure of the industry. Much of the existing literature on the subject has either focused on the rising capital costs in the industry or has made strong assumptions about the production process. Aspects of the technology, such as returns to scale or input responses to changing prices, have been omitted from consideration. This thesis, carefully examines the industry's cost structure. This study accounts for the many features peculiar to the technology such as the stoichastic nature of production and the inability of firms to optimize overall inputs. In addition, particular attention is given to make sure that capital is measured consistently. The results of the model indicate that significant substitution possibilities exist among inputs, that increasing returns to scale is present throughout the range of observed output and that plants in the sample tend to be overcapitalized. Further, no evidence of embodied technical change is found

  12. Nuclear power regional analysis

    International Nuclear Information System (INIS)

    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)

  13. Nuclear Power Plant 1996

    International Nuclear Information System (INIS)

    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)

  14. Physical protection of nuclear facilities. Quarterly progress report, July--September 1978. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, L.D. (ed.)

    1979-01-01

    Major activities during the fourth quarter of FY78 included (1) the vital area analysis of operational reactors and characterization of the Standardized Nuclear Unit Power Plant System (SNUPPS), (2) the algorithm development of a new pathfinding computer code, (3) the completion of contractor-supported work for the component generic data base, (4) the refinement of tests related to human parameters modeling, and (5) the addition of improvements to and demonstration of the Safeguards Automated Facility Evaluation (SAFE), Safeguards Network Analysis Procedure (SNAP), and Fixed-Site Neutralization Model (FSNM) methodologies.

  15. Nuclear power in Sweden

    International Nuclear Information System (INIS)

    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.)

  16. Evaluation of the thermal-mechanical performance of fuel rods of a BWR during a power ramp using the FUELSIM code; Evaluacion del desempeno termomecanico de barras de combustible de un reactor BWR durante una rampa de potencia utilizando el codigo FUELSIM

    Energy Technology Data Exchange (ETDEWEB)

    Pantoja C, R.

    2010-07-01

    To avoid the risk to environment due to release of radioactive material, because of occurrence of an accident, it is the priority of the design and performance of the diverse systems of safety of a commercial nuclear power plant. The safety of nuclear power plants requires, therefore, monitoring those parameters having some direct or indirect effect on safety. The thermal limits are values set for those parameters considered having most impact on the safe operation of a nuclear power reactor. Some thermal limits monitoring requires the thermal-mechanical analysis of the rods containing the nuclear fuel. The fuel rod thermal-mechanical behavior under irradiation is a complex process in which there exists a great deal of interrelated physical and chemical phenomena, so that the fuel rod performance analysis in the core of a nuclear power reactor is generally accomplished by using computer codes, which integrate several of the phenomena that are expected to occur during the lifetime of the fuel rod in the core. The main application of the thermal-mechanical analysis codes is the prediction of occurrence of conditions and/or phenomena that could lead to the deterioration or even mechanical failure of the fuel rod cladding, as, for example, the pellet-cladding interaction. In the operation of a nuclear power reactor, fuel preconditioning operations refer to the operational procedures employed to reduce the fuel rod failure probability due to fuel-cladding interaction, specially during reactor startup. Preconditioning simulations are therefore necessary to determine in advance limit values for the power that can be generated in a fuel rod, and thus avoiding any rod damage. In this work, a first analysis of the thermal-mechanical performance of typical fuel rods used in nuclear reactors of the type BWR 5/6, as those two nuclear reactors in Laguna Verde, Veracruz, is performed. This study includes two types of fuel rods: one from a fuel assembly design with an array 8 x 8

  17. Is nuclear power acceptable

    International Nuclear Information System (INIS)

    The energy shortage forecast for the early 21st century is considered. Possible energy sources other than fossil fuel are stated as geothermal, fusion, solar and fission, of which only fission has been demonstrated technically and economically. The environmental impacts of fission are examined. The hazards are discussed under the following headings: nuclear accident, fatality risk, safe reactor, property damage, acts of God, low-level release of radioactivity, diversion of fissile material and sabotage, radioactive waste disposal, toxicity of plutonium. The public reaction to nuclear power is analyzed, and proposals are made for a programme of safety and security which the author hopes will make it acceptable as the ultimate energy source. (U.K.)

  18. Recent trends of new technologies for BWR power plant instrumentation and control

    International Nuclear Information System (INIS)

    For the improvement of the operation reliability of nuclear power stations and its rational realization, Hitachi Ltd. has advanced research and development with the basic thinking of the harmony of men and machines. This time, the new type synthetic, digital, central monitoring and control system for No. 7 plant in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. was completed, and is being installed at the site. For the purpose of further heightening the operation reliability and maintainability of the plant, advanced man-machine function was positively adopted, and the range of automation was expanded, including the automation of control rod operation, therefore, it is the synthetic digitized system of plantwide. It is considered to show one direction toward the more human friendly measurement and control system of next generation. In this report, as the features of the new type synthetic, digital, central monitoring and control system (NUCAMM-90), the advancement of human interface, the automation of control rod operation and the expansion of the range of automation aiming at the operation system with monitoring as the main, and the digitizing of safety and protection system are described. Efforts are exerted for the research and development of the man-machine system of media fusion type, the support systems for operation planning and the time of abnormality and so on. (K.I.)

  19. Nuclear power and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    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

  20. Floating nuclear power plants

    International Nuclear Information System (INIS)

    This article examines the legal regime for floating nuclear power plants (FNPs), in view of the absence of specific US legislation and the very limited references to artificial islands in the Law of the Sea Convention. The environmental impacts of FNPs are examined and changes in US regulation following the Three Mile Island accident and recent US court decisions are described. References in the Law of the Sea Convention relevant to FNPs are outlined and the current status of international law on the subject is analysed. (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. Nuclear Security for Floating Nuclear Power Plants

    International Nuclear Information System (INIS)

    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

  3. Nuclear power and nuclear safety 2011

    International Nuclear Information System (INIS)

    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 2010

    International Nuclear Information System (INIS)

    The report is the eighth 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 2010 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)

  5. Nuclear power and nuclear safety 2009

    International Nuclear Information System (INIS)

    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)

  6. Nuclear power and nuclear safety 2012

    International Nuclear Information System (INIS)

    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)

  7. Plant operation performance improvements of the General Electric (GE) boiling water reactors (BWR'S)

    International Nuclear Information System (INIS)

    This paper summarizes some of the plant operation performance improvement techniques developed by the General Electric Company Nuclear Energy Business Operation for the General Electric Boiling Water Reactors (GE BWR's). Through the use of both thermal and plant hardware operating margins, substantial additional flexibility in plant operation can be achieved resulting in significant improvements in plant capacity and availability factor and potential fuel cycle economics for the currently operating or requisition GE BWR plants. This list of techniques includes expanding the BWR thermal power/moderator flow operating domain to the maximum achievable region, operation with a single recirculation loop out of service and operation at rated thermal power with reduced feedwater temperatures. These plant improvements and operating techniques can potentially increase plant capacity factor by 1% to 2% and provide additional fuel cycle economics savings to the GE BWR's owners

  8. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island design, Docket No. 50-447

    International Nuclear Information System (INIS)

    The Safety Evaluation Report for the application filed by General Electric Company for the Final Design Approval for the General Electric Standard Safety Analysis Report (GESSAR II FSAR) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report summarizes the results of the staff's safety review of the GESSAR II BWR/6 Nuclear Island Design. Subject to favorable resolution of items discussed in the Safety Evaluation Report, the staff concludes that the facilities referencing GESSAR II, subject to approval of the balance-of-plant design, can conform with the provisions of the Act and the regulations of the Nuclear Regulatory Commission

  9. Decommissioning of light-water reactor nuclear power plants

    International Nuclear Information System (INIS)

    This study deals with the technical and economic questions posed by the decommissioning of light-water reactor nuclear power plants of the 900-1300 MW class, account being taken of the distinctions between boiling- and pressurized-water reactors. Possible decommissioning alternatives and the disposal or confinement of activity are discussed. It emerges from the discussion that decommissioning, and even total dismantlement of these nuclear power plants is in principle feasible. The activity inventory, one year after shutdown, is calculated to be about 3 X 107 Ci for the BWR and 4 X 106 Ci for the PWR; 40 years after shutdown these figures are reduced to 2 X 106 and 4 X 105 Ci, respectively. The decommissioning costs to be expected are also estimated. This estimate serves as the basis for an economic comparison by the present worth method. The economic comparison shows that total dismantlement after a cooling time of one year is more than four times as expensive as interim confinement followed by total dismantlement waiting period of 40 years. The present worths for immediate total dismantlement are estimated at DM 200 million for the BWR and DM 170 million for the PWR; for the other alternative, they are put at DM 45 million for the BWR and DM 42 million for the PWR. A still open question is posed by the final storage of the large quantities of bulky radioactive waste arising in partial or total dismantlement. Since no decision on the storage method has yet been taken, disposal in casks is stipulated as a boundary condition in the estimation of the costs, although this is an unrealistic assumption. It is to be presumed that the costs of disposal can be reduced given appropriate final storage. (Auth.)

  10. 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

  11. International nuclear power status 2002

    International Nuclear Information System (INIS)

    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)

  12. International nuclear power status 2001

    International Nuclear Information System (INIS)

    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)

  13. Recent developments in BWR water chemistry

    International Nuclear Information System (INIS)

    Water chemistry is of critical importance to the operation and economic viability of the Boiling Water Reactor (BWR). A successful water chemistry program will satisfy the following goals: - Minimize the incidence and growth of SCC/IASCC, - Minimize plant radiation fields controllable by chemistry, -Maintain fuel integrity by minimizing cladding corrosion, - Minimize flow-accelerated corrosion (FAC) in balance-of-plant components. The impact of water chemistry on each of these goals is discussed in more detail in this paper. It should be noted that water chemistry programs also include surveillance and operating limits for other plant water systems (e.g., service water, closed cooling water systems, etc.) but these are out of the scope of this paper. This paper reviews developments in water chemistry guidelines for U.S. BWR nuclear power plants. (author). 2 figs., 2 tabs., 7 refs

  14. Voices of nuclear power monitors

    International Nuclear Information System (INIS)

    The system of nuclear power monitors was started in fiscal 1977 for the purpose of hearing the opinions of general people on nuclear energy development and utilization and reflecting them to the nuclear power administration. The monitors were a total of 509 persons selected throughout the nation. First, the voices received in the period from January to March, 1980, are summarized. Then, the results of a questionnaire survey conducted in January, 1980, are presented. The survey was made by means of the questionnaire sent by mail. Of the total 509 persons, 372 (73.1%) answered the questions. The items of the questionnaire were: Atomic Energy Day, energy problem, nuclear power development, nuclear power safety administration. Three Mile Island nuclear power accident in U.S., and nuclear power P.R. activities. (J.P.N.)

  15. International nuclear power status 1999

    International Nuclear Information System (INIS)

    This report is the sixth in a series of annual reports on the international development of nuclear power with special emphasis on reactor safety. For 1999, the report contains: General trends in the development of nuclear power; The past and possible future of Barsebaeck Nuclear Power Plant; Statistical information on nuclear power production (in 1998); An overview of safety-relevant incidents in 1999; The development in Sweden; The development in Eastern Europe; The development in the rest of the world; Trends in the development of reactor types; Trends in the development of the nuclear fuel cycle. (au)

  16. Operating experience from Swedish nuclear power plants 2008

    International Nuclear Information System (INIS)

    The overall safety level of the Swedish nuclear power plants during 2008 has been high, despite disturbances that caused longer shutdowns in some plants. A number of improvements have been made in order further to improve the safety of the plants. Electricity production from the power plants amounted to 61.3 TWh, which represents 43 % of Sweden's total electricity production during the year. The total average energy availability was lower than in previous years. For the BWR reactors, it amounted to 78 %, as against an average value of about 84 % for the last five years. For the PWRs, the energy availability was about 87 % in 2008, which is about the same as the five-year average. Oskarshamn 3 and Forsmark 3 suffered from long shutdowns due to cracks in the reactor control rods, which was a contributory reason for the poor performance figures for the BWR reactors. On the PWR side, it was Ringhals 2's problems with auxiliary feed water system capacity that caused a longer shutdown. During the year, KSU started its courses for the maintenance staff of all Swedish power plants at the shut-down Barsebaeck site. This provides training for electrical and mechanical maintenance personnel under authentic conditions, working on real components and systems before doing the same under live conditions at their home power plants

  17. The Brazilian nuclear power programme

    International Nuclear Information System (INIS)

    The booklet contains survey articles on the nuclear power problems of Brazil, the German-Brazilian nuclear power agreement, the application of international safety measures, and 'Brazil and the non-proliferation of nuclear weapons'. The agreement is given in full wording. (HP)

  18. Nuclear power plant

    International Nuclear Information System (INIS)

    The present invention provides a nuclear power plant which generates thermoelectric power by utilizing heat generated by fission reaction. Namely, a fuel/thermoelectric material is made of a semiconductor material containing fission products or a semimetal material containing fission products. A reactor container contains the fuel/thermoelectric material and a reactor core constituted by the fuel/thermoelectric material. The reactor container comprises coolants for removing heat generated by nuclear reaction of fission products from the reactor core and a high temperature side electrode connected to a central portion of the fuel/thermoelectric material and a low temperature side electrode connected to the outside of the fuel/thermoelectric material. Electromotive force is caused in the fuel/thermoelectric material by temperature difference upon combustion caused at the central portion and the outer surface of the fuel/thermoelectric material. The electromotive force is taken out of the high temperature side electrode and the low temperature side electrode. (I.S.)

  19. Nuclear power, nuclear weapons, and international stability

    International Nuclear Information System (INIS)

    The National Energy Plan included as one of its key components a revision of this country's long-standing policy on the development of civilian nuclear power. The proposed change, which would have the effect of curtailing certain aspects of the U.S. nuclear-power program and of placing new restrictions on the export of nuclear materials, equipment, and services, was based explicitly on the assumption that there is a positive correlation between the worldwide spread of nuclear-power plants and their associated technology on the one hand, and the proliferation of nuclear weapons and the risk of nuclear war on the other. The authors advance here the heretical proposition that the supposed correlation may go the other way, and that the recent actions and statements of the U.S. Government have taken little account of this possibility. In brief, they suggest that if the U.S. were to forgo the option of expanding its nuclear-energy supply, the global scarcity of usable energy resources would force other countries to opt even more vigorously for nuclear power and, moreover, to do so in ways that would tend to be internationally destabilizing. Thus, actions taken with the earnest intent of strengthening world security would ultimately weaken it. They believe further that any policy that seeks to divide the world into nuclear ''have'' and ''have not'' nations by attempting to lock up the assets of nuclear technologywill lead to neither a just nor a sustainable world society but to the inverse. In any event the technology itself probably cannot be effectively contained. They believe that the dangers of nuclear proliferation can be eliminated only by building a society that sees no advantage in having nuclear weapons in the first place. Accordingly, they view the problem of the proliferation of nuclear weapons as an important issue not just in the context of nuclear power but in a larger context

  20. Data list of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    This report has collected and compiled the data by December in 1981 concerning performances, equipments and installations of the nuclear power plants in Japan. The data have been modified according to the changes produced after previous publication of 1979 edition including BWR and PWR (JAERI-M 8947) and 1980 edition including PWR (JAERI-M 9629), and extended to cover the new plants developed thereafter. All data have been processed and tabulated with a data processing computer program FREP. Besides this report, user also can refer to 'Data List of Nuclear Power Plant in Japan' through terminals equipped at various places in JAERI using TSS (Time Shearing System) network of FACOM M-200, and the explanation of the usage is given in the Appendix. (author)

  1. Examination of turbine discs from nuclear power plants

    International Nuclear Information System (INIS)

    Investigations were performed on a cracked turbine disc from the Cooper Nuclear Power Station, and on two failed turbine discs (governor and generator ends) from the Yankee-Rowe Nuclear Power Station. Cooper is a boiling water reactor (BWR) which went into commercial operation in July 1974, and Yankee-Rowe is a pressurized water reactor (PWR) which went into commercial operation in June 1961. Cracks were identified in the bore of the Cooper disc after 41,913 hours of operation, and the disc removed for repair. At Yankee-Rowe two discs failed after 100,000 hours of operation. Samples of the Cooper disc and both Yankee-Rowe disc (one from the governor and one from the generator end of the LP turbine) were sent to Brookhaven National Laboratory (BNL) for failure analysis

  2. An overview of the BWR ECCS strainer blockage issues

    Energy Technology Data Exchange (ETDEWEB)

    Serkiz, A.W.; Marshall, M.L. Jr.; Elliott, R. [Nuclear Regulatory Commission, Washington, DC (United States)

    1996-03-01

    This Paper provides a brief overview of actions taken in the mid 1980s to resolve Unresolved Safety Issue (USI) A-43, {open_quotes}Containment Emergency Sump Performance,{close_quotes} and their relationship to the BWR strainer blockage issue; the importance of insights gained from the Barseback-2 (a Swedish BWR) incident in 1992 and from ECCS strainer testing and inspections at the Perry nuclear power plant in 1992 and 1993; an analysis of an US BWR/4 with a Mark I containment; an international community sharing of knowledge relevant to ECCS strainer blockage, additional experimental programs; and identification of actions needed to resolve the strainer blockage issue and the status of such efforts.

  3. The BWR owners' group planning guide for life extension

    International Nuclear Information System (INIS)

    Extending the operating life of a commercial nuclear power plant has been shown to be economically beneficial to both the utility and the electric customer. As such, many utilities are planning and implementing plant life extension (PLEX) programs. A document has been developed which provides guidance to utilities in formulating a PLEX program plant for one or more boiling water reactor (BWR) plants. The guide has been developed by the BWR Owners' Group Plant Life Extension Committee. The principal bases for this guide were the BWR Pilot and Lead Plant Programs. These programs were used as models to develop the 'base plan' described in this guide. By formulating their program plant utilizing the base plan, utilities will be able to maximize the use of existing evaluations and results. The utility planner will build upon the base plan by adding any tasks or features that are unique to their programs. (author)

  4. Digital implementation, simulation and tests in MATLAB of the models of Steam line, the turbines, the pressure regulator of a BWR type nucleo electric power plant; Implementacion digital, simulacion y pruebas en MATLAB de los modelos de la linea de vapor, las turbinas y el regulador de presion de una central Nucleoelectrica tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Lopez R, A. [UNAM, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: andyskamx@yahoo.com.mx

    2004-07-01

    In this phase of the project they were carried out exhaustive tests to the models of the steam lines, turbines and pressure regulator of a BWR type nucleo electric central for to verify that their tendencies and behaviors are it more real possible. For it, it was necessary to also analyze the transfer functions of the different components along the steam line until the power generator. Such models define alone the dominant poles of the system, what is not limitation to reproduce a wide range of anticipated transitoriness of a power station operation. In the same manner, it was integrated and proved the integrated model form with the models of feeding water of the SUN-RAH, simulating the nuclear reactor starting from predetermined entrances of the prospective values of the vessel. Also it was coupled with the graphic interface developed with the libraries DirectX implementing a specific monitoring panel for this system. (Author)

  5. BWR-X experimental reactor for operating in remote sites (thermal-hydraulic study)

    International Nuclear Information System (INIS)

    The primary objective of this indigenous nuclear plant is to power supply no ease accessible places needed of support, like scientific bases and government facilities. What's more, design and built this particular type BWR at low pressure and temperature will give substantial background on nuclear engineering. The paper is intended to treat the nuclear reactor as a heat source in a power cycle and to study the processes by which energy is removed and converted to useful power. (author)

  6. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    The gross output of the 345MWe pressurized water nuclear power station at Obrigheim, operation on base load, amounted to about 2.57TWh in 1974, the net power fed to the grid being about 2.44TWh. The core was used to its full capacity until 10 May 1974. Thereafter, the reactor was on stretch-out operation with steadily decreasing load until refuelled in August 1974. Plant availability in 1974 amounted to 92.1%. Of the 7.9% non-availability, 7.87% was attributable to the refuelling operation carried out from 16 August to 14 September and to the inspection, overhaul and repair work and the routine tests performed during this period. The plant was in good condition. Only two brief shutdowns occurred in 1974, the total outage time being 21/2 hours. From the beginning of trial operation in March 1969 to the end of 1974, the plant achieved an availability factor of 85.2%. The mean core burnup at the end of the fifth cycle was 19600 MWd/tonne U, with one fuel element that had been used for four cycles achieving a mean burnup of 39000 MWd/tonne U. The sipping test on the fuel elements revealed defective fuel-rods in a prototype plutonium fuel element, a high-efficiency uranium fuel element and a uranium fuel element. The quantities of radioactive substances released to the environment in 1974 were far below the officially permitted values. In july 1974, a reference preparation made up in the nuclear power station in October 1973 was discovered by outsiders on the Obrigheim municipality rubbish tip. The investigations revealed that this reference preparation had very probably been abstracted from the plant in October 1973 and arrived at the rubbish tip in a most irregular manner shortly before its discovery

  7. Modernising Sweden's oldest BWR

    International Nuclear Information System (INIS)

    A new range of digital, programmable process control systems has been used to upgrade the instrumentation and control room of Oskarshamn 1's power station. It will enable Sweden's oldest BWR reactor to comply with higher safety levels, improving the operator's overview of production, and reducing the risk of human error. The ''Advant Power'' range of systems will also be used for future planned improvements to the control room. (UK)

  8. Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Analia Bonelli

    2012-01-01

    Full Text Available A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code. Atucha 2 is a pressurized heavy water reactor, cooled and moderated with heavy water, by two separate systems, presently under final construction in Argentina. The initiating event is loss of power, accompanied by the failure of four out of four diesel generators. All remaining plant safety systems are supposed to be available. It is assumed that during the Station Black-Out sequence the first pressurizer safety valve fails stuck open after 3 cycles of water release, respectively, 17 cycles in total. During the transient, the water in the fuel channels evaporates first while the moderator tank is still partially full. The moderator tank inventory acts as a temporary heat sink for the decay heat, which is evacuated through conduction and radiation heat transfer, delaying core degradation. This feature, together with the large volume of the steel filler pieces in the lower plenum and a high primary system volume to thermal power ratio, derives in a very slow transient in which RPV failure time is four to five times larger than that of other German PWRs.

  9. Reliability innovations for AREVA NP BWR fuel

    International Nuclear Information System (INIS)

    AREVA NP is a supplier of nuclear fuel assemblies and associated core components to light water reactors worldwide, representing today more than 185,000 fuel assemblies on the world market including more than 63,000 fuel assemblies for boiling water reactors (BWRs). ATRIUM trademark 10 fuel assemblies have been supplied to a total of 32 BWR plants worldwide resulting in an operating experience over 20,250 fuel assemblies. ATRIUM trademark 10XP and ATRIUM trademark 10XM are AREVA NP's most recent fuel assembly designs featuring improved fuel utilization and achieving high margins to operating limits while maintaining very good reliability. Nevertheless, fuel failures are still encountered in all modern and advanced fuel assembly designs leading to significant operating limitations or unplanned shutdowns of nuclear power plants. The majority of fuel failures in BWR plants are caused by debris fretting, with PCI induced failures being a second leading cause. AREVA NP runs programs to study these root causes and to develop product solutions as part of the continuous improvement process within the Zero Tolerance for Failure (ZTF) initiative. The focus of the ZTF initiative is to further upgrade BWR fuel assembly reliability to achieve the goal of failure free fuel. In the following, two major product improvements are described that will significantly contribute to this goal: - Improved FUELGUARD trademark Lower Tie Plate - Chamfered Fuel Pellet Design (orig.)

  10. An estimation of population doses from a nuclear power plant during normal operation

    International Nuclear Information System (INIS)

    A model is presented for estimation of the potential submersion and inhalation radiation doses to people located within a distance of 1000 km from a nuclear power plant during normal operation. The model was used to calculate doses for people living 200-1000 km from hypothetical nuclear power facility sited near the geographical centre of Denmark. Two kinds of sources are considered for this situation: - unit release of 15 isotopes of noble gases and iodines, - effluent releases from two types of 1000 MWe Light Water Power Reactors: PWR and BWR. Parameter variations were made and analyzed in order to obtain a better understanding of the mechanisms of the model. (author)

  11. Nuclear power: An economic geography

    Energy Technology Data Exchange (ETDEWEB)

    Mounfield, P.R.

    1988-01-01

    This book presents a major study of the economic and social geography of nuclear power. Starting with descriptions of the distribution of nuclear power on a national and international level using maps and graphs, the book goes on to discuss a whole range of topics ranging from reactor design to the socio-economic impact of nuclear power stations. The book discuses the issues as they apply throughout the world.

  12. Discharges from nuclear power stations

    International Nuclear Information System (INIS)

    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)

  13. Manpower development for nuclear power

    International Nuclear Information System (INIS)

    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

  14. Nuclear power program in Korea

    International Nuclear Information System (INIS)

    Korea is a nation making great progress with its nuclear power development program despite the current worldwide nuclear industry slump resulting from the global recession. The reason for this is that Korea does not have sufficient energy resources to meet demand. Six 950 MW nuclear power plants are under construction, and these units are scheduled for completion by 1989. This paper describes the status of Korea's nuclear power development program and the activities of local nuclear industries. It also discusses the efforts being made by local industries to achieve self-reliance

  15. France's nuclear power programme

    International Nuclear Information System (INIS)

    The prospects of development of France's consumption of electricity will widen the deficit of her national energy resources. Nuclear power stations should enable this deficit to be reduced, provided a certain number of uncertainties prevailing today are resolved. The first programme, put forward by Messrs. AILLERET and TARANGER at the 1955 Geneva Conference aimed at commissioning 850 MWe by 1965; the programme was devoted to developing the natural uranium graphite-gas sequence and reaches its completion with the construction of EDF 3, the world's first unit capable of 500 MWe. Before changing over from the prototype stage to their duplication, Electricite De France decided, in agreement with the Commissariat A L'energie Atomique to build EDF 4, which, while reproducing EDF 3's reactor, together with the referring equipment, the entire control equipment and various other systems, pioneers an important innovation by incorporating the heat exchangers and fans inside the prestressed concrete pressure vessel housing the core. At the same time, studies are being carried on on the same type of reactor enabling possible use of a new annular-shaped fuel element, whose use would considerably improve the performance of EDF 5, to be envisaged. On the heavy water side, the construction of EL 4 at Brennilis jointly by the Commissariat A L'energie Atomique and Electricite De France is continuing. Design work on a 500 MWe reactor of this type has already started. As regards pressurized water reactors, the Chooz power station is built jointly by Electricite De France and Belgian Utilities. Finally, the Commissariat A L'energie Atomique is continuing the construction of the 'Rapsodie' rapid neutron reactor at Cadarache, together with studies on a larger power reactor. It may thus be seen that the technical and economic knowledge gained on these various types of reactor mean that an equipment program may be contemplated which will endow nuclear power stations with a place of ever

  16. Safety analysis of thorium-based fuels in the General Electric Standard BWR

    International Nuclear Information System (INIS)

    A denatured (U-233/Th)O2 fuel assembly has been designed which is energy equivalent to and hardware interchangeable with a modern boiling water reactor (BWR) reference reload assembly. Relative to the reference UO2 fuel, the thorium fuel design shows better performance during normal and transient reactor operation for the BWR/6 product line and will meet or exceed current safety and licensing criteria. Power distributions are flattened and thermal operating margins are increased by reduced steam void reactivity coefficients caused by U-233. However, a (U-233/Th)O2-fueled BWR will likely have reduced operating flexibility. A (U-235/Th)O2-fueled BWR should perform similar to a UO2-fueled BWR under all operating conditions. A (Pu/Th)O2-fueled BWR may have reduced thermal margins and similar accident response and be less stable than a UO2-fueled BWR. The assessment is based on comparisions of point model and infinite lattice predictions of various nuclear reactivity parameters, including void reactivity coefficients, Doppler reactivity coefficients, and control blade worths

  17. Nuclear power reactor physics

    International Nuclear Information System (INIS)

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

  18. Nuclear power ecology: comparative analysis

    International Nuclear Information System (INIS)

    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

  19. Nuclear power perspective in China

    International Nuclear Information System (INIS)

    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)

  20. Nuclear power plant operator licensing

    International Nuclear Information System (INIS)

    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.)

  1. 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,…

  2. Nuclear power - the Hydra's head

    International Nuclear Information System (INIS)

    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)

  3. Nuclear power and the UK

    International Nuclear Information System (INIS)

    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.)

  4. Nuclear power in human medicine

    International Nuclear Information System (INIS)

    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.)

  5. Trends in nuclear power developments

    International Nuclear Information System (INIS)

    Modern state and prospects of nuclear power development in industrial states are considered. Structure of power consumption, dynamics of nuclear capacity commissioning, the growth of specific capital expenses for reactor construction, orders for NPP production are analyzed. Electric power production costs at NPPs and coal TPPs in Canada, USA, Western Europe and Japan are compared. It is underlined that inspite of certain depressions nuclear power is being developed further on. Increase of electric power consumption for commercial and public purposes and growth of fresh water shortage appear to be the main prerequisites of its further development

  6. Power peaking nuclear reliability factors

    International Nuclear Information System (INIS)

    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

  7. Nuclear reactor power control device

    International Nuclear Information System (INIS)

    When occurrence of earthquakes is judged in a BWR type reactor, the power is decreased by inserting a portion of control rods, reducing a speed of recycling pumps, stopping recycling pumps, increasing the opening degree of a main steam control valve and opening a main steam relief valve. The reactor scram can be avoided by bypassing neutron flux high signal, settling a filter to neutron flux signals and setting a reactor scram set value by neutron flux signals, for example, to 120%. There is constituted an interlock for performing reactor scram when both of a neutron flux high signal and a signal outputted if a surface heat flux corresponding signal formed by applying calculation to the neutron flux high signal exceeds a set value are valid, to avoid unnecessary reactor scram. As a measuring means, not only an acceleration meter in the power plant, but also acceleration meters at remote places, acceleration meters or displacement meters for various kinds of equipments in the power plant are used, and when signals from them exceed set values, earthquake judgement is conducted. (N.H.)

  8. Power generation costs. Coal - nuclear power

    International Nuclear Information System (INIS)

    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

  9. Knowledge and abilities catalog for nuclear power plant operators: boiling water reactors

    International Nuclear Information System (INIS)

    The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWR) (NUREG-1123) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog and Examiners' Handbook for Developing Operator Licensing Examinations (NUREG-1121) will cover those topics listed under Title 10, Code of Federal Regulations, Part 55. The BWR Catalog contains approximately 7000 knowledge and ability (K/A) statements for ROs and SROs at boiling water reactors. Each K/A statement has been rated for its importance to the safe operation of the plant in a manner ensuring personnel and public health and safety. The BWR K/A Catalog is organized into five major sections: Plant-wide Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Function, Emergency and Abnormal Plant Evolutions, Components, and Theory. The BWR Catalog represents a modification of the form and content of the K/A Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG-1122). First, categories of knowledge and ability statements have been redefined. Second, the scope of the definition of emergency and abnormal plant evolutions has been revised in line with a symptom-based approach. Third, K/As related to the operational applications of theory have been incorporated into the delineations for both plant systems and emergency and abnormal plant evolutions, while K/As pertaining to theory fundamental to plant operation have been delineated in a separate theory section. Finally, the components section has been revised

  10. Nuclear power plant

    International Nuclear Information System (INIS)

    In a condensate cleanup system and a reactor water cleanup system of a BWR-type reactor, in which primary coolants flow, there is disposed a filtering and desalting device using hollow thread membrane filter and ion exchange resin for a condensate cleanup system, and using a high temperature filter made of a metal, a metal oxide or ceramics as a filtering material and a precoat filter made of a powdery ion exchange resin as a filtering material for a reactor water cleanup system. This can completely remove cruds generated in the condensate system. Since the reactor water cleanup system comprises the powdery resin precoat-type filtering and desalting device and the high temperature filter using ceramics, ionic impurities such as radioactive materials can be removed. Accordingly, cruds are not carried into the inside of the reactor, and since the radioactive concentration in the reactor water is reduced, radiation exposure upon periodical inspection can be minimized almost to zero, to attain a clean plant. (T.M.)

  11. Problems concerning the installation of pipings for nuclear power generation

    International Nuclear Information System (INIS)

    The nuclear power stations in the world in operation at the end of 1975 were 173 plants, and those in planning or construction stage were 505 plants. The total power output amounted to 530 x 103 MW. Light water reactors occupy nearly 90% of commercial nuclear power stations. The pipings in a 1100 MW BWR nuclear power station exceeds 5000 tons, and the man-hours for the construction of the pipings are enormous. High degree of safety and reliability are required for these pipings, and it is the difference and the feature that the manufacture and installation of these pipings are carried out under the strict quality assurance system, as compared with other plants. The pipings in a nuclear power plant are diverse and complex, and laid in very restricted spaces. Therefore they interfere with each other, and construction schedule is disturbed. The problems in the planning of the pipings, the reliability of the pipings, the enormous amount of the pipings, the management of working procedures, the storage, piping works and the state of installation, the consideration about the design and layout, the pipings in a containment vessel and the models of machinery and equipments, and the tendency of design method for the future are explained. (Kako, I.)

  12. Nuclear power project in Thailand

    International Nuclear Information System (INIS)

    Full text: Thailand has been highly relied on fossil fuels for electricity generation. In fact 66% of today's electric power is supplied from natural gas. With current unprecedented increase of oil and gas prices, the country is in need of alternative energy sources more than ever. The Government recognizes the problem and seeks sustainable solution not only to improve energy security but also to reduce greenhouse gases emission, the root of threatening global warming problem. For base load power generation, however, nuclear power is perhaps the only practical option currently available. As a result, in Thailand Power Development Plan 2007-2021 (PDP 2007), there will be a 1,000 MWe nuclear power plant commercialized in 2020 and another in 2021. By the end of 2021, nuclear share of electricity generation of Thailand will be about 5%. Due to the fact that this is Thailand's first nuclear power plant, necessary infrastructures are not currently in place. To cope with this requirement, on April 11, 2007, the National Energy Policy Council (NEPC) appointed the Nuclear Power Infrastructure Preparation Committee (NPIPC) to develop the Nuclear Power Infrastructure Establishment Plan (NPIEP). NPIEP comprises two major plans: nuclear power infrastructure and nuclear power utility preparation plans. Required infrastructures include: legal and regulatory systems and international commitments; industrial infrastructure and commerce; technology development and transfer and human resources development; nuclear safety and environmental protection; and public relations and public acceptance. Utility planning comprises preparations for setting up organizational structure to accommodate a nuclear power project, technology selection, assessment of nuclear safety and technical aspects of nuclear power generation, and implementation of project feasibility study and site selection. NPIEP had been effectively developed under guidelines and technical support from the International Atomic

  13. Low-power nuclear reactors

    International Nuclear Information System (INIS)

    A brief development history of low-power nuclear reactors is presented in this paper. Nowadays, some countries have plans to build a series of small nuclear power plants (also floating ones) for use in remote regions. Present constructions of such NPP are presented in this paper. (author)

  14. Competitive economics of nuclear power

    International Nuclear Information System (INIS)

    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

  15. Islands for nuclear power stations

    International Nuclear Information System (INIS)

    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)

  16. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    Lin Chengge; Li Shulan

    2009-01-01

    @@ China's nuclear power industry experienced such three stages as initiation, moderate development and active development. So far, there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW. In addition, there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  17. Nuclear power - the moral question

    International Nuclear Information System (INIS)

    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)

  18. International nuclear power status 2000

    International Nuclear Information System (INIS)

    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)

  19. Nuclear power supply (Japan Nuclear Safety Institute)

    International Nuclear Information System (INIS)

    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)

  20. The collapse of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Jeffery, J.W. (Birkbeck Coll., London (UK))

    1991-06-01

    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).

  1. Nuclear power and the environment

    International Nuclear Information System (INIS)

    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

  2. Completion of Kashiwazaki Kariwa Nuclear Power Station Unit No. 4

    International Nuclear Information System (INIS)

    No. 4 plant in Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. is a BWR plant in which the results of the LWR improvement and standardization project by Japanese independent technology were adopted. Hitachi Ltd. has applied the experiences of construction and operation obtained so far, the improved technology based on research and development and the latest technologies to it, in addition to the technology which was verified in the preceding No. 5 plant. In the aspect of the systems and facilities, the various improvements based on the experience in past plants were reflected from the initial stage of design. Also in the design techniques, the three-dimensional CAD system using the newest computer technology was applied to the layout and piping design, and the quality and efficiency of design were improved. In the aspect of construction, a crawler crane with the largest lifting capacity in the world was used, and the large section module method, by which large prefabricated machinery, equipment and piping are directly lifted in, was applied. By these means, the safety of workings was secured, the construction period was shortened, and the plant showed good, stable results in the trial, and started the commercial operation in August, 1994. No. 4 plant is a BWR plant of 1100 MW output. The applied new technologies and the contents of the improvement of the design and facilities are shown. The outline and the features of the construction works and the trial operation are reported. (K.I.)

  3. Evaluation of the cracking by stress corrosion in nuclear reactor environments type BWR

    International Nuclear Information System (INIS)

    The stress corrosion cracking susceptibility was studied in sensitized, solution annealed 304 steel, and in 304-L welded with a heat treatment that simulated the radiation induced segregation, by the slow strain rate test technique, in a similar environment of a boiling water reactor (BWR), 288 C, 8 MPa, low conductivity and a electrochemical corrosion potential near 200 mV. vs. standard hydrogen electrode (She). The electrochemical noise technique was used for the detection of the initiation and propagation of the cracking. The steels were characterized by metallographic studies with optical and scanning electronic microscopy and by the electrochemical potentiodynamic reactivation of single loop and double loop. In all the cases, the steels present delta ferrite. The slow strain rate tests showed that the 304 steel in the solution annealed condition is susceptible to transgranular stress corrosion cracking (TGSCC), such as in a normalized condition showed granulated. In the sensitized condition the steel showed intergranular stress corrosion cracking, followed by a transition to TGSCC. The electrochemical noise time series showed that is possible associated different time sequences to different modes of cracking and that is possible detect sequentially cracking events, it is means, one after other, supported by the fractographic studies by scanning electron microscopy. The parameter that can distinguish between the different modes of cracking is the re passivation rate, obtained by the current decay rate -n- in the current transients. This is due that the re passivation rate is a function of the microstructure and the sensitization. Other statistic parameters like the localized index, Kurtosis, Skew, produce results that are related with mixed corrosion. (Author)

  4. Nuclear power in developing countries

    International Nuclear Information System (INIS)

    In early 1988, 417 nuclear power plants were in opration worldwide, which is twenty more than in early 1987. The total installed power of 300 GWe corresponds to 11% of the total generating capacity and contributes more than 16% of the worldwide electricity production. Fifty of these nuclear power plants, with an aggregate 28 GWe, have been built in developing countries, where they contribute 7% to the electricity requirement. With respect to installed power, the growth of nuclear power lags behind the plans made ten years ago, because some developing countries have stretched out their nuclear power programs for the next decade. This is due to various reasons. In some cases, the availability of alternative energies has reduced the use of nuclear power. In other cases, the delay has been due to funding and to the long planning and construction periods. The main problem facing the developing countries, however, is financing nuclear power plant projects in the light of the high capital costs of nuclear power plants. (orig.)

  5. Construction costs - nuclear power stations

    International Nuclear Information System (INIS)

    According to present development plans in the western industrial nations nuclear power will be able to cover 35 to 45% of power requirements in the mid 1980's. Although specific investment costs are higher for nuclear power plants than for other thermal power stations, nuclear plants are in a position today to generate power more economically than fossil fired plants into the upper part of the middle load sector. The relatively high proportion of fixed costs of the total power generation costs, and a still considerable potential to exploit the economy of scale, will contribute to minimize the inflationary burden on electric power generation. Nevertheless price development of nuclear power plants should be watched attentively, rapid price escalation for components, extremely long planning and construction times and exaggerated environmental protection requirements which serve no real purpose may reduce the economic benefit gained by nuclear energy. Electrical utilities will try to hold investment cost down by all means; for instance they will encourage standardization of nuclear power plants or order twin stations. For long term utilization of nuclear energy the development of high temperature reactors and fast breeders is a logical step forward. (author)

  6. Developing countries curtail nuclear power

    International Nuclear Information System (INIS)

    The nuclear power programmes in developing countries, following the accident at the Chernobyl power plant are summarized. Many of these have abandoned plans for nuclear power (eg Gabon), mothballed existing reactors (eg Philippines) or deferred decisions on a reactor programme (eg Egypt, Taiwan, Libya). Economic and political pressures are usually the underlying reasons, but the Chernobyl incident has proved a useful excuse. Other countries (Nigeria, Korea, India, Pakistan) have not let the accident change their nuclear policy. In China, Israel and Turkey the debate about nuclear power has been sharpened by the accident. Although Chernobyl has hastened decisions on nuclear power in some countries it has not affected the long-term policies of developing countries. (UK)

  7. Solid-State Nuclear Power

    Science.gov (United States)

    George, Jeffrey A.

    2012-01-01

    A strategy for "Solid-State" Nuclear Power is proposed to guide development of technologies and systems into the second 50 years of nuclear spaceflight. The strategy emphasizes a simple and highly integrated system architecture with few moving parts or fluid loops; the leverage of modern advances in materials, manufacturing, semiconductors, microelectromechanical and nanotechnology devices; and the targeted advancement of high temperature nuclear fuels, materials and static power conversion to enable high performance from simple system topologies.

  8. Strategy for utilizing nuclear power

    International Nuclear Information System (INIS)

    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

  9. Special aspects of nuclear power

    International Nuclear Information System (INIS)

    This paper discusses how, with almost 300 nuclear power plants operating worldwide, the safety of nuclear power will soon be better known. Over the next decade we will learn whether or not the lessons learned from these accidents have made nuclear power safer. In the meantime, we must be well prepared to take care of patients injured in accidents at normally operating and at malfunctioning power plants. It would be tragic if lack of preparation and/or fear of radiation resulted in mistreatment of patients

  10. Medical perspective on nuclear power

    International Nuclear Information System (INIS)

    Is generating electricity with nuclear power safe in the United States? Could the explosion of a nuclear power reactor cause widespread dissemination of radioactivity, as the Chernobyl explosion did in 1986? How do power reactors operate, and what principles safeguard their operation? What should be the role of the physician with regard to nuclear power? A recent report of the Council on Scientific Affairs of the American Medical Association (AMA) considered such questions. The report, prepared by an expert committee, received the endorsement of the AMA's House of Delegates. Major issues delineated in the report and all of its conclusions appear in this summary. 20 refs

  11. Garigliano nuclear power plant

    International Nuclear Information System (INIS)

    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

  12. Nuclear reactor power monitor

    International Nuclear Information System (INIS)

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

  13. Obrigheim nuclear power plant

    International Nuclear Information System (INIS)

    In 1973 the 345 MW pressurized water nuclear power plant at Obrigheim operated on base load, generating approximately 2.63 TWh, approximately 2.5 TWh of which was supplied to the KWO members. The plant availability for the year was 89.9%. Of the 10.1% non-availability, 6.4% (23 d) was caused by refuelling, including inspection, overhaul and repair operations and routine tests carried out in September 1973. 3.3% was due to stoppages for repairs to a steam generator and the two main cooling pumps, while 0.4% resulted from failures in the electrical section of the plant. The plant was shut down seven times in all, including three scrams. The average core burnup at the end of the fourth cycle (1 September 1973) was 18900 MWd/tU, representing an average burnup of approximately 37500 MWd/tU for a fuel element used in all four cycles. The operating performance of the steam generators and the result of the steam generator inspection carried out during refuelling in 1973 suggest no progressive damage. The quantities of radioactive materials released to the environment in 1973 were well below the officially permitted levels. The availability of the plant from the beginning of pilot operation in 1969 to the end of 1973 was 83.7 %

  14. Climate change and nuclear power

    International Nuclear Information System (INIS)

    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)

  15. BWR recirculation pump diagnostic expert system

    International Nuclear Information System (INIS)

    At General Electric (GE), an on-line expert system to support maintenance decisions for BWR recirculation pumps for nuclear power plants has been developed. This diagnostic expert system is an interactive on-line system that furnishes diagnostic information concerning BWR recirculation pump operational problems. It effectively provides the recirculation pump diagnostic expertise in the plant control room continuously 24 hours a day. The expert system is interfaced to an on-line monitoring system, which uses existing plant sensors to acquire non-safety related data in real time. The expert system correlates and evaluates process data and vibration data by applying expert rules to determine the condition of a BWR recirculation pump system by applying knowledge based rules. Any diagnosis will be automatically displayed, indicating which pump may have a problem, the category of the problem, and the degree of concern expressed by the validity index and color hierarchy. The rules incorporate the expert knowledge from various technical sources such as plant experience, engineering principles, and published reports. These rules are installed in IF-THEN formats and the resulting truth values are also expressed in fuzzy terms and a certainty factor called a validity index. This GE Recirculation Pump Expert System uses industry-standard software, hardware, and network access to provide flexible interfaces with other possible data acquisition systems. Gensym G2 Real-Time Expert System is used for the expert shell and provides the graphical user interface, knowledge base, and inference engine capabilities. (author)

  16. Nuclear power for environmental protection

    International Nuclear Information System (INIS)

    Nuclear power does not produce CO2 or other greenhouse gases, and also does not produce any SO2, NOx 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 CO2: 12,000 t of SO2; and 6,000 t of NOx, 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 CO2. 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 CO2 annually. This is 8% of the 20,000 million tons of CO2 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

  17. Nuclear power sector in Romania

    International Nuclear Information System (INIS)

    According to a recent Romanian Government Decision on restructuring strategy of the power sector in Romania the first step was the creation of the National Power Company (CONEL) and splitting off the nuclear research, design-engineering and some support activities. At the same time, the former Nuclear Power Group split into the National Nuclear Electric Company ('Nuclearelectrica'-S.A.) and Regia Autonoma pentru Activitati Nucleare. The 'Nuclearelectrica'-S.A. (SNN) includes three subsidiaries, one for nuclear power production, CNE-PROD (Cernavoda Unit 1), one for nuclear power development, CNE-INVEST (Cernavoda Units 2 to 5) and one for nuclear fuel fabrication FCN (Pitesti Nuclear Fuel Plant). The other branches of the former Nuclear Power Group, as Heavy Water Plant (ROMAG-Drobeta), Institute for Nuclear Research (INR-Pitesti) and Center for Nuclear Projects Engineering (CITON-Bucharest) are parts of the new created 'Regia Autonoma pentru Activitati Nucleare'. On 11 July 1996 Romania joined the 'Nuclear Club' and the first nuclear megawatt-hour was supplied by the Cernavoda NPP into our national grid. On December 2, 1996 the Cernavoda Unit 1 reached the level of commercial operation. Planned to produce 4.5 TWh yearly the Cernavoda NPP-Unit 1 represents about 10% of the overall power production of the country. Up to the end of August 1998, the Unit 1 generated a total of 9.17 TWh at a gross capacity factor of 85%. The plant's good performance to date demonstrates the SNN's total commitment to meet world class standards and to ensure that Cernavoda NPP Unit 1 is among the best performing stations in the world. Romanian Power Sector Least Cost Development Studies demonstrate the opportunity to complete and put Unit 2 of Cernavoda NPP in commercial operation up to the year 2001, in cooperation with AECL and ANSALDO. The author emphasizes the strong help and support which the IAEA granted to Romania Nuclear Power Program, especially after 1989 in all areas of

  18. Nuclear power, economy and environment

    International Nuclear Information System (INIS)

    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)

  19. Nuclear power for sustainable development

    International Nuclear Information System (INIS)

    Energy demand continues to grow in spite of drastic efforts, especially in OECD countries for efficiency and energy savings. At the same time, the concept of sustainable development is calling for the alleviating and/or mitigating of environmental impacts. A limited number of options, that are technically mature and economically competitive, can substitute fossil fuel burning for electricity generation. Nuclear power is one of the electricity generating options that can contribute to an environmentally friendly development. The paper investigates the potential role of nuclear power in global energy supply up to 2050 and analyses the opportunities and challenges, for governments and nuclear industries, of a broad nuclear power deployment in response to environmental concerns. It concludes that, in the long term, increasing substantially the share of nuclear power in electricity generation is feasible and would contribute significantly to enhancing the sustainability of energy supply systems world-wide. (author)

  20. Nuclear power: a Greek tragedy

    International Nuclear Information System (INIS)

    The present state and expected future of nuclear power and its regulation in the United States is outlined. The two major influences on the nuclear regulatory environment in the US, outside of the Three Mile Island accident, are the legal profession and the Congress. The increasing influence of the lawyers and the diverse and increasing interaction with the Congress is examined. It is concluded that nuclear power in the US has one fatal flaw - it cannot get public acceptance. The deep hatred and divisions within the US public on the issues of nuclear power, the uncertainties of accidents, the confusion over what is radiation, the fear of abnormalities and serious cancers in future generations, the author believes will lead to the demise of commercial nuclear power in the US. (U.K.)

  1. Nuclear power: a Greek tragedy

    Energy Technology Data Exchange (ETDEWEB)

    Ahearne, J. (Nuclear Regulatory Commission, Washington, DC (USA))

    1981-01-01

    The present state and expected future of nuclear power and its regulation in the United States is outlined. The two major influences on the nuclear regulatory environment in the US, outside of the Three Mile Island accident, are the legal profession and the Congress. The increasing influence of the lawyers and the diverse and increasing interaction with the Congress is examined. It is concluded that nuclear power in the US has one fatal flaw - it cannot get public acceptance. The deep hatred and divisions within the US public on the issues of nuclear power, the uncertainties of accidents, the confusion over what is radiation, the fear of abnormalities and serious cancers in future generations, the author believes will lead to the demise of commercial nuclear power in the US.

  2. Nuclear power in the Midwest

    International Nuclear Information System (INIS)

    The Twelfth Annual Illinois Energy Conference, held in Chicago, Illinois, October 1984 was sponsored by the Energy Resources Center, University of Illinois at Chicago in cooperation with the U.S. Department of Energy, the Illinois Department of Energy and Natural Resources, the Illinois Energy Resources Commission, and the Illinois Commerce Commission. The theme for the conference was ''Nuclear Power in the Midwest.'' The topic of Nuclear Power is particularly appropriate in view of the fact that the State of Illinois, as well as the Midwest region, has made a major commitment to the use of this option for electric power generation. This is evidenced by the fact that some twenty-three of the eighty-six currently licensed nuclear reactors in the United States are located in the Midwest region. Illinois alone contains ten licensed nuclear reactors with four other nuclear plants either under construction or waiting for an operating license. In rated capacity of electric power generated by nuclear reactors, the region is capable of producing 21.5% of the national total of 70,000 MWe. The problems surrounding nuclear power involve complex technologies, environmental and public health concerns, economic and legal factors as well as numerous other policy questions. The goal of the 12th Annual Illinois Energy Conference was to review these issues in order to educate the public and to assist government policy makers in making rational judgements regarding the use and development of the nuclear power option

  3. 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.)

  4. Towards sustainable nuclear power development

    International Nuclear Information System (INIS)

    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.)

  5. Nuclear power - a reliable future

    International Nuclear Information System (INIS)

    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

  6. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    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

  7. Nuclear power prospects in Pakistan

    International Nuclear Information System (INIS)

    As part of its programme to assist the development of nuclear power, IAEA undertakes, on r e quest, reviews of the prospects for nuclear power in individual Member States. A general finding of the Pakistan report is that nuclear power should be considered 'a leading contender for the supply of future energy needs'. A principal reason for this is that the conventional energy resources available, both of hydroelectric energy and of fossil fuels, appear insufficient by themselves to give in the long run the high per capita consumption of electricity which is characteristic of a developed country. Thus, an alternative source of energy to supplement the existing resources appears desirable. The analysis comparing nuclear power economics with those of conventional alternatives is performed separately for the Karachi area, for West Pakistan and for East Pakistan, since the power supply systems serving these regions are not now, nor in the near future likely to be, interconnected

  8. Checking nuclear power station safety

    International Nuclear Information System (INIS)

    The paper describes the test facilities and research projects for Sizewell-B and other nuclear power stations, directed by the National Nuclear Corporation (NNC). The NNC is Britain's nuclear power station design and construction company, and is currently carrying out commissioning on both the Heysham and Torness AGRs. A description is given of NNC's nuclear research and development work, which includes: the production of Cobalt-free alloy, coatings for the primary containment shell, and ''fitness for purpose'' tests on reactor components using its 'Loki' rig to put the equipment through postulated accident conditions. NNC also has a rig to test structural features under extreme thermal shock conditions. (U.K.)

  9. On PA of nuclear power

    International Nuclear Information System (INIS)

    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.)

  10. Emergency power systems at nuclear power plants

    International Nuclear Information System (INIS)

    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

  11. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant; Analisis de documentos de los materiales de la envolvente del nucleo del reactor nuclear de la CLV U-1

    Energy Technology Data Exchange (ETDEWEB)

    Zamora R, L.; Medina F, A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  12. Simulation of a scenario of total loss of external and internal power (Sbo) for different vent pressures of the containment of a BWR-5

    International Nuclear Information System (INIS)

    The simulation of a Station Black Out (Sbo) was realized with intervention of the vent containment by means of a rigid vent coming from the dry-well and that discharges directly to the atmosphere, with the MELCOR code version 2.1. This scenario was carried out for a BWR-5 and containment type Mark II, with a thermal power of 2317 MWt similar to the reactor of nuclear power plant of Laguna Verde. For this scenario was considered as only available system for coolant injection to the reactor to the Reactor Core Isolation Cooling (Rcic), which remained operating 4 hours with batteries bank. The Security and Relief Valves (SR V) were considered functional (by simplicity) and that they mechanically do not exceed their capacity to liberate pressure due to the performances in their safety way. The operator maneuver to perform the SR V and to de pressurize the vessel until the pressure (13 kg/cm2) to operate the low pressure systems was modeled. The results cover approximately 48 hours (172000 seconds), time in which was observed the behavior of the level and pressure in the vessel. Also the scenario evolution was analyzed to different vent pressures of the primary containment (2.0, 3.0, 4.5, 6.0, and 10.0 kg/cm2), the temperature profiles of the dry-well, the hydrogen accumulation in the containment, the radio-nuclides liberation through rigid vent to the atmosphere and the inventory of these. In this work an analysis of the pressure behavior in the primary containment is presented, with the purpose of minimizing liberated fission products to the environment. (Author)

  13. 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.

  14. Effects of Void Uncertainties on Pin Power Distributions and the Void Reactivity Coefficient for a 10X10 BWR Assembly

    Energy Technology Data Exchange (ETDEWEB)

    Jatuff, F.; Krouthen, J.; Helmersson, S.; Chawla, R

    2004-03-01

    A significant source of uncertainty in Boiling Water Reactor physics is associated with the precise characterisation of the axially-dependent neutron moderation properties of the coolant inside the fuel assembly channel, and the corresponding effects on reactor physics parameters such as the lattice neutron multiplication, the neutron migration length, and the pin-by-pin power distribution. In this paper, the effects of particularly relevant void fraction uncertainties on reactor physics parameters have been studied for a BWR assembly of type Westinghouse SVEA-96 using the CASMO-4, HELIOS/PRESTO-2 and MCNP4C codes. The SVEA-96 geometry is characterised by the sub-division of the assembly into four different sub-bundles by means of an inner bypass with a cruciform shape. The study has covered the following issues: (a) the effects of different cross-section data libraries on the void coefficient of reactivity, for a wide range of void fractions; (b) the effects due to a heterogeneous vs. homogeneous void distribution inside the sub-bundles; and (c) the consequences of partly inserted absorber blades producing different void fractions in different sub-bundles. (author)

  15. The economics of nuclear power

    International Nuclear Information System (INIS)

    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 CO2 at baseload power plant capture CO2 at H2 plant; capture CO2 at coal-to-synfuels plant and geological storage; wind power for coal power; PV power for coal power; wind H2 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

  16. BWR AXIAL PROFILE

    International Nuclear Information System (INIS)

    The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips. Thus, accounting for axially varying burnup in criticality analyses is also referred to as accounting for the ''end effect'' reactivity. The magnitude of the reactivity change due to ''end effect'' is dependent on the initial assembly enrichment, the assembly average burnup, and the particular axial profile characterizing the burnup distribution. The set of bounding axial profiles should incorporate multiple BWR core designs and provide statistical confidence (95 percent confidence that 95 percent of the population is bound by the profile) that end nodes are conservatively represented. The profiles should also conserve the overall burnup of the fuel assembly. More background on BWR axial profiles is provided in Attachment I

  17. BWR AXIAL PROFILE

    Energy Technology Data Exchange (ETDEWEB)

    J. Huffer

    2004-09-28

    The purpose of this calculation is to develop axial profiles for estimating the axial variation in burnup of a boiling water reactor (BWR) assembly spent nuclear fuel (SNF) given the average burnup of an assembly. A discharged fuel assembly typically exhibits higher burnup in the center and lower burnup at the ends of the assembly. Criticality safety analyses taking credit for SNF burnup must account for axially varying burnup relative to calculations based on uniformly distributed assembly average burnup due to the under-burned tips. Thus, accounting for axially varying burnup in criticality analyses is also referred to as accounting for the ''end effect'' reactivity. The magnitude of the reactivity change due to ''end effect'' is dependent on the initial assembly enrichment, the assembly average burnup, and the particular axial profile characterizing the burnup distribution. The set of bounding axial profiles should incorporate multiple BWR core designs and provide statistical confidence (95 percent confidence that 95 percent of the population is bound by the profile) that end nodes are conservatively represented. The profiles should also conserve the overall burnup of the fuel assembly. More background on BWR axial profiles is provided in Attachment I.

  18. Nuclear power stations licensing

    International Nuclear Information System (INIS)

    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 n0 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

  19. Nuclear power: An evolving scenario

    International Nuclear Information System (INIS)

    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

  20. Nuclear power development in China

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1990-01-01

    The Chinese nuclear power programme for electricity generation is in an early stage. Two nuclear power stations are under construction. One is the Qinshan nuclear power plant, a 300-mega-watt-electric (MWe) unit located in the Zhejiang Province. The plant was domestically designed and most of its equipment was manufactured in China. It is expected to be connected to the electrical grid in 1991. The other nuclear power station is being built at Daya Bay in Guangdong Province. It has two 900-MWe units purchased from foreign suppliers that are scheduled to be put into operation in 1992 and 1993. Overall, China's nuclear power programme for electricity generation has progressed very slowly in contrast to the successful experience in other areas of nuclear development over the last 30 years. Many factors have influenced the development of nuclear power, in particular the structure and development of the national economy and energy system, which is based on domestic energy resources. (author).

  1. Nuclear power and sustainable development

    International Nuclear Information System (INIS)

    Nuclear Power is a new, innovative technology for energy production, seen in the longer historic perspective. Nuclear technology has a large potential for further development and use in new applications. To achieve this potential the industry needs to develop the arguments to convince policy makers and the general public that nuclear power is a real alternative as part of a sustainable energy system. This paper examines the basic concept of sustainable development and gives a quality review of the most important factors and requirements, which have to be met to quality nuclear power as sustainable. This paper intends to demonstrate that it is not only in minimising greenhouse gas emissions that nuclear power is a sustainable technology, also with respect to land use, fuel availability waste disposal, recycling and use of limited economic resources arguments can be developed in favour of nuclear power as a long term sustainable technology. It is demonstrated that nuclear power is in all aspects a sustainable technology, which could serve in the long term with minimal environmental effects and at minimum costs to the society. And the challenge can be met. But to achieve need political leadership is needed, to support and develop the institutional and legal framework that is the basis for a stable and long-term energy policy. Industry leaders are needed as well to stand up for nuclear power, to create a new industry culture of openness and communication with the public that is necessary to get the public acceptance that we have failed to do so far. The basic facts are all in favour of nuclear power and they should be used

  2. Nuclear power and the environment

    International Nuclear Information System (INIS)

    The environmental impacts and the impacts on man are compared for nuclear power plants and solid-fossil-fuel power plants. Practical experience points to significant advantages of nuclear power facilities. While coal-fired power plants in normal operation pollute the environment up to 30% of the permissible limits, the actual exposures caused by nuclear power plants are less than one per mille of the limits given by legal regulations. Some problems are also discussed of radiation protection. It is stated that thanks to the systematic research in this field which has been carried out for nearly sixty years, the knowledge of ionizing radiation hazards is now much more profound and complex than, e.g., that of toxic chemical pollutants released from fossil-fuel power plants and from chemical plants or contained in vehicle exhaust gases. (Z.M.). 5 tabs

  3. Analysis of Heat Balance on Innovative-Simplified Nuclear Power Plant Using Multi-Stage Steam Injectors

    Science.gov (United States)

    Goto, Shoji; Ohmori, Shuichi; Mori, Michitsugu

    The total space and weight of the feedwater heaters in a nuclear power plant (NPP) can be reduced by replacing low-pressure feedwater heaters with high-efficiency steam injectors (SIs). The SI works as a direct heat exchanger between feedwater from condensers and steam extracted from turbines. It can attain pressures higher than the supplied steam pressure. The maintenance cost is lower than that of the current feedwater heater because of its simplified system without movable parts. In this paper, we explain the observed mechanisms of the SI experimentally and the analysis of the computational fluid dynamics (CFD). We then describe mainly the analysis of the heat balance and plant efficiency of the innovative-simplified NPP, which adapted to the boiling water reactor (BWR) with the high-efficiency SI. The plant efficiencies of this innovative-simplified BWR with SI are compared with those of a 1100MWe-class BWR. The SI model is adopted in the heat balance simulator as a simplified model. The results show that the plant efficiencies of the innovate-simplified BWR with SI are almost equal to those of the original BWR. They show that the plant efficiency would be slightly higher if the low-pressure steam, which is extracted from the low-pressure turbine, is used because the first-stage of the SI uses very low pressure.

  4. Environmental tests of electric cables for nuclear power plants

    International Nuclear Information System (INIS)

    The evaluation of the materials for flame retardation of cables for nuclear power plants and the tests of their environmental resistivity are reported. Several cables to meet the severe requirements for these cables have been produced for trial, which have been subjected to the simulated environment test including Loss of Coolant Accident. The results are summarized as follows: (a) the ethylene-proylene rubber-insulated, chloroprene-sheathed cable has the sufficient properties to use in BWR containment vessels, such as radiation resistance and flame resistance. (b) It is the same in the chloroprene-sheathed cable, that has glass braids on the outermost layer and around each core, and the insulation layer of the silicone rubber electrically stable but mechanically low in radiation resistivity. (c) The flame-resistant cross-linking polyethylene-insulated, low hydrochloric acid vinyl-sheathed cable is usable near but outside BWR containment vessels. (d) The flame-resistant cross-linking polyethylene-insulated, chloroprene-sheathed cable having the insulating layer of polyethylene for each core can be used in PWR containment vessels. (e) Chloroprene and polyvinyl chloride, the flame-resistant sheath materials, deteriorate owing to heat aging alone. Only the insulating layers mainly contribute to the environmental resistivity of cables. (f) The environmental conditions are severer when heat aging is carried out prior to irradiation. The influence of dose rate is rather little. (Wakatsuki, Y.)

  5. Nuclear power for economic development

    International Nuclear Information System (INIS)

    Various sources of energy available in India are discussed and it is emphatically stated that nuclear power is the only answer to the energy problem of the world and in particular of India. Advantages of atomic power over other sources of energy such as oil, hydel, coal etc. are described. Oil is still imported and petrolium consumption is required in petro-chemical industries and transportation. Hydro-electric potential available in India is limited as estimated by the erstwhile Central Water and Power Commission. As regards coal, India cannot entirely depend on this source for production of electricity since uneven distribution of the coal deposits necessitates its transportation over long distances from the mines to the points of consumption. Transportation required for nuclear fuel is almost non-existant as compared to that required for coal-fired plant, hence the generation cost is also low. Nuclear power potential, taking breeding into consideration turns out to be enormous. As regards safety, results of analysis carried out in the U.S. are given to show that safety of mining for nuclear power is much superior to that for coal-fired power plants. It is stated that there is no fear about nuclear wastes getting into water streams since they are carefully stored in underground depositories. Nuclear power program in India is described in brief. (B.G.W.)

  6. The debate on nuclear power

    International Nuclear Information System (INIS)

    The need for nuclear power is pointed out. The Study Group on Nuclear Fuel Cycles of the American Physical Society has studied the problem of waste disposal in detail and has found that geological emplacement leads to safe waste disposal. The relation between nuclear power and weapons proliferation is discussed. The problem of preventing proliferation is primarily a political problem, and the availability of nuclear power will contribute little to the potential for proliferation. However, to further reduce this contribution, it may be desirable to keep fast-breeder reactors under international control and to use only converters for national reactors. The desirable converter is one which has a high conversion ratio, probably one using the thorium cycle, 233U, and heavy water as the moderator. The nuclear debate in the United States of America is discussed. Work on physical and technical safeguards in the USA against diversion of fissile materials is mentioned. (author)

  7. Space nuclear reactor power plants

    International Nuclear Information System (INIS)

    Requirements for electrical and propulsion power for space are expected to increase dramatically in the 1980s. Nuclear power is probably the only source for some deep space missions and a major competitor for many orbital missions, especially those at geosynchronous orbit. Because of the potential requirements, a technology program on space nuclear power plant components has been initiated by the Department of Energy. The missions that are foreseen, the current power plant concept, the technology program plan, and early key results are described

  8. Nuclear Power Plant Simulation Game.

    Science.gov (United States)

    Weiss, Fran

    1979-01-01

    Presents a nuclear power plant simulation game which is designed to involve a class of 30 junior or senior high school students. Scientific, ecological, and social issues covered in the game are also presented. (HM)

  9. The politics of nuclear power

    International Nuclear Information System (INIS)

    The Long Island Lighting Company (LILCO) built the Shoreham Nuclear Power plant, on New York State's Long Island, at a cost of over $5 billion. In 1989, the United States Nuclear Regulatory Commission granted LILCO a full operating license for Shoreham. yet, that year New York State and LILCO signed an agreement under which LILCO would sell the plant to New York State for $1. new York, in turn, would dismantle Shoreham, despite great uncertainties regarding future power supplies for Long Island. The Shoreham project brought a major public utility to the brink of bankruptcy, forced the question of state versus federal control of nuclear power, and for over a decade dominated the politics of a region of 2.7 million people. This book examines how technology, economics, managements, politics, and personal commitments interacted to produce one of the most spectacular and pivotal failures of nuclear power policy in the United States

  10. The future of nuclear power

    International Nuclear Information System (INIS)

    Energy production and use will contribute to global warming through greenhouse gas emissions in the next 50 years. Although nuclear power is faced with a lot of problems to be accepted by the public, it is still a significant option for the world to meet future needs without emitting carbon dioxide (CO2) and other atmospheric pollutants. In 2002, nuclear power provided approximately 17% of world energy consumption. There is belief that worldwide electricity consumption will increase in the next few years, especially in the developing countries followed by economic growth and social progress. Official forecasts shows that there will be a mere increase of 5% in nuclear electricity worldwide by 2020. There are also predictions that electricity use may increase at 75%. These predictions require a necessity for construction of new nuclear power plants. There are only a few realistic options for reducing carbon dioxide emissions from electricity generation: Increase efficiency in electricity generation and use; Expand use of renewable energy sources such as wind, solar, biomass and geothermal; Capture carbon dioxide emissions at fossil-fuelled electric generating plants and permanently sequester the carbon; Increase use of nuclear power. In spite of the advantages that nuclear power has, it is faced with stagnation and decline today. Nuclear power is faced with four critical problems that must be successfully defeat for the large expansion of nuclear power to succeed. Those problems are cost, safety, waste and proliferation. Disapproval of nuclear power is strengthened by accidents that occurred at Three Mile Island in 1979, at Chernobyl in 1986 and by accidents at fuel cycle facilities in Japan, Russia and in the United States of America. There is also great concern about the safety and security of transportation of nuclear materials and the security of nuclear facilities from terrorist attack. The paper will provide summarized review regarding cost, safety, waste and

  11. Nuclear power - razing and creating

    International Nuclear Information System (INIS)

    In the book a studies fulfilled by the author is summarized, and issues of modern status for nuclear reactors safety; worldwide statement of nuclear power; nuclear waste disposal; radiation ecology; military polygons infrastructure conversion are considered. Works - fulfilled under scientific supervision of the author - on getting a new information about nuclear tests consequences on the Kazakhstan territory, its effect on the environment and human health, problems of determination of radiation contamination levels of the Republic's regions, suffered population rehabilitation from these tests, reimbursement of former agricultural areas after nuclear tests activity into national economy are discussed, and implementation of up-to-date technologies is given. The book is intended for a wide circle of readers, specialists, teachers, postgraduates and students and all who are interesting of nuclear power use issues for a prosperity and well-being of mankind

  12. History on foundation of Korea nuclear power

    International Nuclear Information System (INIS)

    This reports the history on foundation of Korea nuclear power from 1955 to 1980, which is divided ten chapters. The contents of this book are domestic and foreign affairs before foundation of nuclear power center, establishment of nuclear power and research center, early activity and internal conflict about nuclear power center, study for nuclear power business and commercialization of the studying ordeal over nuclear power administration and new phase, dispute for jurisdiction on nuclear power business and the process, permission for nuclear reactor, regulation and local administration, the process of deliberation and decision of reactor 3. 4 in Yonggwang, introduction of nuclear reprocessing facilities and activities for social organization.

  13. Investor perceptions of nuclear power

    International Nuclear Information System (INIS)

    Evidence is provided that investor concerns about nuclear power have recently been reflected in the common stock returns of all utilities with such facilities and have resulted in a risk premium. In particular, over the 1978-1982 period, three nuclear-related events occurred at the same time as, and therefore appear to have caused, significant drops in the market values of nuclear utilities relative to their non-nuclear counterparts. The three events were as follows: the accident at TMI, which occurred in March 1979; the realization in the summer of 1980 that an accident of the magnitude of TMI could result in cleanup costs of over $1 billion, which are not completely insurable and could therefore result in substantial losses; and the summer 1982 decision by the Tennessee Valley Authority (TVA) to cancel some if its nuclear power plant construction projects, and the Nuclear Regulatory Commission (NRC) decision to stop work on the construction of the Zimmer reactor, followed by a warning that it might close the Indian Point 2 and 3 reactors. If an individual had invested $100 in an average nuclear utility on the day before the TMI accident and reinvested all dividends, the value of this investment would have fallen by 10% relative to an identical investment in the average non-nuclear utility. The risk of investments in nuclear power versus conventional generating technologies shows nuclear power to be a relatively risky investment. However, relative to all investments, nuclear power was less risky in terms of the type of risk that would cause investors to require a premium before purchasing their securities. 6 figures, 6 tables

  14. Nuclear power and CO2

    International Nuclear Information System (INIS)

    Temperatures in the atmosphere have risen by nearly one degree in the twentieth century. To contain changes in global climate and their consequences, worldwide emissions of CO2 need to be curbed drastically in the future. Even if CO2 emissions are not taken into account, nuclear power has no economic disadvantages compared to fossil fuels. On the basis of an amount of money per ton of carbon emitted, nuclear power is cheaper than coal and, in most cases, also than natural gas. Actually, the worldwide CO2 problem and energy generation are part of the ongoing 'sustainability' debate. The following arguments, among others, used in the discussion show the sustainable character of nuclear power: - Comparison of the risks associated with major accidents for various sources of energy show nuclear power to be relatively free from hazard. - The introduction of fast breeders and other technical factors will make it possible to use nuclear fission as an important source of energy for many centuries. - The radiotoxicity of waste over very long periods of time can be influenced, for instance, by transmutation. The need to further develop CO2-free nuclear power has been recognized by many countries, among them Switzerland. The Generation IV International Forum (GIF) works towards developing a new generation of nuclear power plants by 2030. It will be the symbiosis of the new types of reactors with today's modern plants which finally will establish CO2-free nuclear fission as a sustainable cornerstone of energy generation worldwide. That nuclear power has this potential for further development must be acknowledged generally. (orig.)

  15. The economics of nuclear power

    International Nuclear Information System (INIS)

    Generating electricity from nuclear power involves a complicated chain of processes, from mining uranium ore through to managing the wastes for hundreds of thousands of years. In trying to understand the economics of nuclear power we have to consider both the individual stages and the whole system. It is possible for some individual stages to be profitable (especially when they are heavily subsidised by taxpayers) and for the whole system to be uneconomical.

  16. Robotics for nuclear power plants

    International Nuclear Information System (INIS)

    Demand for robots in nuclear power plants is increasing of late in order to reduce workers' exposure to radiations. Especially, owing to the progress of microelectronics and robotics, earnest desire is growing for the advent of intellecturized robots that perform indeterminate and complicated security work. Herein represented are the robots recently developed for nuclear power plants and the review of the present status of robotics. (author)

  17. Nuclear power to aid development

    International Nuclear Information System (INIS)

    Before nuclear power can play its full role in contributing to the development of less advanced countries, full understanding of the capital investment, fuel costs and other economic factors as well as of the place it must take in existing power programmes is essential. Some insight into the problems and prospects was gained at the symposium arranged by the Agency, and held in Istanbul in October, on 'Nuclear Energy Costs and Economic Development'. (author)

  18. Nuclear Power Development in China

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    China's nuclear power industry experienced such three stages as initiation,moderate development and active development.So far,there have been 11 nuclear power units in service in the Chinese mainland with a total installed capacity of 9 100 MW.In addition,there are 24 units being constructed or to be constructed as listed in the 11th Five-Year Plan.

  19. Nuclear power and childhood leukaemia

    Energy Technology Data Exchange (ETDEWEB)

    Grimston, M. (AEA Technology, London (UK))

    1991-06-19

    The possibility of illness caused by exposure to emissions from nuclear power plants continues to raise enormous public concern. Nowhere is this more evident than in the debate over the aetiology of childhood leukaemias. This review explores the evidence in relation to this and other diseases which are linked in the public's mind to nuclear power. The scientific evidence presented suggests that these links are more tenuous than is commonly believed. (author).

  20. Nuclear power: Issues and misunderstandings

    International Nuclear Information System (INIS)

    A sizeable sector of the public remains hesitant or opposed to the use of nuclear power. With other groups claiming nuclear power has a legitimate role in energy programs, there is a need to openly and objectively discuss the concerns limiting its acceptance: the perceived health effects, the consequences of severe accidents, and the disposal of high level waste. This paper discusses these concerns using comparisons with other energy sources. (author)

  1. Nuclear power cap opposed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-01-17

    This article is a review of litigation in Canada that challenges the country`s Nuclear Liability Act. Both parties agree that repeal of this law would raise operating costs, lead to earlier closing of older units, and reduce the likelihood of future plant construction. The suit is brought by the city of Toronto and the Energy Probe watchdog group. Comments by the plaintiffs and several Canadian nuclear utilities are offered.

  2. Nuclear power - the future

    Energy Technology Data Exchange (ETDEWEB)

    Hawley, R. (Nuclear Electric plc. (United Kingdom))

    1993-09-01

    Following the Coal Review earlier this year, the UK government took the decision to bring forward the Nuclear Review from 1994 to this year. When the nuclear element was removed from the privatisation of the UK electricity industry, decommissioning costs were perceived to be too great a burden for the private sector to bear. Four years on a more optimistic picture is beginning to emerge. (author).

  3. Space nuclear power systems

    International Nuclear Information System (INIS)

    Materials of the 19-th Symposium on Space Nuclear Energetic and Engine Units taking place in 2002, in Albuquerque, USA are reviewed. Reports on transformation of heat energy produced by nuclear reactors in electrical one are presented in the reports. Result of works on improvement as traditional (Brayton and Rankine cycles, thermoelectricity and thermionic emission), so innovation converter systems (Stirling engine, alkali metal thermal to electric converter - AMTEC, thermoacoustic engine) are represented

  4. Nuclear power: policy and prospects

    Energy Technology Data Exchange (ETDEWEB)

    Jones, P.M.S. (ed.)

    1987-01-01

    This comprehensive book covers many aspects of nuclear power. The first section is on the technical background and covers the physical principles, nuclear reactor types, the nuclear fuel cycle and the uses of nuclear energy other than to generate electricity. The next section deals with areas of public interest; radiation, safety, risks, waste management and decommissioning. Experience of nuclear power, its development, current position and future prospects in the United States of America, France, Canada, the United Kingdom, the Federal Republic of Germany, Japan, India and the developing countries is discussed in section III. The opportunities for the civil nuclear industry are considered in the next section; the present world scene, the potential possible if nuclear power is developed, the incentives for developing this method, the constraints on this development and a summary of the past, present and future of nuclear power is made. The appendices, on discounting and the case for economic growth are also included. All the chapters and the appendices are indexed separately (24 chapters in total). (U.K.).

  5. Nuclear power and sustainable development

    International Nuclear Information System (INIS)

    In Romania, the nuclear power is an element of sustainable development, being competitive, efficient and viable in the market economy. Fuel supply is ensured as nuclear fuel is manufactured in the country out of local uranium resources available in Romania. As for the environmental protection, it is known that, unlike the thermal power plants, the nuclear power plants do not release sulfur and nitrogen oxides, carbon dioxide and do not generate slag and ashes. The operation of nuclear power units does not release pollutants and, accordingly, these stations can contribute to the limitation and the abatement of environmental pollution. After seven years of Cernavoda NPP Unit 1 operation, a facility for storing low and medium level nuclear fuel wastes was built at the plant site as well as an intermediate dry storage for spent nuclear fuel whose first modules were commissioned in July 2003. They shall provide safe storage conditions for nuclear fuel wastes for many decades ahead. After Chernobyl accident in 1986, many improvements have been initiated and effected in area of both engineering solutions and plant operation practices. These have led to the increase of the nuclear safety level and, accordingly, to better production performance. (author)

  6. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    The sustainability of specific technology became the important issue in future developement perspective as the environmental issue occupies the most priority in adopting the relevant technology. This study summarizes the concepts of sustainable development and analyses the nuclear future under the pressure of sustainable development. Also, it shows the fields that need the concentrated research in nuclear power

  7. Is nuclear power safe enough

    International Nuclear Information System (INIS)

    The vice-chairman of the Nuclear Power Safety Commission presents here the background for the Commission's work. He summarises informally the conclusions reached and quotes the minority dissensions. He also criticises many of the arguments made by anti-nuclear organisations. (JIW)

  8. Nuclear power - the reason why

    International Nuclear Information System (INIS)

    The subject is covered in sections, entitled: mankind's need for energy; energy sources; energy conservation; safety; what level of safety is acceptable; the effects of nuclear accidents; the risks of nuclear power in normal operation; waste disposal; plutonium; quantity and cost; which reactor; wider issues (socio-economic aspects). (U.K.)

  9. Operate a Nuclear Power Plant.

    Science.gov (United States)

    Frimpter, Bonnie J.; And Others

    1983-01-01

    Describes classroom use of a computer program originally published in Creative Computing magazine. "The Nuclear Power Plant" (runs on Apple II with 48K memory) simulates the operating of a nuclear generating station, requiring students to make decisions as they assume the task of managing the plant. (JN)

  10. Nuclear power: the political challenge

    International Nuclear Information System (INIS)

    A brief overview of the political and economical situation and nuclear energy problems in Europe is given. The author presented his opinion on topic such as need of nuclear power, Kozloduy NPP units 1-4 shutdown, climate change , energy security, environmental problems

  11. The dangerous dream: Nuclear power

    International Nuclear Information System (INIS)

    After Chernobyl: Necessary basic knowledge and information, data on safety hazards and risks, sketches of all German nuclear power plants and brief accounts of incidents reported so far, consequences of the Chernobyl and Harrisburg accidents for man and the environment, emergency control plans. With an attached short dictionary of terms in nuclear energy. (orig./HP)

  12. Public attitudes to nuclear power

    International Nuclear Information System (INIS)

    The British public is very poorly informed about nuclear power. 55 % express concern about it, but few can explain why. Some of the reasons given are extraordinary: 37 % of the public think nuclear power causes acid rain which pollutes lakes and kills trees; 47 % think coal is a safer fuel for making electricity than nuclear; a quarter think natural radiation is less harmful than that from nuclear stations. And a very large number of people have greatly exaggerated views of the amount of radiation released from power stations and the harm that it is doing people. Also, a quarter of everyone asked thought that nuclear power stations make bombs as well as electricity. Most of these concerns come from the media, and in particular from television which has broadcast many programmes which are strongly anti-nuclear, often inaccurate, and usually sensational. Fortunately, the effect of these stories is less damaging than one might think. At present about 42 % of the adult British population are not in favour of nuclear power, so there is still a majority who are not against. About 44 % are positively in favour, and the remainder are not sure or have no view

  13. Identification of dose-reduction techniques for BWR and PWR repetitive high-dose jobs

    International Nuclear Information System (INIS)

    As a result of concern about the apparent increase in collective radiation dose to workers at nuclear power plants, this project will provide information to industry in preplanning for radiation protection during maintenance operations. This study identifies Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) repetitive jobs, and respective collective dose trends and dose reduction techniques. 3 references, 2 tables

  14. Climate change and nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    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)

  15. Real issue with nuclear power

    International Nuclear Information System (INIS)

    The voter referendums on nuclear power planned in some states can affect the energy supply and economic health of the public at large more than it affects the industry that provides nuclear power, the author states. He makes the point that those responsible for energy supplies in the U. S.--the President and all relevant Federal agencies, the majority of Congress, the national utility industry, major laboratories, universities and consulting firms, and other energy industries--all favor nuclear power. The complex U.S. energy situation is reviewed, and the hope of alternative energy sources, practice of energy conservation, and benefits of nuclear power are summarized. Specifically, the California Initiative and its three conditions which it says should dictate the future of nuclear power are reviewed. The author does not believe that the reasons that are usually given in opposing nuclear power are the real reasons. He states that ''it seems clear that the principal philosophy behind the initiatives is one of halting economic growth by striking at the energy source that would make that growth possible.'' Attention is called to the morality of nuclear power by asking where is the morality: in leaving future generations an insufficient amount of energy, limiting their abilities to solve the economic and employment problems; in squandering our finite supply of fossil fuels while ignoring nuclear fuels; in forcing the nation into further dependence on unpredictable foreign nations for its energy supply; in expecting other states to provide California with the energy that it does not want to generate itself; and in allowing an arbitrary limit on growth to be set by groups of political activists

  16. Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies

    International Nuclear Information System (INIS)

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant battery chargers, inverters and uninterruptible power supplies important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already, experienced) and aging management program activities to the more generic results and recommendations presented herein

  17. Nuclear power - the glittering prizes

    International Nuclear Information System (INIS)

    The paper on the benefits of nuclear power is based on a lecture given for the Institution of Nuclear Engineers, London, 1986. Suggestions for short term benefits include a clean environment and a cheap energy source, whereas suggestions for long term benefits include freedom from want in the world and avoidance of 'energy wars'. These benefits are discussed along with alternative energy sources, the financial savings to be saved from nuclear power, world energy wealth, depletion of world energy reserves, and risks due to radiation exposure. (UK)

  18. Nuclear power - the glittering prizes

    Energy Technology Data Exchange (ETDEWEB)

    Horton, C.C.

    The paper on the benefits of nuclear power is based on a lecture given for the Institution of Nuclear Engineers, London, 1986. Suggestions for short term benefits include a clean environment and a cheap energy source, whereas suggestions for long term benefits include freedom from want in the world and avoidance of 'energy wars'. These benefits are discussed along with alternative energy sources, the financial savings to be saved from nuclear power, world energy wealth, depletion of world energy reserves, and risks due to radiation exposure.

  19. Owners of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Hudson, C.R.; White, V.S.

    1996-11-01

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

  20. Owners of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Reid, R.L.

    2000-01-12

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of November 1999. The report is divided into sections representing different aspects of nuclear plant ownership.

  1. Nuclear power vs. solar energy

    International Nuclear Information System (INIS)

    What should a long-term energy policy strategy look like. Nuclear power is still a controversial issue. Can solar energy be a realistic alternative. The book presents a detailed comparison of the two energy sources, showing that a combined strategy of solar energy and energy conservation is better suited to the future ecological, social and economic needs than nuclear energy. Bauerschmidt's detailed investigation, in which the advantages and drawbacks of the two alternatives are carefully weighed against each other, makes it impossible for anybody to consider nuclear power as the only feasible alternative. (orig.)

  2. Demonstration of zinc injection technique in Fugen Nuclear Power Station

    International Nuclear Information System (INIS)

    Applicability of the zinc injection technique for reducing the equivalent dose of annual inspection workers has been cleared and confirmed by several out-of-pile tests at Fugen Nuclear Power Station. A trial, which aimed at compressing the dose rate increase, was developed by BWR and was carried out in several plants from 1986. And then, regular zinc injections were started from Aug. 1999 after the start up of the 15th annual inspection. As a result of this injection, the 60Co ion concentration in reactor has been reduced by the order of about 30%, and a radioactivity reduction effect has also been confirmed. Also, the rebuild up rate of 60Co on piping surfaces has been drastically reduced from about 60% to about 12% after system decontamination. According to an analysis of the practical method, the adhesive rate coefficient of 60Co to metal oxide film is compressed to about 1/3. (author)

  3. Aging management guideline for commercial nuclear power plants-pumps

    International Nuclear Information System (INIS)

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

  4. Aging Management Guideline for commercial nuclear power plants: Electrical switchgear

    International Nuclear Information System (INIS)

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance, to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein

  5. Aging management guideline for commercial nuclear power plants-pumps

    Energy Technology Data Exchange (ETDEWEB)

    Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D. [MDC-Ogden Environmental and Energy Services, Southfield, MI (United States)

    1994-03-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  6. Nuclear power without joy

    International Nuclear Information System (INIS)

    A partial report against the peaceful application of nuclear energy without exact details of literature quotation. Escape rates from NPPs and WAAs are changed with slogans such as 'enourmously big' or 'the radioactivity escaping into the air and water an increasing extermination is threatening the peoples of the world'. The end with the words 'one of the pre-conditions is the elimination of the distinguishing between knowing and unknowing people and the exploitation of both as a privilege of the ruling persons' shows that it is not the authors' concern to show the problems of nuclear energy in an objective way but to knowingly raise emotions. This is a contribution to the nuclear controversy which makes the gap between pros and cons even bigger. (GL)

  7. Investigation of BWR [boiling water reactor] instability phenomena using RETRAN-03

    International Nuclear Information System (INIS)

    In 1988, LaSalle, a boiling water reactor (BWR)/5, experienced severe flux oscillations following a trip of both recirculation pumps. The flux oscillations were terminated by an automatic scram at 118% of rated neutron flux. As a result of this event, the U.S. Nuclear Regulatory Commission has asked the BWR utilities to develop procedural or hardware changes that will assure protection of all safety limits. The rapid growth of the oscillations at LaSalle, and the fact that previous stability analyses had predicted the plant to be very stable, emphasizes that a better understanding of this phenomenon is needed before the success of the long-term fixes can be assured. The intent of the Electric Power Research Institute's work was to use BWR transient methods to model reactor instabilities and investigate the factors that dominate this phenomenon. The one-dimensional transient code RETRAN-03 (Ref. 1) was used. The following conclusions are drawn: (1) RETRAN has demonstrated the ability to model BWR instability (nonlinear oscillations). (2) The general system behavior predicted by RETRAN in BWR stability analyses matches theoretical prediction and plant data. (3) These one-dimensional, time-domain results have increased the understanding of BWR stability phenomena and have helped optimize the long-term solutions being developed by the utilities

  8. Training Nuclear Power Specialists

    International Nuclear Information System (INIS)

    Situation of preparation of nuclear energy specialists in Lithuania is presented. Nuclear engineers are being prepared at Kaunas University of Technology. In view with decision to shut down Unit 1, the Ignalina NPP is limiting the number of new personnel to fill in vacancies. The main attention is given to the training courses for improvement skills of existing Ignalina NPP, VATESI personnel. Main topics of the training courses are listed. Information on number of the personnel who extended their knowledge and improved skills by the type of training is presented

  9. Women and nuclear power

    International Nuclear Information System (INIS)

    Surveys in most countries show, that women's attitude towards nuclear energy differ quite a bit from that of men. Why is this so and what can be done about it? The difference is that a cigarette is a familiar risk. But only few women are familiar with nuclear risks, especially radioactivity, be it scientifically or emotionally. Women in general are less inclined to technical subjects. Technical matters still are male. Technical issues are - by education and in schools - (at least in Switzerland) no female subjects. Therefore we have to change this in order to change women's attitudes towards technical subjects. How can women become more technology-oriented?

  10. Nuclear power and public opinion

    International Nuclear Information System (INIS)

    The public opinion on Nuclear Power is not favorable. A purposeful work with public perception is necessary. One way to create a positive image of the nuclear industry is to improve public radiological education. This challenge can be resolved in the close cooperation with state school and preschool education. The formation about nuclear power should be simple and symbolical. Our society can be divided into 4 parts which can be called as target groups: First group - People from the nuclear industry with special education working at nuclear facilities or related to the industry. Second group - People working in the fields connected with nuclear power. Third group - People not related to nuclear power or even with negative impression to the industry. This group is the largest and the work required is the most difficult. Fourth group - The number of this group's members is the least, but it has strong influence on public opinion. 'Greens' and a broad spectrum of ecological organizations can be included in this group. (Authors)

  11. Nuclear power bankrupts the Northwest

    International Nuclear Information System (INIS)

    The Washington Public Power Supply System's nuclear power project is discussed. The author contends that cost overruns, mismanagement, and inflation finally led to the cancellation of the 5 reactor project after more than $8 billion was spent. The need for the reactors is questioned, and the possible impact on electrical rates is discussed

  12. Providing emergency supply of nuclear power plants

    OpenAIRE

    ROZMILER, Jiří

    2013-01-01

    Work "Providing emergency power nuclear power plant" describes how solving their own consumption nuclear power plant, as emergency power supply is designed and how it should be a solution of known states of emergency, having an immediate impact on the power consumption of their own nuclear power plants. The aim of this thesis is to propose options to strengthen its own emergency power consumption of nuclear power plants, one might say-more resistant to harsh extremes, which could lead to loss...

  13. An engineer-constructor's view of nuclear power plant safety

    International Nuclear Information System (INIS)

    At SWEC we have been involved in the development of safety features of nuclear power plants ever since we served as the engineer-constructur for the first commerical nuclear power station at Shippingport, Pennsylvania, in the 1950s. Our personnel have pioneered a number of safety innovations and improvements. Among these innovations is the subatmospheric containment for pressurized water reactor (PWR) power plants. This type of containment is designed so that leakage will terminate within 1 to 2 hours of the worst postulated loss of coolant accident. Other notable contributions include first use of reinforced-concrete atmospheric containments for PWR power plants and of reinforced-concrete, vapor-suppression containments for boiling water reactor (BWR) power plants. Both concepts meet rigorous U.S. safety requirements. SWEC has performed a substantial amount of work on developing standardized plant designs and has developed standardized engineering and construction techniques and procedures. Standardization concepts are being developed in Canada, France, USSR, and Germany, as well as in the United States. The West German convoy concept, which involves developing a number of standardized plants in a common effort, has been quite successful. We believe standardization contributes to safety in a number of ways. Use of standardized designs, procedures, techniques, equipment, and methods increases efficiency and results in higher quality. Standardization also reduces the design variations with which plant operators, emergency teams, and regulatory personnel must be familiar, thus increasing operator capability, and permits specialized talents to be focused on important safety considerations. (orig./RW)

  14. Nuclear Power and Sustainable Development

    International Nuclear Information System (INIS)

    Any discussion of 21st century energy trends must take into account the global energy imbalance. Roughly 1.6 billion people still lack access to modern energy services, and few aspects of development - whether related to living standards, health care or industrial productivity - can take place without the requisite supply of energy. As we look to the century before us, the growth in energy demand will be substantial, and 'connecting the unconnected' will be a key to progress. Another challenge will be sustainability. How can we meet these growing energy needs without creating negative side effects that could compromise the living environment of future generations? Nuclear power is not a 'fix-all' option. It is a choice that has a place among the mix of solutions, and expectations for the expanding use of nuclear power are rising. In addition to the growth in demand, these expectations are driven by energy security concerns, nuclear power's low greenhouse gas emissions, and the sustained strong performance of nuclear plants. Each country must make its own energy choices; one size does not fit all. But for those countries interested in making nuclear power part of their sustainable development strategies, it is important that the nuclear power option be kept open and accessible

  15. Climate change and nuclear power

    International Nuclear Information System (INIS)

    Today, the nuclear power industry is an established, experienced industry that generates one sixth of the world's electricity, one fifth of the USA's, and almost one third of Western Europe's. The recent SIRES scenarios highlight that, even in the absence of policies to limit GHG emissions, meeting the energy needs and economic development aspirations of the 21st century will require the full range of energy supply options available including nuclear power. None of the world's available energy supplies should be excluded. Fossil, nuclear, and renewable resources are all large, and the future evolution of the world's energy system is less likely to be determined by resource constraints than by active choices made by governments, the private sector, and individuals. Nuclear power has the potential to fill a substantial part of the gap between where emissions from Annex I countries are now headed, and where they are required to be in 2008-2012 according to the Kyoto Protocol. If the CDM is taken into account, nuclear power's potential approximately doubles. And if the path charted by the Kyoto Protocol is to continue beyond the 2008-2012 commitment window, the potential importance of nuclear power only grows. The best chance for sustainable development - for meeting the needs of the present generation without compromising the ability of future generations to meet their needs - lies in allowing all energy supply options to compete, improve, and contribute on a level playing field directly on the basis of cost-effectiveness, environmental protection, and safety

  16. Nuclear power infrastructure and planning

    International Nuclear Information System (INIS)

    There are several stages in the process of introducing nuclear power in a country. These include feasibility studies; technology evaluation; request for proposals and proposal evaluation; project and contracts development and financing; supply, construction, and commissioning; and finally operation. The IAEA is developing guidance directed to provide criteria for assessing the minimum infrastructure necessary for: a) a host country to consider when engaging in the implementation of nuclear power, or b) a supplier country to consider when assessing that the recipient country would be in an acceptable condition to begin the implementation of nuclear power. There are Member States that may be denied the benefits of nuclear energy if the infrastructure requirements are too large or onerous for the national economy. However if co-operation could be achieved, the infrastructure burden could be shared and economic benefits gained by several countries acting jointly. The IAEA is developing guidance on the potential for sharing of nuclear power infrastructure among countries adopting or extending nuclear power programme

  17. Sustainable development and nuclear power

    International Nuclear Information System (INIS)

    Although there is an awareness on both the technical and political levels of the advantages of nuclear power, it is not a globally favoured option in a sustainable energy future. A sizeable sector of public opinion remains hesitant or opposed to its increased use, some even to a continuation at present levels. With various groups calling for a role for nuclear power, there is a need openly and objectively to discuss the concerns that limit its acceptance: the perceived health effects, the consequences of severe accidents, the disposal of high level waste and nuclear proliferation. This brochure discusses these concerns, and also the distinct advantages of nuclear power. Extensive comparisons with other energy sources are made

  18. Nuclear power: obstacles and solutions

    International Nuclear Information System (INIS)

    Nuclear power has a history extending over more than 50 years; it has been pursued both for military power applications (primarily aircraft carrier and submarine propulsion) and for commercial power applications. Nuclear power has benefited from many hundreds of billions of dollars in research, development, design, construction, and operations expenditures, and has received substantial attention and support world-wide, having being implemented by most developed countries, including all of the G-7 countries, and several developing countries (for example, India, China, and Republic of Korea). In spite of this long history, massive development effort, and unprecedented financial commitment, nuclear power has failed to achieve commercial success, having captured less than 5% of the world's primary energy supply market. There are many factors contributing to the stagnation/decline of the commercial nuclear power business. These factors include: non competitive economics, lengthy construction schedules, large and demanding human resource requirements, safety concerns, proliferation concerns, waste management concerns, the high degree of government financial and political involvement necessary, and the incompatibility of the available nuclear power plant designs with most process heat applications due to their temperature limitations and/or large heat output. An examination of the obstacles to deployment of nuclear power plants of current design suggest a set of requirements for new nuclear power plants, which may overcome or circumvent these obstacles. These requirements include: inherent characteristics that will achieve reactor shutdown under any postulated accident condition; the removal of decay heat by natural and passive means; no safety dependence on operator actions and tolerant to operator error, and malicious or incompetent operator action; and, economic viability in relatively small unit sizes. Many innovative reactor technologies and concepts are under

  19. Public attitudes to nuclear power

    International Nuclear Information System (INIS)

    The public is influenced against nuclear power by fear of a large accident, fear of radiation, worry about nuclear waste, and by the fact that it is a symbol of the bureaucratic, impersonal aspects of industrialized society. The nuclear industry must do several things to overcome this public concern. It must be more articulate in speaking to the public in a language the public understands and not in nuclear jargon; it must be strictly accurate and truthful in all statements, and if it believes the case it is putting forward is sound, it should defend the proposal and not promise to do even more to buy off criticism. Acceptance of nuclear power will either have to wait until the energy situation is desperate, or until the industry puts enough effort into presenting and defending its case to convince all objective people

  20. Infrastructure needs for nuclear power

    International Nuclear Information System (INIS)

    Nuclear power is a significant component of electricity systems world-wide and in OECD countries as a whole it accounts for about 25% of the electricity supply. The current stagnation in nuclear power orders and the expectation of diminishing nuclear programmes in several countries might jeopardize industrial infrastructures based on nuclear activities. Questions arise as to whether special measures are needed to ensure that the nuclear option will be available when wanted and if so, who would take these measures. This paper provides at first an attempt to define what can be considered as ''structure'' and ''infrastructure'' and then a review of relevant issues related to industrial and governmental supporting infrastructure. In particular, the manpower availability and educational implications are examined

  1. Nuclear power research and development

    International Nuclear Information System (INIS)

    Research in the nuclear field must change, at least in the sense that more attention must be devoted to questions raised by non-specialists. This is necessary in order to convince society that nuclear energy can be applied safely and economically. Special attention must be paid to the prevention of accidents. There are several ways of approaching this aspect. One is the further development of the boiling-water reactor with natural circulation, such as operated by KEMA and GKN at Dodewaard. If communication with the non-specialists is improved, society will accept nuclear power, thus increasing the potential for nuclear growth throughout the world. (author)

  2. Topics in nuclear power

    Science.gov (United States)

    Budnitz, Robert J.

    2015-03-01

    The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of "significant events" since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its "lessons learned" have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come.

  3. Nuclear power: in perspective

    International Nuclear Information System (INIS)

    Dr. Agnew, former director of Los Alamos Scientific Lab., observes that modern communications have made the over-populated and less-developed countries impatient to have the energy-intensive living standards enjoyed by Europe and the US. More cartels can be expected, he feels, to give these people economic leverage unless they are supplied with cheap, available energy. He notes that all energy sources, including nuclear, have a role and must be developed. The economic and environmental impacts of nuclear energy compare favorably with other major energy sources, but the public neds to be given factual rather than sensational information about nuclear energy so that realistic comparisons can be made. Dr. Agnew points to new types of reactors for land-based facilities that can be designed and that will be safer than the water-cooled design and eliminate some risks. He also finds fuel reprocessing removing some risks, in contrast to the failing nonproliferation policy. He admonishes opponents of nuclear energy to recognize that their position has serious social and economic implications for developing countries and possibly grave political and security repercussions for the US

  4. Nuclear power plant

    International Nuclear Information System (INIS)

    The nuclear part with the negative pressure control system is installed in an underground chamber of a mountain. The containment consists of a sealing concrete layer directly sprayed to the rock and containing reinforcement inserts as well as of a consolidating concrete shell. The sealing concrete layer is combined with the rock by means of prestressed concrete tie rods. (DG)

  5. Topics in nuclear power

    International Nuclear Information System (INIS)

    The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of 'significant events' since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its 'lessons learned' have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come

  6. Topics in nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Budnitz, Robert J. [Earth Sciences Division, Lawrence Berkeley National Laboratory, Berkeley, CA 94720 (United States)

    2015-03-30

    The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of 'significant events' since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its 'lessons learned' have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come.

  7. Environmental aspects of nuclear power

    International Nuclear Information System (INIS)

    Nuclear power provides the world with an important option for generating electricity. To successfully and safely utilize this power, engineering and environmental factors should be carefully considered throughout a nuclear power plant project, especially during the planning stages. This paper discusses the major environmental aspects of a nuclear power plant project from site selection to retirement. During the site selection process, both engineering and environmental resources must be identified and evaluated. Environmental resources include areas that support agricultural or aquatic commercial activities, habitats for commercial or endangered species, population centers, transportation systems, and recreational areas. Also, during the site selection process, the potential impacts of both construction and operating activities must be considered. In addition to the area actually disturbed by construction, construction activities also affect local services, such as transportation systems, housing, school systems, and other social services. Since nuclear power plants use a 'clean fuel,' generally the most significant operating activity having a potential environmental impact is the discharge of cooling water. The potential effect of this discharge on commercial activities and sensitive habitats should be thoroughly evaluated. Lastly, the method of decommissioning can affect long-range land use planning and should therefore be considered during the planning process. With appropriate planning, nuclear power plants can be constructed and operated with minimum environmental impact. (author)

  8. Starting of nuclear power stations

    International Nuclear Information System (INIS)

    The procedure is briefly characterized of jobs in nuclear power plant start-up and the differences are pointed out from those used in conventional power generation. Pressure tests are described oriented to tightness, tests of the secondary circuit and of the individual nodes and facilities. The possibility is shown of increased efficiency of such jobs on an example of the hydraulic tests of the second unit of the Dukovany nuclear power plant where the second and the third stages were combined in the so-colled integrated hydraulic test. (Z.M.). 5 figs

  9. Pre service and inservice inspection of light water moderated nuclear power plant pressure-containing components

    International Nuclear Information System (INIS)

    The authors comment the current national (United States) and international techniques, experience and problems in the field of pre-service and in-service inspection of pressure vessels and piping of nuclear power plant reactors. They also comment the personnel qualification issue, and results obtained during inspections of components of various nuclear plant reactor vessel (BWR and PWR). They highlight and comment the major problems associated with in-service inspection: the scarcity of personnel trained and qualified for reactor system examination, the variability of procedures and data recording, and the problem of inspection personnel radiation exposure

  10. LDC nuclear power: Venezuela

    International Nuclear Information System (INIS)

    Venezuela had an aggressive nuclear program when it was under a dictatorship in the 1950s, but it is currently assuming a wait-and-see stance. The country has one small research reactor, but it may have a reactor on-line in the mid-1990s. CONADIN, Venezuela's nuclear energy planning agency, has commissioned feasibility studies and requested proposals for a reactor-siting survey. A recent study for the Venezuelan state oil company suggests tha a natural-uranium, gas-cooled reactor could provide process steam to extract oil from the bituminous tar sands of the Orinoco Basin. Venezuela is also exploring for uranium reserves. 23 references, 1 figure, 2 tables

  11. Church and nuclear power

    International Nuclear Information System (INIS)

    This position paper is the result of talks conducted by natural scientists and engineers with ethical specialists and theologists in 1980/81. To cope with the difficulty of the authenticity of ecclesiastical statements, the report was worked out as an independent paper giving not only a negative response to past ecclesiastical pronouncements but taking a stand regarding nuclear energy from the point of view of the natural sciences respectively technology. As it was not possible to reach agreement in all points, the partners in the talks consider this position paper to be a statement on nuclear energy by natural scientists and engineers grown from the discussions with ethical specialists and theologists. The partners in the discussions agree that this can only be a first step. (orig./HSCH)

  12. Nuclear power and health

    International Nuclear Information System (INIS)

    In the focus of the nuclear energy discussion in the FRG was and still is the damaging effect of ionizing radiation on the life and health of man which, in the population, is an indistinct fear. In the foreground mostly is the possible exposure to radiation of personnel and people living near nuclear plants. The booklet contains statements, often also from the medical sector, and their analysis by radiation biologists and physicists. In order to verify these statement, an extensive bibliography is given. For argumentation important tables and illustrations were taken from the sources and appended to the individual analyses. For quick reference to interesting topics an extensive index was set up. It is the aim of the booklet to provide physicians and those interested with information and with the possibility of weighing arguments, evaluating scientific results and forming individual opinions. (orig./HSCH)

  13. Nuclear power and hydrogen

    International Nuclear Information System (INIS)

    Ontario has been using CANDU reactors to produce electricity since 1962. The province does not have an electricity shortage, but it does have a shortage of liquid fuels. The government of Ontario is encouraging research into the production of hydrogen using electricity generated by a dedicated nuclear plant, and the safe and economical use of hydrogen both in the production of synthetic petroleum fuels and as a fuel in its own right

  14. Nuclear power generation system

    International Nuclear Information System (INIS)

    Purpose: To reduce radioactivity exposure by optionally and surely controlling the concentration ratio of nickel-iron in a feedwater system, and reducing the ionic radioactivity concentration in the nuclear reactor and substituting radioactive sources in nuclear reactor pipeways. Constitution: Condensated water in a nuclear reactor is caused to flow from a condensate pump through a reactor condensate-feed water system and condensate pipeways into hollow thread membrane filters. Most of iron oxide in the condensate is captured by the hollow thread membrane filters. When the filters are back-washed, the captured iron oxide is stored passing through an iron receiving tank of a feedwater iron injection device. The iron oxide thus stored is passed through a desalter, removed with ionic impurities and then stored as iron oxide equivalent with leak ion oxide in the condensate desalter into an iron storage tank. On the other hand, necessary ion oxide is injected into feed water by adjusting the opening degree of an iron injection controlling valve by a feedwater sampling device such that the concentration ratio of nickel-iron in the reactor feedwater system is maintained at 1/2. (Ikeda, J.)

  15. Nuclear power : exploding the myths

    International Nuclear Information System (INIS)

    A critique of the Canadian government's unaccountability in terms of nuclear decisions was presented. The federal government has spent more than $13 billion building dozens of nuclear facilities, and spreading Canadian nuclear technology to India, Pakistan, Taiwan, Korea, Argentina and Romania. The author argued that this was done without any public consultation or public debate. In addition, the federal government announced in 1996 that it will play a role in nuclear disarmament and would accept tonnes of leftover plutonium from dismantled nuclear warheads to be used as fuel in CANDU reactors. Samples of weapons plutonium fuels from Russia and the United States are currently being tested in a reactor at Chalk River, Ontario. In addition, China received a $1.5 billion loan from the Treasury of Canada to help finance a CANDU reactor. It was the largest loan in Canadian history, yet had no procedure to obtain taxpayer's permission. Turkey was promised an equal amount if it would build a CANDU reactor. Despite this activity, the nuclear industry is in a dying state. No reactors have been ordered in North America for the past 25 years and there are no future prospects. Nuclear expansion has also ground to a halt in western Europe, Germany, Sweden, Switzerland and France. The author discussed the association of nuclear energy with nuclear weapons and dispelled the myth that the nuclear energy programs have nothing to do with nuclear weapons. He also dispelled the myth that plutonium extracted from dismantled warheads can be destroyed by burning it as fuel in civilian reactors. The author emphasized that nuclear warheads are rendered useless when their plutonium cores are removed, but there is no method for destroying the plutonium, which constitutes a serious danger. The third myth which he dispelled was that nuclear power can significantly reduce greenhouse gas emissions. Studies show that each dollar invested in energy efficiency saves 5 to 7 times as much carbon

  16. The abuse of nuclear power

    International Nuclear Information System (INIS)

    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. (U.K.)

  17. World nuclear power plant capacity

    International Nuclear Information System (INIS)

    This report provides the background information for statistics and analysis developed by NUKEM in its monthly Market Report on the Nuclear Fuel Cycle. The assessments in this Special Report are based on the continuous review of individual nuclear power plant projects. This Special Report begins with tables summarizing a variety of nuclear power generating capacity statistics for 1990. It continues with a brief review of the year's major events regarding each country's nuclear power program. The standard NUKEM Market Report tables on nuclear plant capacity are given on pages 24 and 25. Owing to space limitations, the first year shown is 1988. Please refer to previous Special Reports for data covering earlier years. Detailed tables for each country list all existing plants as well as those expected by NUKEM to be in commercial operation by the end of 2005. An Appendix containing a list of abbreviations can be found starting on page 56. Only nuclear power plants intended for civilian use are included in this Special Report. Reactor lifetimes are assumed to be 35 years for all light water reactors and 30 years for all other reactor types, unless other data or definite decommissioning dates have been published by the operators. (orig./UA)

  18. Safety partnership in nuclear power

    International Nuclear Information System (INIS)

    Nuclear safety is composed of responsible plant design and, in addition, of a human component comprising the technical skills of the personnel and adequate administrative structures, especially in the form of independent supervisory organizations, summed up under the concept of 'safety culture'. This component becomes the more important, the smaller the product of design reserves and the degree of plant automation. The exchange of experience therefore is a key factor within the concept of safety culture. Realizing this need, the operators of 439 nuclear generating units worldwide have joined forces at various different levels in the best possible way under the prevailing circumstances in order to profit from each other's experience. The background of experience of nuclear power plant operators worldwide approaches the mark of 10,000 years of reactor operation. This helps to minimize further the residual risk associated with the civilian use of nuclear power. Numerous threshold countries have recognized the opportunities offered by nuclear power and, weighing the pros and cons, are pursuing a constructive and expansive nuclear power policy. All the more important is the further development of the joint operational effort in the sense of a global safety partnership. (orig.)

  19. Nuclear power and durable development

    International Nuclear Information System (INIS)

    This paper highlights the role that the nuclear power can play in a durable development of society. From a comparative analysis of different energy sources capable to fulfil the national energy demand it turns out that for Romania the optimal alternative is nuclear power. The nuclear power proved its attributes and characteristics in ensuring durable development by: 1. the technological maturation of the CANDU system as demonstrated by the good functioning of Cernavoda NPP Unit 1; 2. optimal utilization of the uranium national resources as well as the mining industry; 3. uranium processing and nuclear fuel and heavy water manufacturing as entailed by an educational infrastructure, research and industrial development; 4. low environmental impact; 5. high professional skill of the nuclear personnel. In addition, the low cost of the energy produced by the nuclear sector, as well as the social effects, namely, a 100% utilization of industrial infrastructure and national research capacity, urges the decision makers to develop the Cernavoda NPP, to increase the weight of nuclear energy in the energy production of the country

  20. The economics of nuclear power

    International Nuclear Information System (INIS)

    The main economic concern about nuclear power reactors is their high capital cost, which currently contributes approximately 70% to the total cost of nuclear generated electricity. Nuclear capital costs are also rising rapidly -by as much as 10-14% per annum in the USA. The economics and technical aspects of the 'back-end' processes of reprocessing, waste storage and disposal and reactor decommisioning are also receiving more attention than before. In particular the cost of reprocessing spent fuel elements from the Magnox reactors has almost doubled the overall nuclear fuel costs in only 6 or 7 years. The economics of irradiated fuel transport is considered briefly first. Then the ways in which economic forces are likely to influence the future of nuclear development in general are considered. The four main factors which emerge as important are expectation about electricity, demand growth, nuclear capital and operating costs, the economics of coal-fired power stations and the degree of public opposition to nuclear power. (UK)

  1. Nuclear power and technology transfer

    International Nuclear Information System (INIS)

    For the majority of developing countries, nuclear power is yet to become a practical means of producing heat and electricity. Most of the IAEA's technical assistance to them, therefore, has consisted of the transfer of radioisotope-related nuclear science techniques. These are playing a valuable role in treating diseases, eradicating pests, augmenting agricultural production, improving the quality of food, assessing and managing water resources and increasing the efficiency of industrial products. There is hardly any field of human endeavour to which nuclear science does not have an application. Such techniques may be usefully integrated into national agricultural, water resource, health and medical, and industrial research programmes. In helping to create cadres of scientists, technicians and administrators familiar with the economic use of nuclear science and able to handle radiation safely, their application in these areas can be seen as a first step towards the eventual use of nuclear power. This is even more important for the thirty developing countries that are already operating research reactors. There is a distinction, therefore, between the transfer of nuclear power technology, at present to a dozen developing countries, and that of nuclear science techniques which have useful applications in almost all of the other developing countries, more than 120 in number

  2. Fukushima, two years later, modification requirements in nuclear power plants

    International Nuclear Information System (INIS)

    The occurred events in the nuclear power plant of Fukushima Daiichi as consequence of the strong earthquake of 9 grades in the Richter scale and the later tsunami with waves estimated in more than 14 meters high began a series of important questions about the safety of the nuclear power plants in operation and of the new designs. Firstly, have allowed to be questioned on the magnitudes and consequences of the extreme external natural events; that can put in risk the integrity of the safety barriers of a nuclear power plant when being presented in a multiple way. As consequence of the events of the Fukushima Daiichi NPP, the countries with NPPs in operation and /or construction carried out evaluations about their safety operation. They have also realized evaluations about accidents and their impact in the safety, analysis and studies too that have forced to the regulatory bodies to continue a systematic and methodical revision of their procedures and regulations, to identify the possible improvements to the safety in response to the events happened in Japan; everything has taken it to determine the necessity to incorporate additional requirements to the nuclear power plants to mitigate events Beyond the Design Base. Due to Mexico has the nuclear power plant of Laguna Verde, with two units of BWR-5 type with contention Mark III, some the modifications can be applicable to these units to administrate and/or to mitigate the consequences of the possible occurrence of an accident Beyond the Design Base and that could generate a severe accident. In this work an exposition is presented on the modification requirements to confront external natural events Beyond the Design Base, and its application in our country. (Author)

  3. Nuclear power data; Kernenergie in Zahlen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-05-15

    The report ''nuclear power data'' includes data on the following issues: nuclear power plants in Germany including their operational characteristics, gross data on electricity generation in Germany, primary energy consumption in Germany, nuclear power plants worldwide, top ten nuclear power plants worldwide with respect to electricity generation in 2012.

  4. Development of a computer program of fast calculation for the pre design of advanced nuclear fuel 10 x 10 for BWR type reactors; Desarrollo de un program de computo de calculo rapido para el prediseno de celdas de combustible nuclear avanzado 10 x 10 para reactores de agua en ebullicion

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Montes, J.L.; Ortiz, J.J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: mrpc@nuclear.inin.mx

    2005-07-01

    In the National Institute of Nuclear Research (ININ) a methodology is developed to optimize the design of cells 10x10 of assemble fuels for reactors of water in boil or BWR. It was proposed a lineal calculation formula based on a coefficients matrix (of the change reason of the relative power due to changes in the enrichment of U-235) for estimate the relative powers by pin of a cell. With this it was developed the computer program of fast calculation named PreDiCeldas. The one which by means of a simple search algorithm allows to minimize the relative power peak maximum of cell or LPPF. This is achieved varying the distribution of U-235 inside the cell, maintaining in turn fixed its average enrichment. The accuracy in the estimation of the relative powers for pin is of the order from 1.9% when comparing it with results of the 'best estimate' HELIOS code. With the PreDiCeldas it was possible, at one minimum time of calculation, to re-design a reference cell diminishing the LPPF, to the beginning of the life, of 1.44 to a value of 1.31. With the cell design with low LPPF is sought to even design cycles but extensive that those reached at the moment in the BWR of the Laguna Verde Central. (Author)

  5. Nuclear power plant

    International Nuclear Information System (INIS)

    A modular design for an internal heat exchanger for a power reactor with separate primary and secondary cooling circuits, eg. a PWR, is described. The purpose of the design is to reduce the thermal stresses in the feed water system by a special arrangement of this. (JIW)

  6. Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

    International Nuclear Information System (INIS)

    Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

  7. Nuclear power generation incorporating modern power system practice

    CERN Document Server

    Myerscough, PB

    1992-01-01

    Nuclear power generation has undergone major expansion and developments in recent years; this third edition contains much revised material in presenting the state-of-the-art of nuclear power station designs currently in operation throughout the world. The volume covers nuclear physics and basic technology, nuclear station design, nuclear station operation, and nuclear safety. Each chapter is independent but with the necessary technical overlap to provide a complete work on the safe and economic design and operation of nuclear power stations.

  8. Elections: nuclear power confirmed

    International Nuclear Information System (INIS)

    2007 was an election year in France and the presidential campaign was an opportunity to bring in the debate a lot of topics, it appears that this year sustainable development was a concern shared by a lot of politicians. Candidate Sarkozy said that nuclear energy is consistent with the preservation of the environment and must be an essential part of the energy mix. He compelled himself to pursue the construction of the EPR reactor on the Flamanville site and to organize as soon as possible a large debate on all the topics involved in sustainable development. (A.C.)

  9. Judith Perera: 'Nuclear Power in Europe'-A review

    International Nuclear Information System (INIS)

    The book published by Financial Time Energy, London 1999, presents the history of nuclear power and its current status in both Eastern and Western Europe. The book extends on 370 pages and is structured in 8 chapters, annexes, a glossary of terms and references. Romanian nuclear power is represented by the Cernavoda NPP Unit 1 commissioned in December 1996. Till September 1999 the production of Cernavoda NPP amounted up to 15,271 TWh with a internal consumption lower than 8%, which covered 10-14% of the total electric energy demand of Romania, at a 12 to 14 USD/MWh production cost. The statistical data show that: - with the highest nuclear energy quota appears US, namely with 28.1% of world nuclear power production; - in a classification on countries, Lithuania and France appear on the first place, namely with 77.2% and 75.8%, respectively, as share of nuclear energy in the total national energy production. A review of the reactor types mostly used world wide show that the PWR is the most used technology in France, Japan, USA and several other countries. The chapter two presents the performances of different reactor types among which AGR, BWR and PWR, the load factor of which appears to be the highest. The problems of fuel cycles, fuel conversion, enrichment and production are treated in Chapter 3. The following chapter presents the economic aspects of nuclear power, the energy costs being a pro in the public debates on the future of nuclear energy. A detailed analysis on the environmental impact of nuclear power production is given in Chapter 6. The situation of nuclear sector throughout Europe is shown in the following chapter while the last one is devoted to the main European power companies implied in the nuclear industry. In conclusion, the prospects of nuclear energy in Europe are reviewed by taking into account factors like: public acceptance, costs, competition, waste management, fuel market, safety environmental issues, in-service life, personnel

  10. 2011 nuclear power world report

    International Nuclear Information System (INIS)

    At the end of 2011, 437 nuclear power plants were available for energy supply in 31 countries of the world. This are 6 plants less than at the end of 2010. The aggregate gross power of the plants amounted to approx. 389,367 MWe, the aggregate net power, to 369,371 MWe. This capacity numbers are also less than one year before (gross: 396,118 MWe, net: 375,947 MWe). Seven units were commissioned in 2011; 3 units in China and one unit in the Iran, the Rep. Korea, Pakistan and Russia each. Thirteen units were shut down permanently in 2011 or finished power production; 8 units in Germany, 4 units in Japan and 1 unit in the United Kingdom. The 8 units in Germany were forced to stop electricity production by political decisions. The 4 units in Japan have been destroyed by the effects of the March 11 Tsunami. The shut down in the United Kingdom was planned due to the operational age of the reactor. 63 nuclear generating units were under construction in late 2011 in 14 countries with an aggregate gross power of approx. 64,706 MWe. Worldwide, some 90 new nuclear power plants are in the concrete project design, planning, and licensing phases; in some of these cases license applications have been submitted or contracts have already been signed. Some 120 further projects are planned. Net electricity generation in nuclear power plants worldwide in 2011 achieved another reasonable ranking level of approx. 2,497.1 billion kWh (2010: approx. 2,627.5 billion kWh). Since the first generation of electricity in a nuclear power plant in the EBR-I fast breeder (USA) on December 20, 1951, cumulated net production has reached approx. 65,600 billion kWh, and operating experience has grown to some 14,750 reactor years. (orig.)

  11. Nuclear power world report 2013

    International Nuclear Information System (INIS)

    At the end of 2013, 435 nuclear power plants were available for energy supply in 31 countries of the world. This means that the number decreased by 2 units compared to the previous year's number on 31 December 2012. The aggregate gross power of the plants amounted to approx. 398,861 MWe, the aggregate net power, to 378,070 MWe (gross: 392,793 MWe, net: 372,572 MWe, new data base as of 2013: nameplate capacities). Four units were commissioned in 2014; three units in China and one in India. Eight units were shut down permanently in 2013; 2 units in Japan, and four units in the USA. Two units in Canada were declared permanently shut-down after a long-term shutdown. 70 nuclear generating units - 2 more than at the end of 2012 - were under construction in late 2013 in 15 countries with an aggregate gross power of approx. 73,814 MWe and net power of approx. 69,279 MWe. Six new projects have been started in 2013 in four countries (Belarus, China, the Republic of Korea, and the United Arab Emirates). Worldwide, some 125 new nuclear power plants are in the concrete project design, planning, and licensing phases; in some of these cases license applications have been submitted or contracts have already been signed. Some 100 further projects are planned. Net electricity generation in nuclear power plants worldwide in 2013 achieved a level of approx. 2,364.15 billion (109) kWh (2012: approx. 2,350.80 billion kWh). Since the first generation of electricity in a nuclear power plant in the EBR-I fast breeder (USA) on December 20, 1951, cumulated net production has reached approx. 70,310 billion kWh, and operating experience has grown to some 15,400 reactor years. (orig.)

  12. Current status of nuclear power

    International Nuclear Information System (INIS)

    The public is aware of nuclear plants that are in serious financial trouble, but hears little about the 84 plants that operate quietly to reduce US dependence on oil. There are 25 countries producing nuclear power and nine more will join them in this decade, with the US producing about one-third of the 180 million kW generated worldwide. Public opposition and economic recession over the past 10 years have caused utilities to cancel or postpone some plant construction, but the overall financial condition of utilities is improving even though electric rates must go up to recover the capital and other fixed costs of new plants. Other countries proceeded with their nuclear programs, and will benefit from the inflation-resistance and potential for cost improvement that nuclear power offers. Utilities are concerned that underestimating the growth in demand could cause a shortfall in supply unless regulatory and legislative uncertainty can be eased

  13. Nuclear power plant with pressure vessel boiling water reactor VK-300 for district heating and electricity supply

    International Nuclear Information System (INIS)

    The viability for Russia of the Boiling Water Reactor (BWR) concept has been shown by a number of feasibility studies fulfilled for perspective sites with increased energy demands. Russia has long (31 year) successful experience in operation of NPPs with the vessel-type boiling reactor VK-50 which is located in the city of Dimitrovgrad. Taking into account the large Russian district heating market, it is expedient to apply this concept (BWR) not only for electricity supply, but also for district heating. This is a way to increase of nuclear power plant competitiveness along with good safety performance. The safety and protection of nuclear heat customer is guaranteed by reliable technical means which are well checked at Russian nuclear sites. (author)

  14. Nuclear Power Project in Thailand

    International Nuclear Information System (INIS)

    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

  15. Financing nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Much is at stake in developing a financial strategy for decommissioning nuclear power plants. Since decommissioning experience is limited to relatively small reactors, will the costs associated with larger reactors be significantly higher. Certainly the decommissioning issue intersects with other critical issues that will help to determine the future of commercial nuclear power in the US. The author examines briefly the basic concepts and terms related to decommissioning expenses, namely: (1) segregated fund; (2) non-segregated fund; (3) external method; and (4) internal method. He concludes that state regulatory commissions have turned increasingly to the external funding method because of increasing costs and related problems associated with nuclear power, changing conditions and uncertainties concerned with utility restructuring, and recent changes in federal tax laws related to decommissioning. Further, this trend is likely to continue if financial assurance remains a primary concern of regulators to protect this public interest

  16. TVA's nuclear power plant experience

    International Nuclear Information System (INIS)

    This paper reviews TVA's nuclear power plant design and construction experience in terms of schedule and capital costs. The completed plant in commercial operation at Browns Ferry and six additional plants currently under construction represent the nation's largest single commitment to nuclear power and an ultimate investment of $12 billion by 1986. The presentation is made in three separate phases. Phase one will recapitulate the status of the nuclear power industry in 1966 and set forth the assumptions used for estimating capital costs and projecting project schedules for the first TVA units. Phase two describes what happened to the program in the hectic early 1979's in terms of expansion of scope (particularly for safety features), the dramatic increase in regulatory requirements, vendor problems, stretchout of project schedules, and unprecedented inflation. Phase three addresses the assumptions used today in estimating schedules and plant costs for the next ten-year period

  17. The benefits of nuclear power

    International Nuclear Information System (INIS)

    The object of the article is to indicate in fairly general terms the nature and magnitude of the benefits of nuclear power. The paper argues that significant economic gains have been obtained and that investment in civil nuclear development has fully justified itself. The justification for these claims is discussed under the topic headings: scale of the industry and world fuel savings, environment, health, fuel prices, United Kingdom benefits, generation costs, security of fuel supply, and the third world. (U.K.)

  18. American acceptance of nuclear power

    International Nuclear Information System (INIS)

    The characteristic adventurous spirit that built American technology will eventually lead to American acceptance of nuclear power unless an overpowering loss of nerve causes us to reject both nuclear technology and world leadership. The acceptance of new technology by society has always been accompanied by activist opposition to industralization. To resolve the debate between environmental and exploitive extremists, we must accept with humility the basic premise that human accomplishment is a finite part of nature

  19. American acceptance of nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Barrett, W.

    The characteristic adventurous spirit that built American technology will eventually lead to American acceptance of nuclear power unless an overpowering loss of nerve causes us to reject both nuclear technology and world leadership. The acceptance of new technology by society has always been accompanied by activist opposition to industralization. To resolve the debate between environmental and exploitive extremists, we must accept with humility the basic premise that human accomplishment is a finite part of nature. (DCK)

  20. Architecture of nuclear power units

    International Nuclear Information System (INIS)

    Nuclear units with circulation cooling using cooling towers are dominating points of the landscape. The individual cooling towers or pairs of cooling towers should be situated in the axes of double units and should also linearly be arranged, rhythmically in the respective zone. Examples are shown of the architectural designs of several nuclear power plants in the USA, the UK, the USSR, France, the FRG and Italy. (H.S.)