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Sample records for darlington nuclear generation

  1. Report on Darlington nuclear generating station

    International Nuclear Information System (INIS)

    1985-12-01

    The Select Committee on Energy was appointed on July 10, 1985 by the Legislative Assembly of the Province of Ontario in order to inquire into and report on Ontario Hydro affairs within ten months. Two sessions were planned the first of which was a review of the Darlington Nuclear Generating Station. Darlington is a large, 4 unit nuclear-powered electricity generating station currently under construction on the shore of Lake Ontario in the town of Newcastle. At the time the Committee met, construction had been underway for over four years. The first two units are scheduled to become operational in 1988 and 1989 with the second two scheduled to become operational in 1991 and 1992. The total estimated cost of the station is $10.895 billion of which $3.66 billion has been spent and $3.385 billion has been committed. Though the nuclear industry has been a major area of investment in Ontario over the past decade, the demand for electrical power from nuclear stations has been significantly decreased. This report focusses on the need for Darlington and public policy issues involved in planning and completing it. The Committee proposed the following recommendations: 1) The relationship between the Government of Ontario and Ontario Hydro and their individual responsibilities should be clarified. 2) An independent review of the Ontario Hydro demand/supply options should be carried out. 3) No further significant contracts for Darlington units 3 and 4 should be let for materials not required for construction during the next 6 months while the Committee studies demand and supply options

  2. Experience on environmental qualification of safety-related components for Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Yu, A.S.; Kukreti, B.M.

    1987-01-01

    The proliferation of Nuclear Power Plant safety concerns has lead to increasing attention over the Environmental Qualification (EQ) of Nuclear Power Plant Safety-Related Components to provide the assurance that the safety related equipment will meet their intended functions during normal operation and postulated accident conditions. The environmental qualification of these components is also a Licensing requirement for Darlington Nuclear Generating Station. This paper provides an overview of EQ and the experience of a pilot project, in the qualification of the Main Moderator System safety-related functions for the Darlington Nuclear Generating Station currently under construction. It addresses the various phases of qualification from the identification of the EQ Safety-Related Components List, definition of location specific service conditions (normal, adbnormal and accident), safety-related functions, Environmental Qualification Assessments and finally, an EQ system summary report for the Main Moderator System. The results of the pilot project are discussed and the methodology reviewed. The paper concludes that the EQ Program developed for Darlington Nuclear Generating Station, as applied to the qualification of the Main Moderator System, contained all the elements necessary in the qualification of safety-related equipment. The approach taken in the qualification of the Moderator safety-related equipment proves to provide a sound framework for the qualification of other safety-related components in the station

  3. Environmental assessment, proposed generating station for Darlington

    International Nuclear Information System (INIS)

    1975-04-01

    This document indicates the intention of Ontario Hydro to seek approval from the Provincial Government for its plan to construct and operate a 3400 MWe nuclear generating station at the Darlington site, west of Bowmanville. This preliminary proposal also contains the environmental assessment. The environmental section of this proposal describes and assesses the existing environment and the environmental influences which would occur due to the construction and operation of a nuclear generating station, consisting of four 850 MW units, at the Darlington site. This proposed station is similar to the Bruce GS A station presently under construction. (author)

  4. Darlington steam generator life assurance program

    International Nuclear Information System (INIS)

    Jelinski, E.; Dymarski, M.; Maruska, C.; Cartar, E.

    1995-01-01

    The Darlington Nuclear Generating Station belonging to Ontario Hydro is one of the most modern and advanced nuclear generating stations in the world. Four reactor units each generate 881 net MW, enough to provide power to a major city, and representing approximately 20% of the Ontario grid. The nuclear generating capacity in Ontario represents approximately 60% of the grid. In order to look after this major asset, many proactive preventative and predictive maintenance programs are being put in place. The steam generators are a major component in any power plant. World wide experience shows that nuclear steam generators require specialized attention to ensure reliable operation over the station life. This paper describes the Darlington steam generator life assurance program in terms of degradation identification, monitoring and management. The requirements for chemistry control, surveillance of process parameters, surveillance of inspection parameters, and the integration of preventative and predictive maintenance programs such as water lancing, chemical cleaning, RIHT monitoring, and other diagnostics to enhance our understanding of life management issues are identified and discussed. We conclude that we have advanced proactive activities to avoid and to minimize many of the problems affecting other steam generators. An effective steam generator maintenance program must expand the knowledge horizon to understand life limiting processes and to analyze and synthesize observations with theory. (author)

  5. AECB staff annual assessment of the Darlington Nuclear Generating Station for the year 1996

    International Nuclear Information System (INIS)

    1997-06-01

    The Atomic Energy Control Board is the independent federal agency that controls all nuclear activities in Canada. A major use of nuclear energy in Canada is electricity production. The AECB assesses every station's performance against legal requirements, including the conditions in the operating licence. Each station is inspected and all aspects of the station's operation and management is reviewed. This report is the AECB staff assessment of safety at the Darlington Nuclear Generating Station for 1996. Ontario Hydro operated the station in a safe manner in 1996. All four special safety systems were fully available 100 percent of the time. There were more problems that affected the safety support systems in 1996 than in the previous year

  6. Darlington NGD valve packing program

    International Nuclear Information System (INIS)

    Spence, C.G.

    1995-01-01

    Darlington NGD is a four unit CANDU 1000 nuclear generation station, located on the shores of Lake Ontario, approximately 45 miles east of Toronto. The CANDU design is a Pressurized Heavy Water Reactor (PHWR), each unit at Darlington is designed to produce 940MWe. The commissioning phase of the station was completed in the spring of 1993. (author)

  7. AECB staff annual assessment of the Darlington Nuclear Generating Station for the year 1995

    International Nuclear Information System (INIS)

    1996-06-01

    This report is the Atomic ENergy Control Board staff assessment of safety at the Darlington Nuclear Generating Station for 1995. The report is based on observations made by our staff, and on information submitted to us by Ontario Hydro. Performance was satisfactory for all four special safety systems. In 1995, Ontario Hydro complied with the regulations made under the Atomic Energy Control Act, except for two instances of non-compliance with the Transport Packaging of Radioactive Materials Regulations. Radiation doses received by Ontario Hydro station staff were below the regulatory limits. In general Ontario Hydro's maintenance program was found satisfactory. 9 tabs

  8. Review of Darlington

    International Nuclear Information System (INIS)

    1985-09-01

    This multi-part report outlines the considerations and results of technical, economic and financial analyses, and analyses of the impact on Ontario's economy associated with continuation of Ontario Hydro's Darlington nuclear generation project. In addition, it assesses and compares the effects of partial or complete cancellation of the project. The introduction to follow briefly outlines the main contents of each part of the report

  9. Fire fighting capability assessment program Darlington NGS

    International Nuclear Information System (INIS)

    1995-05-01

    This is a report on the completion of work relating to the assessment of the capability of Darlington NGS to cope with a large fire incident. This included an evaluation of an exercise scenario that would simulate a large fire incident and of their fire plans and procedures which became the subject of interim reports as part of the process of preparing for the fire fighting and rescue exercise. Finally the execution of fire plans by Darlington Nuclear Generating Station (NGS), as demonstrated by their application of human and material resources during a simulated large fire, was observed. 1 tab., 1 fig

  10. Phytotoxicology section investigation in the vicinity of the Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the Darlington Nuclear Generating Station, in October, 1989

    International Nuclear Information System (INIS)

    1991-02-01

    The Phytotoxicology Section, Air Resources Branch is a participant in the Pickering and Bruce Nuclear Contingency Plans. The Phytotoxicology Emergency Response Team is responsible for collecting vegetation samples in the event of a nuclear emergency at any of the nuclear generating stations in the province. As part of its responsibility the Phytotoxicology Section collects samples around the nuclear generating stations for comparison purposes in the event of an emergency. Because of the limited frequency of sampling, the data from the surveys are not intended to be used as part of a regulatory monitoring program. These data represent an effort by the MOE to begin to establish a data base of tritium concentrations in vegetation. The Phytotoxicology Section has carried out seven surveys in the vicinity of Ontario Hydro nuclear generating stations since 1981. Surveys were conducted for tritium in snow in the vicinity of Bruce Nuclear Power Development (BNPD), February, 1981; tritium in cell-free water of white ash in the vicinity of BNPD, September, 1981; tritium in snow in the vicinity of BNPD, March, 1982; tritium in tree sap in the vicinity of BNPD, April, 1982; tritium in tree sap in the vicinity of BNPD, April, 1984, tritium in the cell-free water of white ash in the vicinity of BNPD, September, 1985; and, tritium in cell-free water of grass in the vicinity of Pickering Nuclear Generation Station (PNGS), October 1986. In all cases a pattern of decreasing tritium levels with increasing distance from the stations was observed. In October, 1989, assessment surveys were conducted around Bruce Nuclear Power Development, the Pickering Nuclear Generating Station and the new Darlington Nuclear Generating Station (DNGS). The purpose of these surveys was to provide baseline data for tritium in cell-free water of grass at all three locations at the same time of year. As none of the reactor units at DNGS had been brought on line at the time of the survey, this data was to be

  11. Preparation and documentation of a CATHENA input file for Darlington NGS

    International Nuclear Information System (INIS)

    1989-03-01

    A CATHENA input model has been developed and documented for the heat transport system of the Darlington Nuclear Generating Station. CATHENA, an advanced two-fluid thermalhydraulic computer code, has been designed for analysis of postulated loss-of-coolant accidents (LOCA) and upset conditions in the CANDU system. This report describes the Darlington input model (or idealization), and gives representative results for a simulation of a small break at an inlet header

  12. Proposed Darlington generating station

    International Nuclear Information System (INIS)

    1975-05-01

    The proposed Darlington GS A project, consisting of four 850 MW CANDU-type reactors, is described. Construction and operation will cause environmental changes with regard to air, water, aquatic life, the site area, safety and noise, and the predicted changes are described. (E.C.B.)

  13. Simulation of Darlington shutdown and regulation systems

    International Nuclear Information System (INIS)

    1986-10-01

    This report describes the development of a simulation of the Darlington Nuclear Generating Station shutdown and regulating systems, DARSIM. The DARSIM program simulates the spatial neutron dynamics, the regulation of the reactor power, and Shutdown System 1, SDS1, and Shutdown System 2, SDS2, software. The DARSIM program operates in the interactive simulation (INSIM) program environment

  14. Steam generator waterlancing at Darlington NGS (system development and field application)

    International Nuclear Information System (INIS)

    Seppala, D.; Malaugh, J.; Kiisel, E.; Kamler, F.

    1996-01-01

    From the initial steam generator (SG) inspections at Darlington Nuclear Generating Station (DNGS), the authors know that the sludge accumulations on the secondary side tubesheets have been minimal. DNGS is a fairly new station but the experience at the older Ontario Hydro plants have shown that significant accumulations will happen. A pro-active strategy has been adopted for maintaining SGs that will minimize corrosion product accumulation and the potential for component degradation. During the four year planned Unit maintenance outages, SGs will be inspected and waterlanced using a waterlance system designed and built by Babcock and Wilcox International. This automated state-of-the-art system also allows fully recorded inspections of the tubesheet/first half-lattice supports. Some of the key elements covered include results of the initial field application (May, 1995), system development and design, system qualification, cleaning performance, and lessons learned for future outages

  15. GRA/RIAM model development at Darlington Nuclear

    International Nuclear Information System (INIS)

    Plourde, J.; Parmar, R.

    2006-01-01

    In 2004, the Darlington Nuclear (DN) Plant of Ontario Power Generation (OPG) undertook a project, in partnership with Nuclear Safety Solutions (NSS) Limited, to develop Risk-Informed Asset Management (RIAM) and Generation Risk Assessment (GRA) models. The models are intended to optimize plant decision-making. The objective of this paper is to present the scope of the project, the methodology employed, the results and the potential applications. DN has recognized the strategic importance of RIAM in the plant decision-making process and has begun its implementation. The required work was split into three phases. Phase 1 involved industry benchmarking, along with collection and review of the industry literature such as EPRI publications and other relevant papers. Based on the review, a description of the requirements to produce a prototype RIAM model was developed. Phase 2 consisted of the development of prototype RIAM and GRA models. Phase 3, currently underway, consists of the work required to translate the prototype models into an operational decision-making tool. RIAM and GRA are relatively new concepts hence the related methodology and the tools are still evolving. NSS has tailored the available methodology to suit the needs of the DN plant. Draft EPRI guides on GRA/RIAM were used in developing DN specific methodology. The details are provided in the paper. At DN, RIAM is expected to support business decisions by facilitating the assessment of risks associated with projects, programs and business case alternatives. These applications are further discussed in the paper. (author)

  16. Newly discovered geological features and their potential impact on Darlington and Pickering

    International Nuclear Information System (INIS)

    Wallach, J.L.

    1990-01-01

    Newly available information reveals the presence of a prominent north-northeast oriented aeromagnetic lineament and east-northeast trending, linear patterns in young sediments on the bottom of Lake Ontario. The magnetic lineament, named the Niagara-Pickering Magnetic Lineament, passes practically beneath the Pickering Nuclear Generating Station (8x1600 MW reactors), and about 30 km west of the Darlington Nuclear Generating Station (4x2800 MW reactors). Magnetic data suggest that the Niagara-Pickering Magnetic Lineament may be the signature of a fault and may connect with the Akron Magnetic Boundary in Ohio, with which several earthquakes appear to be associated. Geological data lend support to the fault hypothesis. A north-northwest trending belt of earthquake epicenters, which includes the Lockport, NY earthquake (est M=5.0) and the Attica, NY earthquake (M=5.8), lies just east of, and parallels, the entire length of Georgian Bay en route to Attica, New York. The proximity and parallelism of the Georgian Bay Linear Zone to this belt of earthquake epicenters implies that the Georgian Bay Linear Zone may be tectonically active. The Georgian Bay Linear Zone and the Niagara-Pickering Magnetic Lineament appear to intersect very near Pickering and within about 30 km from Darlington. This, combined with evidence of high horizontal stresses in the area and the implication that both lineaments may be seismically active, suggests that many of the ingredients necessary for an earthquake of at least M=5.0 to M=6.25 exist near both Darlington and Pickering. Therefore, it is necessary that the Niagara-Pickering Magnetic Lineament, the Georgian Bay Linear Zone and the other newly discovered structural features be properly evaluated in order to determine whether or not the current Design Basis Seismic Ground Motions for Darlington and Pickering are adequate

  17. The J-resistance curve Leak-before-Break test program on material for the Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Mukherjee, B.

    1988-01-01

    The Darlington Leak-Before-Break (DLBB) approach has been developed for large diameter (21, 22, 24 inch) SA106B heat transport (HT) piping and SA105 fittings as a design alternative to pipewhip restraints and in recognition of the questionable benefits of providing such restraints. Ontario Hydro's DLBB approach is based on the elastic plastic fracture mechanics method. In this test program, J-resistance curves were determined from actual pipe heats that were used in the construction of the Darlington heat transport systems (Units 1 and 2). Test blocks were prepared using four different welding procedures for nuclear Class I piping. The test program was designed to take into account the effect of various factors such as test temperature, crack plane orientation, welding effects, etc., which have influence on fracture properties. A total of 91 tests were conducted. An acceptable lower bound J-resistance curve for the piping steels was obtained by machining maximum thickness specimens from the pipes and by testing side grooved compact tension specimens. Test results showed that all pipes, welds and heat-affected zone materials within the scope of the DLBB program exhibited uppershelf toughness behaviour. All specimens showed high crack initiation toughness Jsub(lc), rising J-resistance curve and stable and ductile crack extension. Toughness of product forms depended on the direction of crack extension (circumferential versus axial crack orientation). Toughness of DLBB welds and parent materials at 250 0 C was lower than that at 20 0 C. (author)

  18. Application of best estimate and uncertainty safety analysis methodology to loss of flow events at Ontario's Power Generation's Darlington Nuclear Generating Station

    International Nuclear Information System (INIS)

    Huget, R.G.; Lau, D.K.; Luxat, J.C.

    2001-01-01

    Ontario Power Generation (OPG) is currently developing a new safety analysis methodology based on best estimate and uncertainty (BEAU) analysis. The framework and elements of the new safety analysis methodology are defined. The evolution of safety analysis technology at OPG has been thoroughly documented. Over the years, the use of conservative limiting assumptions in OPG safety analyses has led to gradual erosion of predicted safety margins. The main purpose of the new methodology is to provide a more realistic quantification of safety margins within a probabilistic framework, using best estimate results, with an integrated accounting of the underlying uncertainties. Another objective of the new methodology is to provide a cost-effective means for on-going safety analysis support of OPG's nuclear generating stations. Discovery issues and plant aging effects require that the safety analyses be periodically revised and, in the past, the cost of reanalysis at OPG has been significant. As OPG enters the new competitive marketplace for electricity, there is a strong need to conduct safety analysis in a less cumbersome manner. This paper presents the results of the first licensing application of the new methodology in support of planned design modifications to the shutdown systems (SDSs) at Darlington Nuclear Generating Station (NGS). The design modifications restore dual trip parameter coverage over the full range of reactor power for certain postulated loss-of-flow (LOF) events. The application of BEAU analysis to the single heat transport pump trip event provides a realistic estimation of the safety margins for the primary and backup trip parameters. These margins are significantly larger than those predicted by conventional limit of the operating envelope (LOE) analysis techniques. (author)

  19. Darlington tritium removal facility and station upgrading plant dynamic process simulation

    International Nuclear Information System (INIS)

    Busigin, A.; Williams, G. I. D.; Wong, T. C. W.; Kulczynski, D.; Reid, A.

    2008-01-01

    Ontario Power Generation Nuclear (OPGN) has a 4 x 880 MWe CANDU nuclear station at its Darlington Nuclear Div. located in Bowmanville. The station has been operating a Tritium Removal Facility (TRF) and a D 2 O station Upgrading Plant (SUP) since 1989. Both facilities were designed with a Distributed Control System (DCS) and programmable logic controllers (PLC) for process control. This control system was replaced with a DCS only, in 1998. A dynamic plant simulator was developed for the Darlington TRF (DTRF) and the SUP, as part of the computer control system replacement. The simulator was used to test the new software, required to eliminate the PLCs. The simulator is now used for operator training and testing of process control software changes prior to field installation. Dynamic simulation will be essential for the ITER isotope separation system, where the process is more dynamic than the relatively steady-state DTRF process. This paper describes the development and application of the DTRF and SUP dynamic simulator, its benefits, architecture, and the operational experience with the simulator. (authors)

  20. MOV predictive maintenance program at Darlington NGS

    International Nuclear Information System (INIS)

    Morrison, J.F.

    1992-01-01

    This paper details the Motor Operated Valve (MOV) Predictive Maintenance program at Darlington Nuclear Generating Station. The program encompasses the use of diagnostics tooling in conjunction with more standard maintenance techniques, with the goal of improving performance of MOV's. Problems encountered and solutions developed during the first two phases of this program are presented, along with proposed actions for the final trending phase of the program. This paper also touches on the preventive and corrective maintenance aspects of an overall MOV maintenance program. 6 refs., 6 tabs., 6 figs

  1. Ontario Power Generation Nuclear: results and opportunities

    International Nuclear Information System (INIS)

    Dermarkar, F.

    2006-01-01

    This paper describes the accomplishments of Ontario Power Generation (OPG) Nuclear and outlines future opportunities. OPG's mandate is to cost effectively produce electricity, while operating in a safe, open and environmentally responsible manner. OPG's nuclear production has been increasing over the past three years - partly from the addition of newly refurbished Pickering A Units 1 and 4, and partly from the increased production from Darlington and Pickering B. OPG will demonstrate its proficiency and capability in nuclear by continuing to enhance the performance and cost effectiveness of its existing operations. Its priorities are to focus on performance excellence, commercial success, openness, accountability and transparency

  2. Darlington annunciation: User information needs, current experience and improvement priorities

    International Nuclear Information System (INIS)

    Long, T.; Davey, E.C.

    1997-01-01

    The Darlington Nuclear Generating Station (DNGS) is located approximately 40 kilometers east of Toronto, Ontario on the coast of Lake Ontario. The station consists of four 935 MW(e) pressurized heavy water CANDU type units with a nominal power output of 850 MW(e) per unit. The station was designed and is operated by Ontario Hydro and provides electricity to meet the commercial, industrial and residential needs for 3 million people. Units 1 and 2 began commercial operation in 1990, followed by Unit 3 in 1991 and Unit 4 in 1992. Since commissioning in 1991, the station has continually achieved annual production of greater than 80% of capacity. At Darlington, as in most other industrial enterprises, the plant annunciation systems play a key role in supporting operations staff in supervising and controlling plant operations to achieve both safety and production objectives. This paper will summarize the information needs of operations staff for annunciation of changing plant conditions, describe the operational experience with current plant annunciation systems, discuss areas for annunciation improvement, and outline some of the initiatives being taken to improve plant annunciation in the future. (author). 8 refs, 2 figs, 1 tab

  3. Darlington annunciation: User information needs, current experience and improvement priorities

    Energy Technology Data Exchange (ETDEWEB)

    Long, T [Ontario Hydro, Toronto, ON (Canada); Davey, E C [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1997-09-01

    The Darlington Nuclear Generating Station (DNGS) is located approximately 40 kilometers east of Toronto, Ontario on the coast of Lake Ontario. The station consists of four 935 MW(e) pressurized heavy water CANDU type units with a nominal power output of 850 MW(e) per unit. The station was designed and is operated by Ontario Hydro and provides electricity to meet the commercial, industrial and residential needs for 3 million people. Units 1 and 2 began commercial operation in 1990, followed by Unit 3 in 1991 and Unit 4 in 1992. Since commissioning in 1991, the station has continually achieved annual production of greater than 80% of capacity. At Darlington, as in most other industrial enterprises, the plant annunciation systems play a key role in supporting operations staff in supervising and controlling plant operations to achieve both safety and production objectives. This paper will summarize the information needs of operations staff for annunciation of changing plant conditions, describe the operational experience with current plant annunciation systems, discuss areas for annunciation improvement, and outline some of the initiatives being taken to improve plant annunciation in the future. (author). 8 refs, 2 figs, 1 tab.

  4. Assessment of causes for degrading fuel performance at Darlington NGS

    International Nuclear Information System (INIS)

    Judah, J.; Goodchild, S.

    2013-01-01

    Fuel performance at the Darlington nuclear generating station has historically been excellent. Until recently, the majority of these few fuel defects have been attributed to fretting by heat transport system debris. The minority have been linked to manufacturing issues. Recently, Darlington has experienced an increase in the number of fuel defects. Although the defect rate remains low with respect to industry standards, this defect experience is considered to be unacceptable given current industry expectations and the OPG zero defect policy. Nine fuel defects have been discharged since 2007 from the four Darlington reactors. This represents a fuel defect rate of just 0.35 defects per year per reactor. At the time of this writing three additional defects are suspected to be in core. Although a definitive defect cause has yet to be identified, these fuel performance issues appear to be due to the coincidental degradation of manufacturing and operational factors, thereby decreasing the margins to fuel failure due to fuelling power ramps. All of the confirmed defected bundles have been long bundles and all experienced a relatively high power ramp when shifted from Position 2 to Position 6. High bundle uranium masses and low internal clearances are thought to be significant contributing factors. Bundle burnups at the time of the power ramps were low and these bundles were not identified by existing power ramp defect predictive tools. Our assessment has resulted in a number of recommendations which are designed to mitigate these adverse conditions by restoring the margins to power ramp failures. These recommendations impact broadly across a number of organizations including reactor physics, fuel design, fuel manufacturing, reactor design, inspections and PIE. (author)

  5. Infrared thermography program at Darlington NGD

    International Nuclear Information System (INIS)

    Speer, B.

    1997-01-01

    Infrared thermography is a proven predictive maintenance tool for improving equipment reliability and reducing maintenance costs. It has been identified as one of the maintenance technologies that could contribute to the reduction of OHN forced incapability factor. At Darlington NGD a program has been established by combining OHN and Nuclear Maintenance Applications Center (NMAC) operating experience. This presentation outlines the development and implementation of this program. The main points are: roles and responsibilities, equipment selection, software requirements, manpower level, inspection equipment, training and a cost/benefit review. (author)

  6. Experience gained in the production of licensable safety-critical software for Darlington NGS

    International Nuclear Information System (INIS)

    Crane, R.H.

    1992-01-01

    The Darlington Nuclear Generating Station is a new station, consisting of four 935 Mw units, built by Ontario Hydro, on the north shore of Lake Ontario, approximately 50 miles east of Toronto. In May, 1987, the first of the four units of this station was approaching the point where Ontario Hydro would be requesting a license to load fuel, and then proceed to first criticality. At this point, however, the regulatory authority, the Atomic Energy Control Board (AECB) started to show increasing concerns related to the Trip Computer Software associated with Darlington's newly-designed computerized shutdown systems. The concerns centered around whether or not the safety reliability, reviewability, and maintainability of this software could be demonstrated by Ontario Hydro or the system designer, Atomic Energy of Canada Limited (AECL). In order to back up the validity of their concerns, they hired a well-known consultant, who reviewed the code, and made recommendations concerning its design, implementation, and documentation. Considerable effort was required by Ontario Hydro and AECL in order to comply with those recommendations. This paper describes those efforts, outlines the difficulties encountered, and assesses the lessons learned from them

  7. Steam generator waterlancing at DNGS

    International Nuclear Information System (INIS)

    Seppala, D.; Malaugh, J.

    1995-01-01

    Darlington Nuclear Generating Station (DNGS) is a four 900 MW Unit nuclear station forming part of the Ontario Hydro East System. There are four identical steam generators(SGs) per reactor unit. The Darlington SGs are vertical heat exchangers with an inverted U-tube bundle in a cylindrical shell. The DNGS Nuclear Plant Life Assurance Group , a department of DNGS Engineering Services have taken a Proactive Approach to ensure long term SG integrity. Instead of waiting until the tubesheets are covered by a substantial and established hard deposit; DNGS plan to clean each steam generator's tubesheet, first half lattice tube support assembly and bottom of the thermal plate every four years. The ten year business plan provides for cleaning and inspection to be conducted on all four SGs in each unit during maintenance outages (currently scheduled for every four years)

  8. Darlington Station outage - a maintenance perspective

    International Nuclear Information System (INIS)

    Plourde, J.; Marczak, J.; Stone, M.; Myers, R.; Sutton, K.

    1997-01-01

    Ontario Hydro's Darlington Nuclear Generating Station (4x881MW(e)net) has carried out its first station outage since full commercial operation. The outage presented challenges to the organization in terms of outage planning, support, management, and safe execution within the constraints of schedule, budget and resources. This paper will focus on the success of the outage maintenance program, identifying the major work programs - a vacuum structure and containment outage, an emergency service water system outage, an emergency coolant injection system outage, intake channel inspections, low pressure service water inspections, and significant outage maintenance work on each of the four reactor units. Planning for the outage was initiated early in anticipation of this important milestone in the station's life. Detailed safety reviews - nuclear, radiation, and conventional - were conducted in support of the planned maintenance program. System lineup and work protection were provided by the Station Operator work group. Work protection permitry was initiated well in advance of the outage. Station maintenance staff resources were bolstered in support of the outage to ensure program execution could be maintained within the schedule. Training programs were in place to ensure that expectations were clear and that high standards would be maintained. Materials management issues in support of maintenance activities were given high priority to ensure no delays to the planned work. Station management review and monitoring in preparation for and during the outage ensured that staff priorities remained focused. Lessons learned from the outage execution are being formalized in maintenance procedures and outage management procedures, and shared with the nuclear community. (author)

  9. Updating of the program for simulation of Darlington shutdown and regulation systems

    International Nuclear Information System (INIS)

    1988-07-01

    This report describes the current status of the developments of a simulation of the Darlington Nuclear Generating Station shutdown and regulating systems, DARSIM done under contract to the Atomic Energy Control Board (AECB). The DARSIM program simulates the spatial neutron dynamics, the regulation of the reactor power, and shutdown system 1 and shutdown system 2 software. The DARSIM program operates in the interactive simulation program environment. DARSIM was installed on the APOLLO computer at the AECB and a version for an IBM-PC was also provided for the exclusive use of the AECB. Shutdown system software was updated to incorporate the latest revisions in the functional specifications. Additional developments have been provided to assist in the use and interpretation of the DARSIM results

  10. RTD problems at Darlington

    International Nuclear Information System (INIS)

    McAllindon, D.; Sloan, D.; Mayer, P.

    1997-01-01

    Resistance Temperature Detectors (RTDs) and their measurement circuit components have been a significant maintenance item at Darlington. Analysis of the problems has shown that RTDs and electrical penetrations (EPs) have been the largest sources of faults. A failure mechanism in which the RTD electrical resistance shifts upward was identified as a major source of RTD failures, which prompted a detailed failure investigation by Ontario Hydro Technologies (OHT). The investigation concluded that the root cause failure mechanism is chlorine contamination of the platinum wire during manufacture which resulted in surface damage to the wire and flaking of the wire surface during operation. Electrical penetrations in Darlington are of a pre-built modular design with two crimps internal to the EP. Spurious resistance in poor quality crimps in the EPs lead to errors in resistance measurement. The problem led to a complex and costly job to insert new modules in existing spare EPs. (author)

  11. Depletion calculations of adjuster rods in Darlington

    Energy Technology Data Exchange (ETDEWEB)

    Arsenault, B.; Tsang, K., E-mail: benoit.arsenault@amecfw.com, E-mail: kwok.tsang@amecfw.com [AMEC Foster Wheeler, Toronto, ON (Canada)

    2015-07-01

    This paper describes the simulation methodology and reactivity worth calculated for aged adjuster rods in the Darlington core. ORIGEN-S IST was applied to simulate the isotope transmutation process of the stainless steel and titanium adjusters. The compositions were used in DRAGON-IST to calculate the change in incremental properties of aged adjusters. Pre-simulations of the reactivity worth of the stainless steel and titanium adjusters in Darlington were performed using RFSP-IST and the results showed that the titanium adjuster rods exhibit faster reactivity-worth drop than that of stainless steel rods. (author)

  12. Dispersion, mixing and intentional ignition of hydrogen in the Darlington reactor vault

    International Nuclear Information System (INIS)

    Lee, J.H.S.; Knystautas, R.

    1989-03-01

    The present report reviews the Darlington Safety Report (DSR) which has been used as basis for decisions regarding intentional ignition in the Darlington reactor vault. The validity of the assumptions in the DSR regarding mixing of contents is assessed and possible hydrogen release scenarios, specific to the Darlington reactor vault, are examined. The combustion analysis in the DSR vent code calculations are reviewed in the light of existing state of the art information on high speed turbulent flames and transition to detonation. Limitations of the vent code, in this context, are identified and improvements recommended

  13. Universal delivery machine - design of the Bruce and Darlington heads

    International Nuclear Information System (INIS)

    Gray, M.G.; Brown, R.

    2003-01-01

    The Universal Delivery Machine (UDM) was designed and supplied to reduce the time required to perform channel inspection services. The Bruce UDM was the first to be completed followed by Pickering and Darlington. The Bruce and Darlington machines are nearly identical. Design concepts applied include a rotating, multiple tool station magazine, a rigid chain driving telescoping rams, a common drive package, and an external support frame to meet seismic qualification requirements. (author)

  14. Thermal efficiency improvements - an imperative for nuclear generating stations

    International Nuclear Information System (INIS)

    Hassanien, S.; Rouse, S.

    1997-01-01

    A one and a half percent thermal performance improvement of Ontario Hydro's operating nuclear units (Bruce B, Pickering B, and Darlington) means almost 980 GWh are available to the transmission system (assuming an 80% capacity factor). This is equivalent to the energy consumption of 34,000 electrically-heated homes in Ontario, and worth more than $39 million in revenue to Ontario Hydro Nuclear Generation. Improving nuclear plant thermal efficiency improves profitability (more GWh per unit of fuel) and competitiveness (cost of unit energy), and reduces environmental impact (less spent fuel and nuclear waste). Thermal performance will naturally decrease due to the age of the units unless corrective action is taken. Most Ontario Hydro nuclear units are ten to twenty years old. Some common causes for loss of thermal efficiency are: fouling and tube plugging of steam generators, condensers, and heat exchangers; steam leaks in the condenser due to valve wear, steam trap and drain leaks; deposition, pitting, cracking, corrosion, etc., of turbine blades; inadequate feedwater metering resulting from corrosion and deposition. This paper stresses the importance of improving the nuclear units' thermal efficiency. Ontario Hydro Nuclear has demonstrated energy savings results are achievable and affordable. Between 1994 and 1996, Nuclear reduced its energy use and improved thermal efficiency by over 430,000 MWh. Efficiency improvement is not automatic - strategies are needed to be effective. This paper suggests practical strategies to systematically improve thermal efficiency. (author)

  15. Flow-accelerated corrosion in nuclear power plants: application of CHECWORKS at Darlington

    International Nuclear Information System (INIS)

    Schefski, C.; Pietralik, J.; Dyke, T.; Lewis, M.

    1995-01-01

    CHECWORKS, a comprehensive software package for managing Flow-Accelerated Corrosion (FAC) concerns in the secondary side, was applied to supplement and improve the existing FAC program at Darlington NGS. The database created for the station contains the Heat Balance Diagram, susceptible-to FAC secondary side systems, ultrasonic inspection data, drawings and pictures. The distribution of hot pH and oxygen within the secondary side was calculated and components were ranked by wear rate. The predicted wear rates are relatively small, mainly because of the favourable water chemistry. It was demonstrated that the package is a very useful tool complementing the existing In-Service Inspection program. (author)

  16. TUF assessment of an abnormal load rejection event at Darlington NGS

    International Nuclear Information System (INIS)

    Liauw, W.K.; Liu, W.S.

    1997-01-01

    The main purpose of reactor system code development is to support plant operation and to assist in safety analysis. To illustrate the operational support activities of the TUF code, the assessment of a simple case of abnormal load rejection event at Darlington NGS is described. The main assessment of this event examines the flow conditions at the steam generators and the possible impact on the turbine. This assessment demonstrates the TUF capability in the operational support analysis for CANDU reactors. (author)

  17. Evolution of the Darlington NGS fuel handling computer systems

    International Nuclear Information System (INIS)

    Leung, V.; Crouse, B.

    1996-01-01

    The ability to improve the capabilities and reliability of digital control systems in nuclear power stations to meet changing plant and personnel requirements is a formidable challenge. Many of these systems have high quality assurance standards that must be met to ensure adequate nuclear safety. Also many of these systems contain obsolete hardware along with software that is not easily transported to newer technology computer equipment. Combining modern technology upgrades into a system of obsolete hardware components is not an easy task. Lastly, as users become more accustomed to using modern technology computer systems in other areas of the station (e.g. information systems), their expectations of the capabilities of the plant systems increase. This paper will present three areas of the Darlington NGS fuel handling computer system that have been or are in the process of being upgraded to current technology components within the framework of an existing fuel handling control system. (author). 3 figs

  18. Evolution of the Darlington NGS fuel handling computer systems

    Energy Technology Data Exchange (ETDEWEB)

    Leung, V; Crouse, B [Ontario Hydro, Bowmanville (Canada). Darlington Nuclear Generating Station

    1997-12-31

    The ability to improve the capabilities and reliability of digital control systems in nuclear power stations to meet changing plant and personnel requirements is a formidable challenge. Many of these systems have high quality assurance standards that must be met to ensure adequate nuclear safety. Also many of these systems contain obsolete hardware along with software that is not easily transported to newer technology computer equipment. Combining modern technology upgrades into a system of obsolete hardware components is not an easy task. Lastly, as users become more accustomed to using modern technology computer systems in other areas of the station (e.g. information systems), their expectations of the capabilities of the plant systems increase. This paper will present three areas of the Darlington NGS fuel handling computer system that have been or are in the process of being upgraded to current technology components within the framework of an existing fuel handling control system. (author). 3 figs.

  19. The case for new nuclear

    International Nuclear Information System (INIS)

    Luxat, J.C.

    2013-01-01

    Over a 22 year period from 1971 to 1993 a total of 20 reactor units were brought into service - an average of approximately one unit per year. Ontario Hydro constructed the four-unit Pickering A station, four units at Bruce A, four units at Pickering B, four units at Bruce B and four units at Darlington during this period. This represents a capacity of nearly 14,000 MW, as shown in Figure 1. During this period there was a large increase in industrial capacity in Ontario, particularly in manufacturing, driven in large measure by the incentives offered by low electricity prices, skilled workers and a good health care system. Subsequently in the mid-1990's the Pickering A and Bruce A units were laid up and maintenance efforts were focused on the Pickering B, Bruce B and Darlington stations. Two of the four units at Pickering A were returned to service in the early 2000's and the four units of Bruce A were returned to service with two units being refurbished. By 2010 nuclear capacity in the province had returned to 12,800 MW. The Ontario Long Term Energy Plan (LTEP) announced at the beginning of December does not include new build nuclear but does include refurbishment of the Darlington station as well as two units at Bruce A and four units at Bruce B. The six units at Pickering will be shut down by 2020. As shown in Figure 1, this will reduce the nuclear capacity from the current 12,800 MW to 8000 MW when the Pickering A and B units are removed from service in 2020 and the refurbishment of Darlington and Bruce units proceeds starting in 2016 and projected to complete by 2031. This will be the lowest nuclear generating capacity in the province since 1985. (author)

  20. Recent experience related to neutronic transients in Ontario Hydro CANDU nuclear generating stations

    International Nuclear Information System (INIS)

    Frescura, G.M.; Smith, A.J.; Lau, J.H.

    1991-01-01

    Ontario Hydro presently operates 18 CANDU reactors in the province of Ontario, Canada. All of these reactors are of the CANDU Pressurized Heavy Water design, although their design features differ somewhat reflecting the evolution that has taken place from 1971 when the first Pickering unit started operation to the present as the Darlington units are being placed in service. Over the last three years, two significant neutronic transients took place at the Pickering Nuclear Generating Station 'A' (NGS A) one of which resulted in a number of fuel failures. Both events provided valuable lessons in the areas of operational safety, fuel performance And accident analysis. The events and the lessons learned are discussed in this paper

  1. Darlington refurbishment - performance improvement programs goals and experience

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, N. [Ontario Power Generation, Toronto, ON (Canada)

    2015-07-01

    This paper discusses the refurbishment program at the Darlington site. The program focuses on safety, integrity, excellence and personnel. Worker safety and public safety are of the highest priority. Success resulted from collaborative engineering interface, collaborative front end planning, highly competent people and respectful relationship with partners and regulators.

  2. Control valve friction operational experience at Darlington NGD

    International Nuclear Information System (INIS)

    Speer, B.

    1995-01-01

    Proper installation of valve packing is an important part of ensuring that control valves operate as intended. Darlington NGD has developed a Valve Packing Program. This program combined with valve diagnostics has enabled the station to ensure that the operability of control valves is maintained after repacking. This paper outlines the process that is used for this. (author)

  3. Darlington up and running

    International Nuclear Information System (INIS)

    Show, Don

    1993-01-01

    We've built some of the largest and most successful generating stations in the world. Nonetheless, we cannot take our knowledge and understanding of the technology for granted. Although, I do believe that we are getting better, building safer, more efficient plants, and introducing significant improvements to our existing stations. Ontario Hydro is a large and technically rich organization. Even so, we realize that partnerships with others in the industry are absolutely vital. I am thinking particularly of Atomic Energy of Canada Limited. We enjoy a very close relationship with Aecl, and their support was never more important than during the N/A Investigations. In recent years, we've strengthened our relationship with Aecl considerably. For example, we recently signed an agreement with Aecl, making available all of the Darlington 900 MW e design. Much of the cooperation between Ontario Hydro and Aecl occurs through the CANDU Engineering Authority and the CANDU Owners Group (CO G). These organizations are helping both of US to greatly improve cooperation and efficiency, and they are helping ensure we get the biggest return on our CANDU investments. CO G also provides an important information network which links CANDU operators in Canada, here in Korea, Argentina, India, Pakistan and Romania. In many respects, it is helping to develop the strong partnerships to support CANDU technology worldwide. We all benefit in the long run form sharing information and resources

  4. Darlington GS vacuum building - containment shell

    International Nuclear Information System (INIS)

    Huterer, J.; Ha, E.C.; Brown, D.G.; Cheng, P.C.

    1985-01-01

    The paper describes the consequences of new design requirements for the Darlington vacuum building on its structural configuration, analytical and reinforcing steel layout. Attention focuses on the ring girder where the juncture of dome and perimeter wall produces a complex post-tensioning layout, and attendant difficulties in design and construction. At the wall base, full fixity imposes large local stresses. Long-term, shrinkage and creep, and temperature effects become significant. A research program and in-house analytical procedure established time-dependent concrete behaviour and corresponding wall-sectional stresses. The outcome is examined in terms of reinforcement, temperature controls, and wall liner requirements. (orig.)

  5. Ontario Power Generation Fukushima emergency response drill strengthens and lessons learned - Ontario Power Generation Fukushima Emergency Response Drill Highlights

    International Nuclear Information System (INIS)

    Miller, David W.

    2014-01-01

    Japan's Fukushima Daiichi severe nuclear accident in March 2011 has resulted in a reassessment of nuclear emergency response and preparedness in Canada. On May 26, 27 and 28, 2014 Ontario Power Generation (OPG) conducted the first North American full scale nuclear emergency response exercise designed to include regional, provincial and federal bodies as well as the utility. This paper describes the radiological aspects of the OPG Exercise Unified Response (ExUR) with emphasis on deployment of new Fukushima equipment on the Darlington site, management of emergency workers deplored in the vicinity of Darlington to collect environmental samples and radiation measurements, performance of dose calculations, communication of dose projections and protective actions to local, provincial and federal agencies and conduct of vehicle, truck and personnel monitoring and decontamination facilities. The ExUR involved more than 1000 personnel from local, provincial and federal bodies. Also, 200 OPG employees participated in the off-site emergency response duties. The objective of the ExUR was to test and enhance the preparedness of the utility (OPG), government and non-government agencies and communities to respond to a nuclear emergency. The types of radiological instrumentation and mobile facilities employed are highlighted in the presentation. The establishment of temporary emergency rooms with 8 beds and treatment facilities to manage potentially contaminated injuries from the nuclear emergency is also described. (author)

  6. TUF simulation of Darlington class IV power failure

    Energy Technology Data Exchange (ETDEWEB)

    Liauw, W K; Liu, W S; Leung, R K; Phillips, B S [Ontario Hydro, Toronto, ON (Canada)

    1996-12-31

    Presented here is the TUF simulation of the initial transient of the Class IV power failure event that occurred on November 25, 1993 at Darlington Unit 4. The important physical parameters and models that relate to this event are discussed. The agreements between the code predictions and the plant data on the thermal-hydraulics and controller responses demonstrate the code reliability for plant operational support. (author). 4 refs., 1 tab., 12 figs.

  7. TUF simulation of Darlington class IV power failure

    International Nuclear Information System (INIS)

    Liauw, W.K.; Liu, W.S.; Leung, R.K.; Phillips, B.S.

    1995-01-01

    Presented here is the TUF simulation of the initial transient of the Class IV power failure event that occurred on November 25, 1993 at Darlington Unit 4. The important physical parameters and models that relate to this event are discussed. The agreements between the code predictions and the plant data on the thermal-hydraulics and controller responses demonstrate the code reliability for plant operational support. (author). 4 refs., 1 tab., 12 figs

  8. SEBIM pilot operated tandems. A new solution for Darlington NGS bleed condenser relief valves

    International Nuclear Information System (INIS)

    Paetzold, H.; Hera, V.; Schaumburg, G.

    1996-01-01

    Following incidents at Pickering, Wolsung and Bruce NGS, involving instability of bleed condenser relief valves, Darlington station decided to replace the spring loaded RV's by new pilot operated SEBIM tandem valves. This paper is presenting the approach taken, the design and the testing of the new solution, as well as some of the computer modeling work performed in connection with this project. The SEBIM tandems, following successful testing in France, will be installed in Darlington Unit 2, this spring. The new valves can perform with absence of instability and prevent a LOCA incident due to their design, which includes a protection and a redundant valve in series. (author)

  9. Evolution of CANDU vacuum building and pressure relief structures from Pickering NGS A to Darlington NGS A

    International Nuclear Information System (INIS)

    Beg, Z.M.; Ghosh, R.S.

    1987-01-01

    The vacuum building (VB) and pressure relief structures (PRS) are the unique features of multiple unit CANDU containments. In case of loss-of-coolant accident, the released radionuclides are drawn through the PRS into the subatmospheric VB, doused and contained without being released to the environment. This paper describes the differences in design, configuration and layout of the VB and PRS from Pickering NGS A to Darlington NGS A due to new developments in design concepts and to requirements which have proceeded from the experience gained in both the design and operation of the nuclear stations. (orig.)

  10. PENGARUH PENAMBAHAN RANGKAIAN DARLINGTON SISTEM PENGAPIAN DAN PUTARAN TERHADAP TEGANGAN JARUM YANG DIHASILKAN PADA MESIN KIJANG TYPE 5 K

    Directory of Open Access Journals (Sweden)

    Paryono Paryono

    2012-09-01

    Full Text Available Abstract: Vehicle technology development in this era pushes every vehicle industry to compete tightly in producing of practical, economic and environmentally sound vehicles. Recent fact shows that there are so many vehicles in its operation failed in having correct specification, creating wasteful of fuel consumtion and bad emission through certain limit. Economically, in reaching thrift gasoline with optimal power, it can increase the needle voltage  which is resulted when plug jumped a fire and started the ignition. The research aimed to test the difference between the use of circuit of Darlington ignition system to the needle voltage  in vehicle at low, middle, and high rotation of Toyota Kijang 5K motor. The data collection was done by testing needle voltage in vehicle which used conventional ignition system and Darlington serial ignition system. Research method used was testing the needle voltage which is resulted from conventional ignition system and Darlington ignition system by using factoral 2x2 Design. The results show that the use of Darlington serial ignition system in every motor rotation caused a significant difference with ratio F = 10,214 and P

  11. Managing nuclear power stations for success

    International Nuclear Information System (INIS)

    Smith, G.

    2006-01-01

    Ontario Power Generation's (OPG) top operational priority is to manage its nuclear assets to ensure they operate as safely, efficiently and cost effectively as possible. In meeting these objectives, the company is focused on continuously improving its nuclear performance and benchmarking that performance against the best in North America. This presentation explores how OPG is improving its nuclear performance and the steps it is taking to sustain performance success going forward. Topics to be discussed include the measures OPG is taking to enhance human performance and station reliability as well as the company's preparations to determine if a business case exists for extending the lives of the Pickering B and eventually the Darlington nuclear stations. (author)

  12. Behaviour of aged and new flux detectors in Darlington reactors

    Energy Technology Data Exchange (ETDEWEB)

    Banica, C.; Foster, M., E-mail: Constantin.Banica@OPG.com [Ontario Power Generation, Darlington Nuclear, Bowmanville, Ontario (Canada)

    2013-07-01

    In-core neutron flux detectors are used for protective and safety functions in the Darlington NGS 'A' CANDU reactors. This paper presents new observations regarding the aging of flux detectors, including response to fuelling, response to unit shutdown and indicators of detector noise. Comparisons of detector signals before and after replacement confirm previous assumptions about aging effects. (author)

  13. Supplementary report: cooling water systems for Darlington G.S

    International Nuclear Information System (INIS)

    1975-08-01

    This report summarizes Ontario Hydro's existing aquatic environmental programs, presents results of these investigations, and outlines plans and activities for expanded aquatic environment studies including the evaluation of alternative cooling systems. This report outlines specific considerations regarding possible alternative cooling arrangements for the Darlington station. It concludes with a recommendation that a study be initiated to examine the potential benefits of using the heated discharge water in a warm water recreational centre. (author)

  14. Ontario Hydro's nuclear program

    International Nuclear Information System (INIS)

    Jackson, H.A.

    1982-06-01

    In 1981 Ontario Hydro generated over 100 billion KWh of electrical energy. Approximately one third of this was from nuclear units. There are ten CANDU units (5 250 MW) currently in operation, and another twelve (8 600 MW) are under construction. The presently committed nuclear expansion program is estimated to involve expenditures of 16 billion dollars over the next 10 years. About 10 000 people are employed in the nuclear design and construction program. All projects are generally on schedule, with the stations coming into service during the following time periods: Pickering B, 1983-85; Bruce B, 1984-87; Darlington, 1988-90. The status of each project is reviewed. Planning is underway for some retubing projects, as early as 1985 for Pickering A

  15. AECB staff annual report of Darlington NGS for the year 1991

    International Nuclear Information System (INIS)

    1992-11-01

    Ontario Hydro operated Darlington in a safe manner in 1991. Ontario Hydro violated the Atomic Energy Control Regulations once and the physical security regulations three times in 1991. They failed to observe the Operating Licence conditions on ten occasions. The AECB did not find that the individual events had a significant impact on safety. There were no violations of the construction licence. None of the station staff received a radiation dose in excess of the regulatory limit. Radioactive emissions from the station were far below the regulatory limit. Special safety system performance was not fully satisfactory. Ontario Hydro failed to meet the unavailability targets for shutdown system one and the negative pressure containment system. Ontario Hydro reported seventeen incidents under conditions of the Operating and Construction licences. Units 1 and 2 remained shut down for most of 1991 because of unexplained fuel bundle damage in the reactor core. Ontario Hydro has decided to replace the main generator rotors because of cracks discovered on the rotor shaft. A fully modified rotor was installed on Unit 1. Ontario Hydro staff have a significant backlog of maintenance work. The Quality Improvement Program seemed to work well, resulting in some noticeable improvements. Three Shift Supervisors and four Control Operators were licensed this year. All planned emergency exercises and drills took place as scheduled. Ontario Hydro identified and are addressing several areas for improvement during the drills. Except for a power supply interruption to some IAEA equipment, Ontario Hydro achieved all its safeguards goals at Darlington in 1991. The Tritium Removal Facility (TRF) operated intermittently during 1991. Ontario Hydro is proceeding with the design and planning of an annex to the TRF to replace the present temporary facilities. (Author)

  16. Instrumentation and control in the Canadian nuclear power program - 1991 status

    International Nuclear Information System (INIS)

    Lepp, R.M.

    1992-01-01

    Shortly, Canada will have an installed nuclear capacity of 15,500 MWe. The 4 unit Darlington Nuclear Generating Station, which makes extensive use of computers for control and safety shutdown, is currently being connected to the Ontario Hydro grid. A significant effort is underway on technologies that will enhance the human-machine interface to meet more stringent plant availability and safety goals. This includes work on alarm annunciation, distributed control, plant display, relay logic replacement and software technology. These various initiatives and their benefits are discussed in the paper. (author). 6 refs

  17. Nuclear power plants in Canada: how we address community issues and concerns

    International Nuclear Information System (INIS)

    McFarlane, D.

    2003-01-01

    This presentation was developed by the public affairs staff of three Canadian utilities who offered case studies from three nuclear generating stations. Ontario Power Generation (OPG) facilities include Pickering Nuclear, with 8 units, and Darlington Nuclear, with 4 units, both located in the Region of Durham. The Pickering community is located east of Toronto on the shore of Lake Ontario. The facilities are located in the City of Pickering but are close to Ajax and the City of Toronto as well. They are surrounded by residences and businesses. The Darlington station is close to Pickering but further east of Toronto. It is located in a more rural environment in the Municipality of Clarington. Approximately 96% of installed capacity in Quebec is based on hydropower. Hydro-Quebec's Gentilly-2 is the only thermal nuclear generation station in operation. The station is located in Becancour on the south shore of the St. Lawrence River between Quebec City and Montreal. The population of Becancour is 12 000, while Trois-Rivieres and Champlain, on the north shore, count 100 000 residents. New Brunswick Power's Point Lepreau generating station (PLGS) is the only nuclear facility in Atlantic Canada, and supplies some 30% of in-province energy. The station is located in a rural area on the Lepreau peninsula overlooking the Bay of Fundy. It is located within 10 kilometers of the small communities of Dipper Harbour, Maces Bay, Little Lepreau and Chance Harbour. Approximately 38 kilometers to the northeast is located Saint John with a population of about 120 000. Corporate-community relations objectives are similar across the three utilities. They include building trust, garnering support for ongoing operations, and being - as well as being viewed as - a good corporate citizen. Meeting these objectives implies knowing and caring for the community and the issues raised by residents - not just issues of interest to the company. (author)

  18. How generation choices are influenced by costs, risks and externalities: the generation planning process in Ontario, Canada

    International Nuclear Information System (INIS)

    Marriage, E.A.; Rogers, M.S.

    1994-01-01

    Ontario Hydro is responsible for generating, supplying and delivering electricity throughout Ontario, Canada. Installed generation capacity of 32 GW consists of 20% hydro-electric (6.4 GW), 35% fossil (11.3 GW) and 40% nuclear (14.2 GW). Ontario Hydro' s planning process has evolved significantly since its decision in the late 1970's to build the 4-unit 3500 MW Darlington Nuclear Station. The emergence of environmental issues as a primary consideration, increased awareness of financial and regulatory risks, and uncertainty about the load forecast and the impact of demand management programs on the load have all contributed to the changed planning process. This paper discusses Ontario Hydro's responses to these changes such as: increased public involvement in the decision-making process; the use of a broader range of options including demand management and non-utility generation; optimizing the use of the existing system; more complete risk analyses of generation options, and recent attempts to incorporate externalities into the decision-making process. (authors). 3 figs

  19. Bruce and Darlington power pulse and pressure tube integrity programs -status 1995

    Energy Technology Data Exchange (ETDEWEB)

    Field, G J [Atomic Energy of Canada Ltd., Mississauga, ON (Canada); Wylie, J [Ontario Hydro, Tiverton, ON (Canada). Bruce Nuclear Generating Station-A

    1996-12-31

    The optimum solution to pressure tube fretting at the inlet of the Bruce and Darlington channels, a concern which became very serious following inspections in early 1992, is to remove the inlet bundle and operate with a 12 fuel bundle channel. During analysis of this operating mode a `power pulse` was identified which could occur during an inlet header break where all the fuel in the channel moved rapidly to the inlet of the channel. The pulse was unacceptable and the units were derated until solutions could be implemented. A number of solutions were identified and each station has begun implementation of their specific solution. Implementation has not been without problems and this paper provides a status report on the progress to date of the long bundle implementation solution for Bruce B and Darlington and the fuelling with the flow solution being implemented at Bruce A. Both types of solution have a significant impact on the original concern, fretting of the pressure tube. (author). 1 ref., 6 figs.

  20. RFSP simulations of Darlington FINCH refuelling transient

    International Nuclear Information System (INIS)

    Carruthers, E.V.; Chow, H.C.

    1997-01-01

    Immediately after refuelling of a channel, the fresh bundles are free of fission products. Xenon-135, the most notable of the saturating fission products, builds up to an equilibrium level in about 30 h. The channel power of the refuelled channel would therefore initially peak and then drop to a steady-state level. The RFSP code can track saturating-fission-product transients and power transients. The Fully INstrumented CHannels (FINCHs) in Darlington NGS provides channel power data on the refuelling power transients. In this paper, such data has been used to identify the physical evidence of the fission-product transient effect on channel power, and to validate RFSP fission-product-driver calculation results. (author)

  1. Report on the use of programmable digital computers in the shutdown systems of the Darlington G.S

    International Nuclear Information System (INIS)

    1981-06-01

    This report considers the use of large, programmable computers in the shutdown system at the planned Darlington Generating Station. After a review of the document submitted to the Atomic Energy Control Board (AECB) by Atomic Energy of Canada Ltd. Engineering Company in support of gaining AECB's agreement in principle to such a system, the ACNS concludes that no fundamental principle will be challenged by the introduction of computer technology into safety systems. It cautions, however, that the AECB should ensure that existing principles particularly those of independence and redundancy, will not be compromised in the application

  2. Steam generator life cycle management: Ontario Power Generation (OPG) experience

    International Nuclear Information System (INIS)

    Maruska, C.C.

    2002-01-01

    A systematic managed process for steam generators has been implemented at Ontario Power Generation (OPG) nuclear stations for the past several years. One of the key requirements of this managed process is to have in place long range Steam Generator Life Cycle Management (SG LCM) plans for each unit. The primary goal of these plans is to maximize the value of the nuclear facility through safe and reliable steam generator operation over the expected life of the units. The SG LCM plans integrate and schedule all steam generator actions such as inspection, operation, maintenance, modifications, repairs, assessments, R and D, performance monitoring and feedback. This paper discusses OPG steam generator life cycle management experience to date, including successes, failures and how lessons learned have been re-applied. The discussion includes relevant examples from each of the operating stations: Pickering B and Darlington. It also includes some of the experience and lessons learned from the activities carried out to refurbish the steam generators at Pickering A after several years in long term lay-up. The paper is structured along the various degradation modes that have been observed to date at these sites, including monitoring and mitigating actions taken and future plans. (author)

  3. Empirical observations on the aging of flux detectors at Darlington

    Energy Technology Data Exchange (ETDEWEB)

    Banica, C. [Ontario Power Generation, Darlington Nuclear, Bowmanville, Ontario (Canada); Slovak, R. [Ontario Power Generation, IMandCS, Pickering, Ontario (Canada)

    2011-07-01

    In-core neutron flux detectors are used for protective and safety functions in the Darlington CANDU reactors. This paper presents observations to date regarding aging of detectors, including recent measurements of prompt fractions and lead cable behaviour during a reactor power rundown. Linear models have been used to estimate and predict the prompt fraction evolution in time using independent variables such as the integrated neutron flux at the detector location, the length of the detector lead cable and the residual current at near-zero flux. (author)

  4. A survey on the corrosion susceptibility of Alloy 800 CANDU steam generator tubing materials

    International Nuclear Information System (INIS)

    Lu, Y.C.; Dupuis, M.; Burns, D.

    2008-01-01

    To provide support for a proactive steam generator (SG) aging management strategy, a survey on the corrosion susceptibility of the archived Alloy 800 tubing from CANDU SGs under plausible crevice chemistry conditions was conducted to assess the potential material degradation issues in CANDU SGs. Archived Alloy 800 samples were collected from four CANDU utilities. High-temperature electrochemical analysis was carried out to assess the corrosion susceptibility of the archived SG tubing under simulated CANDU crevice chemistry conditions at both 150 o C and 300 o C. The potentiodynamic polarization results obtained from the archived CANDU SG tubes were compared to the data from ex-service tubes removed from Darlington Nuclear Generating Station (DNGS) SGs and a reference nuclear grade Alloy 800 tubing. It was found that the removed Darlington SG tubes, with signs of in-service degradation, were more susceptible to pitting corrosion than the reference nuclear grade Alloy 800 tubing. At 150 o C, under the same neutral crevice chemistry conditions, the potentiodynamic polarization curve of the ex-service Darlington SG tubing has an active peak, which is a sign of propensity to crevice/underdeposit corrosion. This active peak was not observed in any of the potentiodynamic polarization curves of all archived Alloy 800 CANDU SG tubing indicating that archived CANDU SG tubes are less susceptible to the underdeposit corrosion under SG startup conditions. The corrosion behaviour of the archived Alloy 800 tubes from CANDU SG was similar to that of the reference nuclear grade Alloy 800 tubing. The results of this survey suggest that the Alloy 800 tubing materials used in the existing CANDU utilities (other than ex-service DNGS tubing) will continue to have reliable performance under specified CANDU operating conditions. Ex-service SG tubing from DNGS, although showing lower than average corrosion resistance, still has a wide acceptable operating margin and the in

  5. Prediction of pressure tube fretting-wear damage due to fuel vibration

    Energy Technology Data Exchange (ETDEWEB)

    Yetisir, M; Fisher, N J [Atomic Energy of Canada Ltd., Chalk River, ON (Canada)

    1996-12-31

    Fretting marks between fuel bundle bearing pads and pressure tubes have been observed at the inlet end of some Darlington NGS (nuclear generating station) and Bruce NGS fuel channels. The excitation mechanisms that lead to fretting are not fully understood. In this paper, the possibility of bearing pad-to-pressure tube fretting due to turbulence-induced motion of the fuel element is investigated. Numerical simulations indicate that this mechanism by itself is not likely to cause the level of fretting experienced in Darlington and Bruce NGS`s (nuclear generating stations). (author). 12 refs., 2 tabs., 11 figs.

  6. High current transistor pulse generator

    International Nuclear Information System (INIS)

    Nesterov, V.; Cassel, R.

    1991-05-01

    A solid state pulse generator capable of delivering high current trapezoidally shaped pulses into an inductive load has been developed at SLAC. Energy stored in the capacitor bank of the pulse generator is switched to the load through a pair of Darlington transistors. A combination of diodes and Darlington transistors is used to obtain trapezoidal or triangular shaped current pulses into an inductive load and to recover the remaining energy in the same capacitor bank without reversing capacitor voltage. The transistors work in the switch mode, and the power losses are low. The rack mounted pulse generators presently used at SLAC contain a 660 microfarad storage capacitor bank and can deliver 400 amps at 800 volts into inductive loads up to 3 mH. The pulse generators are used in several different power systems, including pulse to pulse bipolar power supplies and in application with current pulses distributed into different inductive loads. The current amplitude and discharge time are controlled by the central computer system through a specially developed multichannel controller. Several years of operation with the pulse generators have proven their consistent performance and reliability. 8 figs

  7. A progress review of Ontario Hydro's nuclear generation and heavy water production programs

    International Nuclear Information System (INIS)

    Kee, F.J.; Woodhead, L.W.

    Performance and economics of CANDU reactors in service are described. Progress of commissioning, construction and planning of reactors at Pickering, Bruce, and Darlington is outlined. Heavy water production is reviewed. (E.C.B.)

  8. Treatment of Arsenazo III contaminated heavy water stored at Darlington

    International Nuclear Information System (INIS)

    Suryanarayan, S.; Husain, A.; Williams, D.

    2010-01-01

    Darlington Nuclear Generating Station (DNGS) has accumulated over 48 drums of chemistry laboratory waste arising from analysis of heavy water (D 2 O). Several organic, including Arsenazo III, and inorganic contaminants present in these drums results in high total organic carbon (TOC) and conductivity. These drums have not been processed due to uncertainties related to clean-up of Arsenazo III contaminated heavy water. This paper provides details of chemical characterization as well as bench scale studies performed to demonstrate the feasibility of treating the downgraded D 2 O to the stringent target specifications of <1 ppm TOC and <0.1mS/m conductivity, required for feed to the Station Upgrading Plant (SUP). Both ionic organic species such as glycolate, acetate and formate as well as neutral organics such as acetone, methanol and ethylene glycol were detected in all the samples. Morpholine and propylene glycol were detected in one sample. Arsenazo III was determined to be not a major contaminant (maximum 8.4 ppm) in these waste drums, compared to the other organic contaminants present. Various unit processes such as pH adjustment, granular activated carbon (GAC), ion exchange resin (IX), UV-peroxide oxidation (UV-H 2 O 2 ) treatments, nanofiltration (NF) as well as reverse osmosis (RO) were tested on a bench scale both singly as well as in various combinations to evaluate their ability to achieve the stringent target conductivity and TOC specifications. Among the various bench scale tests evaluated, the successive processing train used at DNGS and consisting of GAC+IX+UV/H 2 O 2 +IX (polishing) unit operations was found to meet target specifications for both conductivity and TOC. Unit processes comprising (GAC+IX) and (RO-double pass + GAC+IX) met conductivity targets but failed to meet TOC specifications. The results of GAC+IX tests clearly emphasize the importance of using low flow rates for successful reduction in both conductivity as well as TOC. Detailed

  9. Prediction of pressure tube fretting-wear damage due to fuel vibration

    International Nuclear Information System (INIS)

    Yetisir, M.; Fisher, N.J.

    1997-01-01

    Fretting marks between fuel bundle bearing pads and pressure tubes have been observed at the inlet end of some Darlington Nuclear Generating Station (NGS) and Bruce NGS fuel channels. The excitation mechanisms that lead to fretting are not fully understood. In this paper, the possibility of bearing pad-to-pressure tube fretting due to turbulence-induced motion of the fuel element is investigated. Numerical simulations indicate that this mechanism by itself is not likely to cause the level of fretting experienced in Darlington and Bruce NGSs. (orig.)

  10. Nuclear generation cost and nuclear research development fund

    International Nuclear Information System (INIS)

    Kim, S. S.; Song, G. D.

    2000-01-01

    The main objective of this study is to analyze the effects of nuclear R and D fund to nuclear generation cost and to assess the adaptability of fund size through the comparison with the nuclear research fund in Japan. It was estimated that nuclear R and D fund increased the average annual unit cost of nuclear power generation by 1.14 won/kWh. When the size of nuclear R and D fund is compared with that in Japan, this study suggests that the current nuclear R and D fund should be largely increased taking into consideration the ratio of R and D fund to nuclear generation

  11. Training of troubleshooting skills in nuclear power plants

    International Nuclear Information System (INIS)

    Rhodes, W.; Szlapetis, I.J.; Casselman, K.

    1995-12-01

    This report details the study of training of troubleshooting skills for Canadian nuclear power plant operators and maintainers. The study was conducted in three distinct stages: 1) literature review and production of annotated bibliographies; 2) survey of experts in training for troubleshooting skills in North America; 3) survey of Canadian nuclear power plant training centres. Within this report are 12 annotated bibliographies of significant documents and an extensive bibliographic listing of relevant literature. The review of the literature and the survey of training experts identified the state-of-art in troubleshooting training with respect to training approaches and training tools. Trainers in the military, pharmaceutical, petro-chemical, and nuclear industries were surveyed and/or interviewed to determine the current approaches and technologies used in training for troubleshooting. Training personnel responsible for Canada's major nuclear generating stations (Bruce, Darlington, Pickering, and Point Lepreau) were interviewed and surveyed to determine the status of troubleshooting training in the Canadian nuclear industry. This information has been integrated and presented in this report. Conclusions and recommendations regarding the nature of the troubleshooting tasks performed by operators and maintainers and the related training were submitted. (author). 152 refs., 7 tabs., 1 fig

  12. Training of troubleshooting skills in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Rhodes, W; Szlapetis, I J; Casselman, K [Rhodes and Associates, Inc., Willowdale, ON (Canada)

    1995-12-01

    This report details the study of training of troubleshooting skills for Canadian nuclear power plant operators and maintainers. The study was conducted in three distinct stages: (1) literature review and production of annotated bibliographies; (2) survey of experts in training for troubleshooting skills in North America; (3) survey of Canadian nuclear power plant training centres. Within this report are 12 annotated bibliographies of significant documents and an extensive bibliographic listing of relevant literature. The review of the literature and the survey of training experts identified the state-of-art in troubleshooting training with respect to training approaches and training tools. Trainers in the military, pharmaceutical, petro-chemical, and nuclear industries were surveyed and/or interviewed to determine the current approaches and technologies used in training for troubleshooting. Training personnel responsible for Canada`s major nuclear generating stations (Bruce, Darlington, Pickering, and Point Lepreau) were interviewed and surveyed to determine the status of troubleshooting training in the Canadian nuclear industry. This information has been integrated and presented in this report. Conclusions and recommendations regarding the nature of the troubleshooting tasks performed by operators and maintainers and the related training were submitted. (author). 152 refs., 7 tabs., 1 fig.

  13. The nuclear power generation

    International Nuclear Information System (INIS)

    Serres, R.

    1999-01-01

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

  14. Nuclear power generation

    International Nuclear Information System (INIS)

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

    2001-01-01

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

  15. Licensing safety critical software

    International Nuclear Information System (INIS)

    Archinoff, G.H.; Brown, R.A.

    1990-01-01

    Licensing difficulties with the shutdown system software at the Darlington Nuclear Generating Station contributed to delays in starting up the station. Even though the station has now been given approval by the Atomic Energy Control Board (AECB) to operate, the software issue has not disappeared - Ontario Hydro has been instructed by the AECB to redesign the software. This article attempts to explain why software based shutdown systems were chosen for Darlington, why there was so much difficulty licensing them, and what the implications are for other safety related software based applications

  16. Competitiveness of nuclear power generation

    International Nuclear Information System (INIS)

    Sumi, Yoshihiko

    1998-01-01

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

  17. Ontario Hydro annual report, 1988

    International Nuclear Information System (INIS)

    1989-04-01

    Ontario continues a strong growth in electricity consumption; over the past five years consumption has risen an average of 5 percent a year. In 1988 consumption rose by 6.5 percent to 133.1 billion kilowatt-hours. Peak demand was 23 million kilowatts. The top priority for the 1990s will be improving the energy efficiency of customers and the operating efficiency of the Corporation, with a target saving of 4500 megawatts through demand management and energy efficiency by the year 2000. A new environmental division has been formed, as well as a division for non-utility generation. Safety is of particular importance to the Nuclear Generating Division; in all nuclear operations, after 143 million hours worked from 1955 to 1988, there has never been a work-related fatality or a detectable injury due to radiation. The average radiation dose per worker continues to decline and is now under 10 percent of the legal dose limit. Retubing of Pickering Nuclear Generating Station unit 2 has been completed. Retubing of unit 1 is under way, and work on units 3 and 4 has been approved. Construction continues on the Darlington Nuclear Generating Station, where the first unit is expected to go into service in 1989. The Darlington Tritium Removal Facility was completed

  18. Conditioning and handling of tritiated wastes at Canadian nuclear power facilities

    International Nuclear Information System (INIS)

    Krochmalnek, L.S.; Krasznai, J.P.; Carney, M.

    1987-04-01

    Ontario Hydro operates a 10,000 MW capacity nuclear power system utilizing the CANDU pressurized heavy water reactor design. The use of D 2 O as moderator and coolant results in the production of about 2400 Ci of tritium per MWe-yr. As a result, there is significant Canadian experience in the treatment, handling, transport and storage of tritiated wastes. Ontario Hydro operates its own reactor waste storage site which includes systems for volume reduction, immobilization and packaging of wastes. In addition, a facility to remove tritium from heavy water is presently being commissioned at the Darlington nuclear site. This facility will generate tritiated liquid and solid waste that will have to be properly conditioned prior to storage or disposal. The nature of these various wastes and the processes/packaging required to meet storage/disposal criteria are judged to have relevance to investigations in fusion facility waste arisings. Experience to date, planned operational procedures and ongoing R and D in this area are described

  19. Advanced nuclear reactor and nuclear fusion power generation

    International Nuclear Information System (INIS)

    2000-04-01

    This book comprised of two issues. The first one is a advanced nuclear reactor which describes nuclear fuel cycle and advanced nuclear reactor like liquid-metal reactor, advanced converter, HTR and extra advanced nuclear reactors. The second one is nuclear fusion for generation energy, which explains practical conditions for nuclear fusion, principle of multiple magnetic field, current situation of research on nuclear fusion, conception for nuclear fusion reactor and economics on nuclear fusion reactor.

  20. 76 FR 19148 - PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1...

    Science.gov (United States)

    2011-04-06

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-272, 50-311, 50-354; NRC-2009-0390 and NRC-2009-0391] PSEG Nuclear, LLC, Hope Creek Generating Station and Salem Nuclear Generating Station, Units 1 and 2..., DPR-70, and DPR-75 for an additional 20 years of operation for the Hope Creek Generating Station (HCGS...

  1. Power generation by nuclear power plants

    International Nuclear Information System (INIS)

    Bacher, P.

    2004-01-01

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

  2. Nuclear power generation and nuclear non-proliferation

    International Nuclear Information System (INIS)

    Rathjens, G.

    1979-01-01

    The main points existing between nuclear energy development and nuclear non-proliferation policy are reviewed. The solar energy and other energy will replace for nuclear fission energy in the twenty first century, but it may not occur in the first half, and the structure has to be established to continue the development of nuclear fission technology, including breeder reactor technology. In the near future, it should be encouraged to use advanced thermal reactors if they are economic and operated with safety. Miserable results may be created in the worldwide scale, if a serious accident occurs anywhere or nuclear power reactors are utilized for military object. It is estimated to be possible to develop the ability of manufacturing nuclear weapons within two or three years in the countries where the industry is highly developed so as to generate nuclear power. It is also difficult to take measures so that nuclear power generation does not increase nuclear proliferation problems, and it is necessary to mitigate the motive and to establish the international organization. Concensus exists that as the minimum security action, the storage and transportation of materials, which can be directly utilized for nuclear weapons, should be decided by the international system. The most portions of sensitive nuclear fuel cycle should be put under the international management, as far as possible. This problem is discussed in INFCE. Related to the nuclear nonproliferation, the difference of policy in fuel cycle problems between USA and the other countries, the enrichment of nuclear fuel material, especially the reasons to inhibit the construction of additional enrichment facilities, nuclear fuel reprocessing problems, radioactive waste disposal, plutonium stock and plutonium recycle problems are reviewed. (Nakai, Y.)

  3. Future nuclear power generation

    International Nuclear Information System (INIS)

    Mosbah, D.S.; Nasreddine, M.

    2006-01-01

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

  4. Situation of nuclear power generation in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, S [Swedish Atomic Forum

    1978-01-01

    In Sweden, nuclear power generation was received initially favorably. In the end of 1960s, however, nuclear power generation got involved in the activities of environment preservation. Then, political parties became opposed to nuclear power generation, and now, the need of nuclear power generation itself is regarded as questionable. In the general election in 1976, the Government opposing the nuclear power generation won. As the result, the conditional nuclear power development law and the energy committee were set up. The committee composed of parliament members, experts, and representatives of enterprises and trade unions is to submit its report so that the parliament can prepare a new energy program in the fall of 1978. Meanwhile, the nuclear fuel safety project formed newly has studied to satisfy the conditions of the law. In Sweden, which has developed nuclear reactors independently from the technology of USA, the oppositions are on the decrease, however. It is awaited what decision will be made by the Government in this fall.

  5. Generation 'Next' and nuclear power

    International Nuclear Information System (INIS)

    Sergeev, A.A.

    2001-01-01

    My generation was labeled by Russian mass media as generation 'Next.' My technical education is above average. My current position is as a mechanical engineer in the leading research and development institute for Russian nuclear engineering for peaceful applications. It is noteworthy to point out that many of our developments were really first-of-a-kind in the history of engineering. However, it is difficult to grasp the importance of these accomplishments, especially since the progress of nuclear technologies is at a standstill. Can generation 'Next' be independent in their attitude towards nuclear power or shall we rely on the opinions of elder colleagues in our industry? (authors)

  6. Nuclear power reactors of new generation

    International Nuclear Information System (INIS)

    Ponomarev-Stepnoi, N.N.; Slesarev, I.S.

    1988-01-01

    The paper presents discussions on the following topics: fuel supply for nuclear power; expansion of the sphere of nuclear power applications, such as district heating; comparative estimates of power reactor efficiencies; safety philosophy of advanced nuclear plants, including passive protection and inherent safety concepts; nuclear power unit of enhanced safety for the new generation of nuclear power plants. The emphasis is that designers of new generation reactors face a complicated but technically solvable task of developing highly safe, efficient, and economical nuclear power sources having a wide sphere of application

  7. Recent developments in plugging of steam generator tubes

    International Nuclear Information System (INIS)

    Buhay, S.; Abucay, R.C.

    1995-01-01

    Mechanical Plugging capability has been developed for Bruce Nuclear Generating Station (BNGS) steam generator (SG) tubes and Darlington Nuclear Generating Station (DNGS) SG tubes and tubesheet holes. The plug concept was a modified ABB/Combustion Engineering Inconel 690 plug with a nickel band, rolled into the tube or tubesheet hole from the primary side of the tubesheet. The qualification program included analytical justification of the plug body and experimental testing to verify the leak tightness of the rolled joint under conditions which meet or exceed all service or design requirements. Tools and procedures were developed and tested for manual and remote/robotic installation and removal of the mechanical plugs. Additionally, tools and procedures were developed to plug tubes/tubesheet holes at DNGS in the event the steam generator is recalled to service to act as a heat sink. A crew of Ontario Hydro personnel were trained and qualified for the installation of mechanical plugs for permanent and recall applications. During the DNGS Unit 4 spring 1995 outage, 6 tubes were plugged and the 'Recall Plugging Capability' was deployed and ready for use during a primary side SG tube removal. The mechanical plugs were installed manually with a typical 3 minute/plug in-bowl duration time with an average radiation dose of 12.5 mrem per plug. This compares favourably with manual plug welding during the same outage in the same SG bowl at approximately 15-30 minutes/plug in-bowl duration with an average radiation dose of 117 mrem/plug. (author)

  8. 75 FR 6223 - PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1...

    Science.gov (United States)

    2010-02-08

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-272, 50-311 and 50-354; NRC-2010-0043] PSEG Nuclear LLC; Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2...-70, and DPR-75, issued to PSEG Nuclear LLC (PSEG, the licensee), for operation of the Hope Creek...

  9. Economic analysis of nuclear power generation

    International Nuclear Information System (INIS)

    Song, Ki Dong; Choi, Young Myung; Kim, Hwa Sup; Lee, Man Ki; Moon, Kee Hwan; Kim, Seung Su

    1997-12-01

    The major contents in this study are as follows : - long-term forecast to the year of 2040 is provided for nuclear electricity generating capacity by means of logistic curve fitting method. - the role of nuclear power in a national economy is analyzed in terms of environmental regulation. To do so, energy-economy linked model is developed. By using this model, the benefits from the introduction of nuclear power in Korea are estimated. Study on inter-industry economic activity for nuclear industry is carried out by means of an input-output analysis. Nuclear industry is examined in terms of inducement effect of production, of value-added, and of import. - economic analysis of nuclear power generation is performed especially taking into consideration wide variations of foreign currency exchange rate. The result is expressed in levelized generating costs. (author). 27 refs., 24 tabs., 44 figs

  10. The human factors specialist in nuclear control centre design

    International Nuclear Information System (INIS)

    Wilson, R.B.; Beattie, J.D.

    The main focus at Ontario Hydro for man-machine interface design is in the design of control centres. Because the control of a nuclear generating unit is highly centralized there is an increasing need for effective information display and control layout. Control panel design innovations such as the use of CRT displays and the extended use of computerized control in the Darlington station have made it possible for Ontario Hydro to continue to have one first operator for each generating unit. The human factors specialist involved in control panel design must deal with people who know much more about the specific systems being controlled, and must become a generalist in all these systems as well. Designers have to use conceptual techniques such as task analysis, systems design, panel mock-ups, anthropometric data, and personal judgement based on experience as they design panels. They must find a balance between becoming locked into existing technology and methods, slavishly following the latest technological trends, and forgetting that real people will be using what they design

  11. Nuclear power generation and fuel cycle report 1997

    International Nuclear Information System (INIS)

    1997-09-01

    Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East

  12. Nuclear power generation and fuel cycle report 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

  13. Conscience of Japanese on nuclear power generation

    International Nuclear Information System (INIS)

    Hayashi, Chikio

    1995-01-01

    There are considerably many investigations and researches on the attitude of general public to nuclear power generation, but those which analyzed the contents of attitude or the research which got into the problem of what method is desirable to obtain the understanding of nuclear power generation for power generation side is rarely found. Therefore, the research on where is its cause was begun. As the result, since the attitude to nuclear power generation is related to the attitudes to many things that surround nuclear power generation in addition to that directly to nuclear power generation, it is necessary to elucidate the problem synthetically. The social investigation was carried out for the public of from 18 to 79 years old who live in the supply area of Kansai Electric Power Co., Inc. The data were obtained from those selected by probabilistic sampling, 1000 in urban area (rate of recovery 76%) and 440 in country area (rate of recovery 77%). The way of thinking on making questionnaire is shown. The investigation and the analysis of the obtained data were carried out. What do you recollect as a dangerous matter, the attitude to nuclear power generation, the structure of the conscience to nuclear power generation and its significance, the type classification of people and its features are reported and discussed. (K.I.)

  14. Consolidated nuclear steam generator

    International Nuclear Information System (INIS)

    Jabsen, F.S.; Schluderberg, D.C.; Paulson, A.E.

    1978-01-01

    An improved system of providing power has a unique generating means for nuclear reactors with a number of steam generators in the form of replaceable modular units of the expendable type to attain the optimum in effective and efficient vaporization of fluid during the generating power. The system is most adaptable to undrground power plants and marine usage

  15. Fear of nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Higson, D.J. [Paddington, NSW (Australia)

    2014-07-01

    Communicating the benefits of nuclear power generation, although essential, is unlikely to be sufficient by itself to counter the misconceptions which hinder the adoption of this technology, viz: that it is unsafe, generates intractable waste, facilitates the proliferation of nuclear weapons, etc. Underlying most of these objections is the fear of radiation, engendered by misunderstandings of the effects of exposure - not the actual risks of radiation exposure themselves. Unfortunately, some aspects of current radiation protection practices promote the misconception that there is no safe dose. A prime purpose of communications from the nuclear industry should be to dispel these misconceptions. (author)

  16. Situation of nuclear power generation in Europe

    International Nuclear Information System (INIS)

    Toukai, Kunihiro

    2003-01-01

    Nuclear power plants began to be built in Europe in the latter half of 1960. 146 plants are operating and generating about 33% of total power in 2002. France is top of Europe and operating 59 plants, which generate about 75% of power generation in the country. Germany is second and 30%. England is third and 30%. However, Germany decided not to build new atomic power plant in 2000. Movement of non-nuclear power generation is decreasing in Belgium and Switzerland. The liberalization of power generation decreased the wholesale price and BE Company in England was financial difficulties. New nuclear power generation is planning in Finland and France. (S.Y.)

  17. Third generation of nuclear power development

    International Nuclear Information System (INIS)

    Townsend, H.D.

    1988-01-01

    Developing nations use the nuclear plant option to satisfy important overall national development objectives, in addition to providing economical electric power. The relative importance of these two objectives changes as the nuclear program develops and the interim milestones are reached. This paper describes the three typical stages of nuclear power development programs. The first and the second generations are development phases with the third generation reaching self sufficiency. Examples are presented of European and Far East countries or regions which have reached or are about to step into the third generation phase of development. The paper concludes that to achieve the objectives of a nuclear power self sufficiency, other than merely filling the need of economical electric power, a careful technology transfer plan must be followed which sets realistic and achievable goals and establishes the country as a reliable and technically competent member of the nuclear power industry

  18. Nuclear power generation and fuel cycle report 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

  19. Nuclear power generation and fuel cycle report 1996

    International Nuclear Information System (INIS)

    1996-10-01

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included

  20. Investigation into sensitivity of Darlington boiler 2 feedwater flow calibration factor to boiler level control valve configuration

    Energy Technology Data Exchange (ETDEWEB)

    Coppens, D. [Darlington Nuclear Generating Station, Ontario Power Generation, Bowmanville, Ontario (Canada); Gurevich, Y. [Daystar Technologies Inc., Toronto, Ontario (Canada); Ton, V. [Inspection and Maintenance Services Div., Ontario Power Generation, Ajax, Ontario (Canada); Zobin, D. [AMEC NSS Ltd., Toronto, Ontario (Canada)

    2009-07-01

    The Ultrasonic Cross-Correlation Flow Meter (USCCFM) has been used for regular feedwater flow calibration at Darlington NGS since the early nineties. Typical measurement repeatability over the duration of a calibration run (normally several weeks long) is within {+-}0.2%. However, it was recently noticed that BO2 calibration factor experienced sudden changes of close to 1%. The paper will describe several different approaches used for identifying the reason for the observed effect. The investigation has revealed that changes in USCCFM readings are due to the complicated geometry of BO2 feedwater piping and that its accuracy can be as high as a fraction of percent if several readings are averaged around the pipe. (author)

  1. A large capacity turbine generator for nuclear power generation

    International Nuclear Information System (INIS)

    Maeda, Susumu; Miki, Takahiro; Suzuki, Kazuichi

    2000-01-01

    In future large capacity nuclear power plant, capacity of a generator to be applied will be 1800 MVA of the largest class in the world. In response to this, the Mitsubishi Electric Co., Ltd. began to carry out element technology verification of a four-pole large capacity turbine generator mainly using upgrading technique of large capacity, since 1994 fiscal year. And, aiming at reliability verification of the 1800 MVA class generator, a model generator with same cross-section as that of an actual one was manufactured, to carry out some verifications on its electrified tests, and so on. Every performance evaluation result of tests on the model generator were good, and high reliability to design and manufacturing technique of the 1800 MVA class generator could be verified. In future, on the base of these technologies, further upgrading of reliability on the large capacity turbine generator for nuclear power generation is intended to be carried out. (G.K.)

  2. Nuclear power generation: challenge in the 1980s

    International Nuclear Information System (INIS)

    Eklund, S.A.

    1981-01-01

    In the lecture ''Nuclear power generation - challenge in the 1980s'', attempt is made to predict the events arising in 1980s on the basis of the data available in the International Atomic Energy Agency. By the term ''challenge'', emphasis is placed on the potentiality of nuclear power for solving the world energy problem. This is indicated clearly by nuclear power currently accounting for 8%, of the total power generation in the world. The explanation in the above connection with figures and tables is made, including geographical distribution of reactors, nuclear power generation and total power generation in various countries, future capacity of nuclear power generation, situation of reactor operation, future installation of nuclear power plants, uranium demand/supply situation, spent fuel storage, etc. Then, discussion and analysis are made on such problems as waste management, economy, safety, and safeguards. (J.P.N.)

  3. The nuclear industry and the young generation

    International Nuclear Information System (INIS)

    Hanti, A.

    2000-01-01

    The European Nuclear Society was founded in 1975. It is a federation of 25 nuclear societies from 24 countries-stretching from the Atlantic to the Urals and on across Russia to the Pacific. Through Russia's membership in the Pacific Nuclear Council. ENS is directly linked to that area, too. ENS comprises more than 20 000 professionals from industry, power stations, research centers and authorities, working to advance nuclear energy. ENS has three Member Societies in Australia, Israel and Morocco. Also it has collaboration agreements with the American Nuclear Society, the Argentinean Nuclear Energy Association, the Canadian and the Chinese Nuclear Societies. ENS is doing pioneering work with its Young Generation Network, standing for positive measures to recruit and educate young people as engineers, technicians and skilled staff ion the nuclear field: from school to university and in industry. The goals of the YGN are: to promote the establishment of national Young Generation networks; to promote the exchange of knowledge between older and younger generation cross-linked all over Europe; to encourage young people in nuclear technology to provide a resource for the future; to communicate nuclear issues to the public (general public, media, politicians). (N.C.)

  4. Nuclear power generation and automation technology

    International Nuclear Information System (INIS)

    Korei, Yoshiro

    1985-01-01

    The proportion of nuclear power in the total generated electric power has been increasing year after year, and the ensuring of its stable supply has been demanded. For the further development of nuclear power generation, the heightening of economical efficiency which is the largest merit of nuclear power and the public acceptance as a safe and stable electric power source are the important subjects. In order to solve these subjects, in nuclear power generation, various automation techniques have been applied for the purpose of the heightening of reliability, labor saving and the reduction of radiation exposure. Meeting the high needs of automation, the automation technology aided by computers have been applied to the design, manufacture and construction, operation and maintenance of nuclear power plants. Computer-aided design and the examples of design of a reactor building, pipings and a fuel assembly, an automatic welder for pipings of all position TIG welding type, a new central monitoring and control system, an automatic exchanger of control rod-driving mechanism, an automatic in-service inspection system for nozzles and pipings, and a robot for steam generator maintenance are shown. The trend of technical development and an intelligent moving robot, a system maintenance robot and a four legs walking robot are explained. (Kako, I.)

  5. How is Electricity Generated from Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lajnef, D.

    2015-01-01

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

  6. Is there a tomorrow for nuclear power generation?

    International Nuclear Information System (INIS)

    Kanoh, T.

    1996-01-01

    Critical comments are publicly made about nuclear power generation and the nuclear fuel cycle. This criticism is directed at three areas of concern: accidents, radioactive waste disposal, and proliferation of nuclear weapons. In addition, there are other comments that ask 'Why are there countries pushing for nuclear power generation when other countries around the world are giving it up?' and 'Will further efforts to develop new energy sources and energy conservation not eliminate the nneed for nuclear power generation?' Such critical comments appear in some media more often than those expressing other opinions. Is there really no tomorrow for nuclear power? This question is studied below. (author)

  7. Fuqing nuclear power of nuclear steam turbine generating unit No.1 at the implementation and feedback

    International Nuclear Information System (INIS)

    Cao Yuhua; Xiao Bo; He Liu; Huang Min

    2014-01-01

    The article introduces the Fuqing nuclear power of nuclear steam turbine generating unit no.l purpose, range of experience, experiment preparation, implementation, feedback and response. Turn of nuclear steam turbo-generator set flush, using the main reactor coolant pump and regulator of the heat generated by the electric heating element and the total heat capacity in secondary circuit of reactor coolant system (steam generator secondary side) of saturated steam turbine rushed to 1500 RPM, Fuqing nuclear power of nuclear steam turbine generating unit no.1 implementation of the performance of the inspection of steam turbine and its auxiliary system, through the test problems found in the clean up in time, the nuclear steam sweep turn smooth realization has accumulated experience. At the same time, Fuqing nuclear power of nuclear steam turbine generating unit no.1 at turn is half speed steam turbine generator non-nuclear turn at the first, with its smooth realization of other nuclear power steam turbine generator set in the field of non-nuclear turn play a reference role. (authors)

  8. 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

  9. Situation of nuclear power generation in Sweden: swaying nuclear energy policy and conversion from nuclear phase-out policy

    International Nuclear Information System (INIS)

    Kuroda, Yuji

    2017-01-01

    In Sweden, fossil fuels cannot be produced domestically, and most of them depend on foreign imports. For this reason, together with hydropower generation using abundant water resources, nuclear power generation was introduced and used since the early stage. Nuclear power generation in 2015 reached 35% of total generated power energy. As of 2016, Sweden was steadily constructing the world's second final disposal site of high-level radioactive waste. On the other hand, this country is known as the one that decided nuclear phase-out policy earliest in the world. However, the country's nuclear policy is swaying together with changes in political party power due to election results. In 1980, they decided the policy of abolishing all nuclear power generation by 2010. Thereafter, the nuclear phase-out policy was frozen and maximum 10 units of nuclear plants were accepted. The goal of the latest policy is to allow new construction up to 10 units as replacement, and to use 100% of renewable energy in 2040. However, the year of 2040 is not a deadline for the abolishment of nuclear power generation. In Sweden's public opinion on nuclear power generation, the early abolition was dominant at about 50% during 1986∼1995, but this opinion decreased to about 10% in the 2000s. There is an increasing number of opinions saying that the existing nuclear plants should be continuously operated for a while, and phased out step by step in the future. (A.O.)

  10. Managing nuclear predominant generating capacity

    International Nuclear Information System (INIS)

    Bouget, Y.H.; Carbonnier, D.

    1999-01-01

    The most common believe, associated with nuclear power plant, leads to the conclusion that it can only operate, as a base load plant. This observation can be reversed, by just looking at large generating capacity, using an important nuclear generation mix. Nuclear plants may certainly load follow and contribute to the grid frequency control. The French example illustrates these possibilities. The reactor control of French units has been customized to accommodate the grid requests. Managing such a large nuclear plant fleet requires to take various actions, ranging from a daily basis to a multi-annual prospective standpoint. The paper describes the various contributions leading to safe, reliable, well accepted and cost competitive nuclear plants in France. The combination of all aspects related to operations, maintenance scheduling, nuclear safety management, are presented. The use of PWR units carries considerable weight in economic terms, with several hundred million francs tied in with outage scheduling every year. This necessitates a global view of the entire generating system which can be mobilized to meet demand. There is considerable interaction between units as, on the one hand, they are competing to satisfy the same need, and, on the other hand, reducing maintenance costs means sharing the necessary resources, and thus a coordinated staggering of outages. In addition, nuclear fuel is an energy reserve which remains in the reactor for 3 or 4 years, with some of the fuel renewed each year. Due to the memory effect, the fuel retains a memory of past use, so that today's choices impact upon the future. A medium-term view of fuel management is also necessary. The coordination systems implemented by EDF aim to control these parameters for the benefit of electricity consumers. (author)

  11. Nuclear renaissance in Asia. Energy security and development of nuclear power generation system

    International Nuclear Information System (INIS)

    Nakasugi, Hideo

    2009-01-01

    The energy policy and strategy of development of nuclear power generation system of China, India and Korea are stated on the basis of use of light water reactors (LWRs). The conditions of power generation and introduction plans of nuclear energy of other Asian countries such as Vietnam, Thailand, Indonesia, Malaysia and Philippines are described. The power plant capacity of China increased from 50,500 MW in 2004, to 65,000 MW in 2005, and the target value is 40,000 MW of operating nuclear plants and 18,000 MW in building in 2020. China is lagging behind in peaceful use of nuclear energy technologies. A plan for the reform of nuclear industry and nuclear power generation projects of China are summarized. Total power plant capacity of India is 145,000 MW, but the nuclear plant capacity is 4,120 MW in 2008 and 63,000 MW of the target in 2032. Development of nuclear power, circumstance, and cooperation with other countries' industries are explained. 17,716 MW of nuclear power is in operation, 6,800 MW in building and 2,800 MW in the planning stage in Korea. History of development of national reactors and the subjects of development of the fourth generation reactor of Korea are stated. Management system of nuclear power plants in China, technical bases of nuclear power plants in China, development system of nuclear power generation in India, the conditions of power production of Korea in 2008, the capacity factor of Korea, Japan and world from 1998 to 2008, and comparison of nuclear industries in China, India and Korea are illustrated. (S.Y.)

  12. The different generation of nuclear reactors from Generation-1 to Generation-4

    International Nuclear Information System (INIS)

    Cognet, G.

    2010-01-01

    In this work author deals with the history of the development of nuclear reactors from Generation-1 to Generation-4. The fuel cycle and radioactive waste management as well as major accidents are presented, too.

  13. Third generation nuclear plants

    Science.gov (United States)

    Barré, Bertrand

    2012-05-01

    After the Chernobyl accident, a new generation of Light Water Reactors has been designed and is being built. Third generation nuclear plants are equipped with dedicated systems to insure that if the worst accident were to occur, i.e. total core meltdown, no matter how low the probability of such occurrence, radioactive releases in the environment would be minimal. This article describes the EPR, representative of this "Generation III" and a few of its competitors on the world market.

  14. Power generation from nuclear reactors in aerospace applications

    International Nuclear Information System (INIS)

    English, R.E.

    1982-01-01

    Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion

  15. Power Generation from Nuclear Reactors in Aerospace Applications

    Science.gov (United States)

    English, Robert E.

    1982-01-01

    Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere; a program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

  16. The third generation of nuclear power development

    International Nuclear Information System (INIS)

    Townsend, H.D.

    1987-01-01

    Developing nations use the nuclear plant option to satisfy important overall national development objectives, in addition to providing economical electric power. The relative importance of these two objectives changes as the nuclear program develops and the interim milestones are reached. This paper describes the three typical stages of nuclear power development programs. The first and the second generations are development phases with the third generation reaching self sufficiency. Examples are presented of European and Far East countries or regions which have reached of are about to step into the third generation phase of development. The paper concludes that to achieve the objective of a nuclear power self sufficiency, other than merely filling the need of economical electric power, a careful technology transfer plan must be followed which sets realistic and achievable goals and establishes the country as a reliable and technically competent member of the nuclear power industry. (author)

  17. Darlington NGD fuel handling head eight acceptance program

    International Nuclear Information System (INIS)

    Skelton, P.H.; Sie, T.

    1996-01-01

    Darlington NGD requires eight fuelling machine heads to fuel the four 932 MW reactors. Six heads are used on the three fuelling machine trolleys for normal fuelling operations. A further two heads are required to allow for maintenance and to provide for such reactor face activities as PIPE and CIGAR. Seven heads were successfully delivered to site from the head supplier. During acceptance testing, stalls on the charge tube screw assembly of the eighth and final head prevented its delivery to site. Replacement of the charge tube screw with a spare screw did not alleviate the problem. An in depth series of tests were undertaken at site, at the supplier and at the screw sub-supplier to determine the root cause of the problem. These tests included taking torque measurements under different operating conditions and using different components to assess the effects of the changes on torque levels. An assessment of the effects of changing chemical conditions (particularly crud levels) was also made. To ensure that the results of the testing were well understood, additional torque testing was also completed on a head and screw assembly at site that was known to work well. Based on all of the above series of tests, a recommendation was made to re-machine the charge tube screw(s). The original charge tube screw from Head eight was subsequently returned to the sub-supplier for re-work. Follow-up torque measurements and acceptance testing showed that the screw rework was effective and that Head eight could be successfully delivered to site. This paper focuses on the results of the head/screw test program. Results of the acceptance testing are also discussed. (author). 2 refs., 4 figs

  18. Darlington NGD fuel handling head eight acceptance program

    Energy Technology Data Exchange (ETDEWEB)

    Skelton, P H; Sie, T [Ontario Hydro, Bowmanville (Canada). Darlington Nuclear Generating Station; Pilgrim, J [Canadian General Electric Co. Ltd., Toronto, ON (Canada)

    1997-12-31

    Darlington NGD requires eight fuelling machine heads to fuel the four 932 MW reactors. Six heads are used on the three fuelling machine trolleys for normal fuelling operations. A further two heads are required to allow for maintenance and to provide for such reactor face activities as PIPE and CIGAR. Seven heads were successfully delivered to site from the head supplier. During acceptance testing, stalls on the charge tube screw assembly of the eighth and final head prevented its delivery to site. Replacement of the charge tube screw with a spare screw did not alleviate the problem. An in depth series of tests were undertaken at site, at the supplier and at the screw sub-supplier to determine the root cause of the problem. These tests included taking torque measurements under different operating conditions and using different components to assess the effects of the changes on torque levels. An assessment of the effects of changing chemical conditions (particularly crud levels) was also made. To ensure that the results of the testing were well understood, additional torque testing was also completed on a head and screw assembly at site that was known to work well. Based on all of the above series of tests, a recommendation was made to re-machine the charge tube screw(s). The original charge tube screw from Head eight was subsequently returned to the sub-supplier for re-work. Follow-up torque measurements and acceptance testing showed that the screw rework was effective and that Head eight could be successfully delivered to site. This paper focuses on the results of the head/screw test program. Results of the acceptance testing are also discussed. (author). 2 refs., 4 figs.

  19. Next Generation Nuclear Plant System Requirements Manual

    International Nuclear Information System (INIS)

    Not Listed

    2008-01-01

    System Requirements Manual for the NGNP Project. The Energy Policy Act of 2005 (H.R. 6; EPAct), which was signed into law by President George W. Bush in August 2005, required the Secretary of the U.S. Department of Energy (DOE) to establish a project to be known as the Next Generation Nuclear Plant (NGNP) Project. According to the EPAct, the NGNP Project shall consist of the research, development, design, construction, and operation of a prototype plant (to be referred to herein as the NGNP) that (1) includes a nuclear reactor based on the research and development (R and D) activities supported by the Generation IV Nuclear Energy Systems initiative, and (2) shall be used to generate electricity, to produce hydrogen, or to both generate electricity and produce hydrogen. The NGNP Project supports both the national need to develop safe, clean, economical nuclear energy and the Nuclear Hydrogen Initiative (NHI), which has the goal of establishing greenhouse-gas-free technologies for the production of hydrogen. The DOE has selected the helium-cooled High Temperature Gas-Cooled Reactor (HTGR) as the reactor concept to be used for the NGNP because it is the only near-term Generation IV concept that has the capability to provide process heat at high-enough temperatures for highly efficient production of hydrogen. The EPAct also names the Idaho National Laboratory (INL), the DOE's lead national laboratory for nuclear energy research, as the site for the prototype NGNP

  20. Power generation from nuclear reactors in aerospace applications

    Energy Technology Data Exchange (ETDEWEB)

    English, R.E.

    1982-01-01

    Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

  1. Human factors issues in fuel handling

    International Nuclear Information System (INIS)

    Beattie, J.D.; Iwasa-Madge, K.M.; Tucker, D.A.

    1994-01-01

    The staff of the Atomic Energy Control Board wish to further their understanding of human factors issues of potential concern associated with fuel handling in CANDU nuclear power stations. This study contributes to that objective by analysing the role of human performance in the overall fuel handling process at Ontario Hydro's Darlington Nuclear Generating Station, and reporting findings in several areas. A number of issues are identified in the areas of design, operating and maintenance practices, and the organizational and management environment

  2. Present state and prospect of nuclear power generation

    International Nuclear Information System (INIS)

    Fukushima, Akira

    1980-01-01

    Energy resources are scarce in Japan, therefore Japan depends heavily on imported petroleum. However, the international situation of petroleum became more unstable recently, and the promotion of the development and utilization of nuclear power generation was agreed upon in the summit meeting and the IEA. In order to achieve the stable growth of economy and improve the national welfare in Japan, it is urgent subject to accelerate the development of nuclear power generation. Japan depends the nuclear fuel also on import, but the stable supply is assured by the contract of long term purchase. It is not necessary to replace nuclear fuel usually for three years, and the transport and storage of nuclear fuel are easy because the quantity is not very large. By establishing the independent nuclear fuel cycle in Japan, it is possible to give the character similar to domestically produced energy to nuclear fuel. Moreover, uranium resources can be effectively utilized by the development of nuclear reactors of new types, such as FBRs. The cost of generating 1 kWh of electricity was about 8 yen in case of nuclear power and 15 yen in petroleum thermal power as of January, 1980. 21 nuclear power plants of about 15 million kW capacity are in operation in Japan, and about 30 million kW will be installed by 1985. The measures to promote the development of nuclear power generation are discussed. (Kako, I.)

  3. Optimization in the scale of nuclear power generation and the economy of nuclear power

    International Nuclear Information System (INIS)

    Suzuki, Toshiharu

    1983-01-01

    In the not too distant future, the economy of nuclear power will have to be restudied. Various conditions and circumstances supporting this economy of nuclear power tend to change, such as the decrease in power demand and supply, the diversification in base load supply sources, etc. The fragility in the economic advantage of nuclear power may thus be revealed. In the above connection, on the basis of the future outlook of the scale of nuclear power generation, that is, the further reduction of the current nuclear power program, and of the corresponding supply and demand of nuclear fuel cycle quantities, the aspect of the economic advantage of nuclear power was examined, for the purpose of optimizing the future scale of nuclear power generation (the downward revision of the scale, the establishment of the schedule of nuclear fuel cycle the stagnation of power demand and nuclear power generation costs). (Mori, K.)

  4. Fuel bundle to pressure tube fretting in Bruce and Darlington

    Energy Technology Data Exchange (ETDEWEB)

    Norsworthy, A G; Ditschun, A [Atomic Energy of Canada Ltd., Mississauga, ON (Canada)

    1996-12-31

    As the fuel channel elongates due to creep, the fuel string moves relative to the inlet until the fuel pads at the inboard end eventually separate from the spacer sleeve, and the fuel resides on the burnish mark of the pressure tube. The bundle is then supported in a fashion which contributes to increased levels of vibration. Those pads which (due to geometric variation) have contact loads with the pressure tube within a certain range, vibrate, and cause significant fretting on the burnish mark, and further along at the midplane of the bundle. Inspection of the pressure tubes in Bruce A, Bruce B, and Darlington has revealed fret damage up to 0.55 mm at the burnish mark and slightly lower than this at the inlet bundle midplane. To date, all fret marks have been dealt with successfully without the need for tube replacement, but a program of work has been initiated to understand the mechanism and reduce the fretting. Such understanding is necessary to guide future design changes to the fuel bundle, to guide future inspection programs, to guide maintenance programs, and for longer term strategic planning. This paper discusses how the understanding of fretting has evolved and outlines a current hypothesis for the mechanism of fretting. The role of bundle geometry, excitation forces, and reactor conditions are reviewed, along with options under consideration to mitigate damage. (author). 4 refs., 2 tabs., 13 figs.

  5. Fuel bundle to pressure tube fretting in Bruce and Darlington

    International Nuclear Information System (INIS)

    Norsworthy, A.G.; Ditschun, A.

    1995-01-01

    As the fuel channel elongates due to creep, the fuel string moves relative to the inlet until the fuel pads at the inboard end eventually separate from the spacer sleeve, and the fuel resides on the burnish mark of the pressure tube. The bundle is then supported in a fashion which contributes to increased levels of vibration. Those pads which (due to geometric variation) have contact loads with the pressure tube within a certain range, vibrate, and cause significant fretting on the burnish mark, and further along at the midplane of the bundle. Inspection of the pressure tubes in Bruce A, Bruce B, and Darlington has revealed fret damage up to 0.55 mm at the burnish mark and slightly lower than this at the inlet bundle midplane. To date, all fret marks have been dealt with successfully without the need for tube replacement, but a program of work has been initiated to understand the mechanism and reduce the fretting. Such understanding is necessary to guide future design changes to the fuel bundle, to guide future inspection programs, to guide maintenance programs, and for longer term strategic planning. This paper discusses how the understanding of fretting has evolved and outlines a current hypothesis for the mechanism of fretting. The role of bundle geometry, excitation forces, and reactor conditions are reviewed, along with options under consideration to mitigate damage. (author). 4 refs., 2 tabs., 13 figs

  6. France and nuclear proliferation: the new generation of nuclear submarines

    International Nuclear Information System (INIS)

    Barrillot, B.

    2001-01-01

    Ten years after the end of the 'cold war' the French government has pursued its national defense program with the construction of a new generation of nuclear submarines with new type of missiles and nuclear heads. This book analyzes the possible solutions for a step by step elimination of nuclear weapons from the French weapons stock. (J.S.)

  7. Economic analysis of nuclear power generation

    International Nuclear Information System (INIS)

    Song, Ki Dong; Choi, Young Myung; Kim, Hwa Sup; Lee, Man Ki; Moon, Kee Hwan; Kim, Seung Su; Lim, Chae Young

    1998-12-01

    An energy security index was developed to measure how the introduction of nuclear power generation improved the national security of energy supply in Korea. Using the developed index, a quantitative effort was made to analyze the relationship between the nuclear power generation and the national energy security. Environmental impacts were evaluated and a simplified external cost of a specific coal-fired power plant in Korea was estimated using the QUERI program, which was developed by IAEA. In doing so, efforts were made to quantify the health impacts such as mortality, morbidity, and respiratory hospital admissions due to particulates, SOx, and Nox. The effects of CO 2 emission regulation on the national economy were evaluated. In doing so, the introduction of carbon tax was assumed. Several scenarios were established about the share of nuclear power generation and an effort was made to see how much contribution nuclear energy could make to lessen the burden of the regulation on the national economy. This study re-evaluated the methods for estimating and distributing decommissioning cost of nuclear power plant over lifetime. It was resulted out that the annual decommissioning deposit and consequently, the annual decommissioning cost could vary significantly depending on estimating and distributing methods. (author). 24 refs., 44 tabs., 9 figs

  8. Present status and problems of nuclear power generation

    International Nuclear Information System (INIS)

    Harada, Hiroshi.

    1984-01-01

    The nuclear power generation in Japan began in 1963 with the successful power generation in the JPDR of the Japan Atomic Energy Research Institute, and since then, more than 20 years have elapsed. The Japan Atomic Power Co. started the operation of an imported Calder Hall type gas-cooled reactor with 166,000 kWe output in Tokai Nuclear Power Station in July, 1966. In 1983, the quantity of nuclear power generation was 113.1 billion kWh, which was equivalent to 21.4 % of the total power generation in Japan. As of April 1, 1984, 25 nuclear power plants with 18.28 million kW output were in operation, 12 plants of 11.8 million kW were under construction, and 7 plants of 6.05 million kW were in preparation phase. Besides, the ATR ''Fugen'' with 165,000 kW output has been in operation, and the FBR ''Monju'' with 280,000 kW output is under construction. The capacity ratio of Japanese nuclear power stations attained 71.5 % in 1983. According to the ''Long term energy demand and supply outlook'' revised in November, 1983, the nuclear power generation in 2000 will be about 62 million kW to cater for about 16 % of primary energy supply. The problems are the improvement of economy, the establishment of independent nuclear fuel cycle, the decommissioning of nuclear reactors and so on. (Kako, I.)

  9. Nuclear excited power generation system

    International Nuclear Information System (INIS)

    Parker, R.Z.; Cox, J.D.

    1989-01-01

    A power generation system is described, comprising: a gaseous core nuclear reactor; means for passing helium through the reactor, the helium being excited and forming alpha particles by high frequency radiation from the core of the gaseous core nuclear reactor; a reaction chamber; means for coupling chlorine and hydrogen to the reaction chamber, the helium and alpha particles energizing the chlorine and hydrogen to form a high temperature, high pressure hydrogen chloride plasma; means for converting the plasma to electromechanical energy; means for coupling the helium back to the gaseous core nuclear reactor; and means for disassociating the hydrogen chloride to form molecular hydrogen and chlorine, to be coupled back to the reaction chamber in a closed loop. The patent also describes a power generation system comprising: a gaseous core nuclear reactor; means for passing hydrogen through the reactor, the hydrogen being excited by high frequency radiation from the core; means for coupling chlorine to a reaction chamber, the hydrogen energizing the chlorine in the chamber to form a high temperature, high pressure hydrogen chloride plasma; means for converting the plasma to electromechanical energy; means for disassociating the hydrogen chloride to form molecular hydrogen and chlorine, and means for coupling the hydrogen back to the gaseous core nuclear reactor in a closed loop

  10. Economics of generating electricity from nuclear power

    International Nuclear Information System (INIS)

    Boadu, H.O.

    2001-01-01

    The paper reviews and compares experiences and projected future construction and electricity generation costs for nuclear and fossil fired power plants. On the basis of actual operating experience, nuclear power has been demonstrated to be economically competitive with other base load generation options, and international studies project that this economic competitiveness will be largely maintained in the future, over a range of conditions and in a number of countries. However, retaining and improving this competitive position requires concerted efforts to ensure that nuclear plants are constructed within schedule and budgets, and are operated reliably and efficiently. Relevant cost impacting factors is identified, and conclusions for successful nuclear power plant construction and operation are drawn. The desire to attain sustainable development with balanced resource use and control of the environmental and climate impacts of energy systems could lead to renewed interest in nuclear power as an energy source that does not emit greenhouse gases, thus contributing to a revival of the nuclear option. In this regard, mitigation of emissions from fossil-fuelled power plants could lead to restrictions of fossil fuel use and/or result in higher costs of fossil based generation, thus improving the economic competitiveness of nuclear power (au)

  11. Fatigue load considerations and use of high efficiency materials in the nuclear refurbishment projects: a structural engineering perspective

    Energy Technology Data Exchange (ETDEWEB)

    Mohee, F. M., E-mail: fmm_p@yahoo.com [Univ. of Waterloo, ON (Canada)

    2014-07-01

    For the Darlington refurbishment project in Canada, fatigue load consideration is a very crucial component in the analysis and design of different structures in the nuclear facilities. New and innovative structural materials having much higher ultimate tensile strength and modulus of elasticity, that are free from corrosion, should be considered along with fatigue load during the analysis and design of the nuclear refurbishment projects. The structural analysis should include beam, column and slabs, vibrating, rotating and crane supporting structures, robotic structures, pipe supports, Serapid chain and associated automated gate structures, flask supporting structures, processing unit and lidding unit support structures. (author)

  12. Dynamic modelling of nuclear steam generators

    International Nuclear Information System (INIS)

    Kerlin, T.W.; Katz, E.M.; Freels, J.; Thakkar, J.

    1980-01-01

    Moving boundary, nodal models with dynamic energy balances, dynamic mass balances, quasi-static momentum balances, and an equivalent single channel approach have been developed for steam generators used in nuclear power plants. The model for the U-tube recirculation type steam generator is described and comparisons are made of responses from models of different complexity; non-linear versus linear, high-order versus low order, detailed modeling of the control system versus a simple control assumption. The results of dynamic tests on nuclear power systems show that when this steam generator model is included in a system simulation there is good agreement with actual plant performance. (author)

  13. External costs of nuclear-generated electricity

    International Nuclear Information System (INIS)

    Rotaru, I.; Glodeanu, F.; Popescu, D.; Andrei, V.

    2004-01-01

    External costs of nuclear power include: future financial liabilities arising from decommissioning and dismantling of nuclear facilities, health and environmental impacts of radioactivity releases in routine operation, radioactive waste disposal and effects of severe accidents. The nuclear energy industry operates under regulations that impose stringent limits to atmospheric emissions and liquid effluents from nuclear facilities as well as requiring the containment and confinement of solid radioactive waste to ensure its isolation from the biosphere as long as it may be harmful for human health and the environment. The capital and operating costs of nuclear power plants and fuel cycle facilities already internalize a major portion of the above-mentioned potential external costs, and these are reflected in the prices paid by consumers of nuclear-generated electricity. The externality related to potential health and environmental impacts of radioactive releases during routine operations have been assessed in a large number of comprehensive studies, in particular the ExternE project that was created in the framework of the European Commission. With regard to effects of severe nuclear accidents, a special legal regime, the third-party liability system, has been implemented to provide limited third party liability coverage in the event of a nuclear accident. The nuclear plant owners are held liable for some specified first substantial part of damages to third parties, and must secure insurance coverage adequate to cover this part. The Government provides coverage for some specified substantial second part of the damages, with any remaining damages to be considered by the national legislation. Thus, the costs of an incident or accident are fully internalized in the costs borne by the nuclear plant owners. Externalities of energy are not limited to environmental and health related impacts, but may result also from macro-economic, policy or strategic factors not reflected

  14. Nuclear power generation and nuclear fuel

    International Nuclear Information System (INIS)

    Okajima, Yasujiro

    1985-01-01

    As of June 30, 1984, in 25 countries, 311 nuclear power plants of about 209 million kW were in operation. In Japan, 27 plants of about 19 million kW were in operation, and Japan ranks fourth in the world. The present state of nuclear power generation and nuclear fuel cycle is explained. The total uranium resources in the free world which can be mined at the cost below $130/kgU are about 3.67 million t, and it was estimated that the demand up to about 2015 would be able to be met. But it is considered also that the demand and supply of uranium in the world may become tight at the end of 1980s. The supply of uranium to Japan is ensured up to about 1995, and the yearly supply of 3000 st U 3 O 8 is expected in the latter half of 1990s. The refining, conversion and enrichment of uranium are described. In Japan, a pilot enrichment plant consisting of 7000 centrifuges has the capacity of about 50 t SWU/year. UO 2 fuel assemblies for LWRs, the working of Zircaloy, the fabrication of fuel assemblies, the quality assurance of nuclear fuel, the behavior of UO 2 fuel, the grading-up of LWRs and nuclear fuel, and the nuclear fuel business in Japan are reported. The reprocessing of spent fuel and plutonium fuel are described. (Kako, I.)

  15. Fuzzy logic control for improved pressurizer systems in nuclear power plants

    International Nuclear Information System (INIS)

    Brown, Chris; Gabbar, Hossam A.

    2014-01-01

    Highlights: • Improved performance of the pressurizer system in a CANDU nuclear power plant (NPP). • Inventory control for the pressurizer system in NPP. • Compare fuzzy logic with PID in pressurizer system in NPP. • Develop a fuzzy controller to regulate the pressurizer inventory control. • Compare control performance with current proportional controller used at NPP. - Abstract: The pressurizer system in a CANDU nuclear power plant is responsible for maintaining the pressure of the primary heat transport system to ensure the plant is operated within its safe operating envelope. The inventory control for the pressurizer system use a combination of level sensors, feed valves and bleed valves to ensure that there is adequate room in the pressurizer to accommodate any swell or shrinkage in the PHT system. The Darlington Nuclear Generating Station (DNGS) in Ontario, Canada currently uses a proportional controller for the bleed and feed valves to regulate the pressurizer inventory control which can result in large coolant level overshoot along with excessive settling times. The purpose of this paper is to develop a fuzzy controller to regulate the pressurizer inventory control and compare its performance to the current proportional controller used at DNGS. The simulation of the pressurizer inventory control system shows the fuzzy controller performs better than the proportional controller in terms of settling time and overshoot

  16. CO2 emissions of nuclear electricity generation

    International Nuclear Information System (INIS)

    Wissel, Steffen; Mayer-Spohn, Oliver; Fahl, Ulrich; Blesl, Markus; Voss, Alfred

    2008-01-01

    A survey of LCA studies on nuclear electricity generation revealed life cycle CO 2 emissions ranging between 3 g/kWhe to 60 g/kWhe and above. Firstly, this paper points out the discrepancies in studies by estimating the CO 2 emissions of nuclear power generation. Secondly, the paper sets out to provide critical review of future developments of the fuel cycle for light water reactors and illustrates the impact of uncertainties on the specific CO 2 emissions of nuclear electricity generation. Each step in the fuel cycle will be considered and with regard to the CO 2 emissions analysed. Thereby different assumptions and uncertainty levels are determined for the nuclear fuel cycle. With the impacts of low uranium ore grades for mining and milling as well as higher burn-up rates future fuel characteristics are considered. Sensitivity analyses are performed for all fuel processing steps, for different technical specifications of light water reactors as well as for further external frame conditions. (authors)

  17. Nuclear performance standards: Promoting efficient generation

    International Nuclear Information System (INIS)

    Nagelhout, M.

    1990-01-01

    Nuclear plant performance standards are designed to share the risks of operation associated with nuclear generation. Such standards often shift risks from ratepayers to utility shareholders, even without a finding of imprudence or mismanagement. The rationale underlying nuclear performance standards is that ratepayers should not be responsible for excessive replacement power costs incurred as a result of unreasonable decisions by utility management, especially because the high fixed costs of nuclear plants are already included in base rates. In addition, performance standards can be designed to provide incentives to reward utilities that achieve superior nuclear performance, for the benefit of both ratepayers and shareholders

  18. Future perspective of cost for nuclear power generation

    International Nuclear Information System (INIS)

    Maeda, Ichiro

    1988-01-01

    The report presents and discussed results of evaluation of the cost for power generation in this and forthcoming years on the basis of an analysis of the current fuel prices and the economics of various power sources. Calculations show that nuclear power generation at present is inferior to coal-firing power generation in terms of required costs, but can become superior in the future due to an increased burn-up and reduced construction cost. Investigations are made of possible contributions of future technical improvements to reduction in the overall cost. Results suggest that nuclear power generation will be the most efficient among the various electric sources because of its technology-intensive feature. Development of improved light water reactors is of special importance to achieve a high burn-up and reduced construction costs. In general, the fixed cost accounts for a large part of the overall nuclear power generation cost, indicating that a reduction in construction cost can greatly increase the economic efficiency. Changes in the yen's exchange rate seem to have little effect on the economics of nuclear power generation, which represents another favorable aspect of this type of energy. (Nogami, K.)

  19. World nuclear generating capacity 1993/94

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    This article is the annual summary of world nuclear generating capacity for 1994. A global summary is first provided, reviewing total installed capacity and growth in installed capacity over the next five years. A more detailed discussion of the nuclear efforts in 34 countries follows, with a tabular listing of nuclear projects in each of these countries. The listing includes reactor supplier, reactor type, size, current status, and date of commercial operation

  20. Outlook of nuclear power generation and international situation

    Energy Technology Data Exchange (ETDEWEB)

    Ekulund, S [International Atomic Energy Agency, Vienna (Austria)

    1978-01-01

    Nuclear power generation is advancing at rapid rate over the world, without any major accident. For the base load of electric power, when choice is made between nuclear energy and petroleum, Nuclear energy has larger economic advantages over petroleum as compared with the days before the oil crisis. The costs of its fuel and fuel cycle technology are reasonable. However, nuclear power generation currently has a number of problems. What causes this uncertainty is not technological, but political, i.e. governmental policy changes, and this is based on the apprehension about nuclear proliferation. What is necessary is to strengthen the existing international framework of nuclear nonproliferation. In this respect, IAEA through comprehensive safeguards will make contributions largely to reduction of the political uncertainty. It is important that the new initiatives toward international nuclear cooperation should eliminate the current trends of restraint and denial.

  1. Nigeria nuclear power generation programme: Suggested way forward

    International Nuclear Information System (INIS)

    Adesanmi, C.A.

    2007-01-01

    It has now been established worldwide that nuclear power generation is needed to meet growing energy demands. The gases emitted from fossil fuel have serious adverse effects on the environment. The message from the 50th Annual General Conference of the International Atomic Energy Agency (IAEA) held in Vienna, September 2006 was very clear on this issue. There was a unanimous support for more nuclear power generation to meet the world energy demand. All the member states that can afford the nuclear power technology and willing to abide by the international regulations and safeguards were encouraged to do so. The requirements to participate in the nuclear power generation programme are political will and organized diplomacy, legislative and statutory framework, international safety obligations, institutional framework, public acceptability, capacity building and technology transfer, environmental concern , waste management and financing. Nigeria's performance on all the criteria was evaluated and found satisfactory. All these coupled with Nigeria's dire need for more power and better energy mix, are sufficient and undisputable reasons for the whole world to support Nigeria nuclear power generation programme. Definitely the programme poses serious challenges to the Nigerian Physicists. Therefore, Departments of Physics should endeavour to include nuclear physics option in their programme and work in collaboration with the faculty of Engineering in their various tertiary institutions in order to attain the necessary critical human capacity that will be needed to man the nuclear power industry within the next 10 years

  2. Life cycle analysis of advanced nuclear power generation technologies

    International Nuclear Information System (INIS)

    Uchiyama, Yoji; Yokoyama, Hayaichi

    1996-01-01

    In this research, as for light water reactors and fast breeder reactors, for the object of all the processes from the mining, transport and refining of fuel, electric power generation to the treatment and disposal of waste, the amount of energy input and the quantity of CO 2 emission over the life cycle were analyzed, and regarding the influence that the technical progress of nuclear power generation exerted to environment, the effect of improvement was elucidated. Attention has been paid to nuclear power generation as its CO 2 emission is least, and the effect of global warming is smallest. In order to reduce the quantity of radioactive waste generation in LWRs and the cost of fuel cycle, and to extend the operation cycle, the technical development for heightening fuel burnup is in progress. The process of investigation of the new technologies of nuclear power generation taken up in this research is described. The analysis of the energy balance of various power generation methods is discussed. In the case of pluthermal process, the improvement of energy balance ratio is dependent on uranium enrichment technology. Nuclear power generation requires much materials and energy for the construction, and emits CO 2 indirectly. The CO 2 unit emission based on the analysis of energy balance was determined for the new technologies of nuclear power generation, and the results are shown. (K.I.)

  3. Algorithm for the generation of nuclear spin species and nuclear spin statistical weights

    International Nuclear Information System (INIS)

    Balasubramanian, K.

    1982-01-01

    A set of algorithms for the computer generation of nuclear spin species and nuclear spin statistical weights potentially useful in molecular spectroscopy is developed. These algorithms generate the nuclear spin species from group structures known as generalized character cycle indices (GCCIs). Thus the required input for these algorithms is just the set of all GCCIs for the symmetry group of the molecule which can be computed easily from the character table. The algorithms are executed and illustrated with examples

  4. Power generation costs. Coal - nuclear power

    International Nuclear Information System (INIS)

    1979-01-01

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

  5. Human factors issues in fuel handling

    Energy Technology Data Exchange (ETDEWEB)

    Beattie, J D; Iwasa-Madge, K M; Tucker, D A [Humansystems Inc., Milton, ON (Canada)

    1994-12-31

    The staff of the Atomic Energy Control Board wish to further their understanding of human factors issues of potential concern associated with fuel handling in CANDU nuclear power stations. This study contributes to that objective by analysing the role of human performance in the overall fuel handling process at Ontario Hydro`s Darlington Nuclear Generating Station, and reporting findings in several areas. A number of issues are identified in the areas of design, operating and maintenance practices, and the organizational and management environment. 1 fig., 4 tabs., 19 refs.

  6. Liberation of electric power and nuclear power generation

    International Nuclear Information System (INIS)

    Yajima, Masayuki

    2000-01-01

    In Japan, as the Rule on Electric Business was revised after an interval of 35 years in 1995, and a competitive bid on new electric source was adopted after 1996 fiscal year, investigation on further competition introduction to electric power market was begun by establishment of the Basic Group of the Electric Business Council in 1997. By a report proposed on January, 1999 by the Group, the Rule was revised again on March, 1999 to start a partial liberation or retail of the electric power from March, 2000. From a viewpoint of energy security and for solution of global environmental problem in Japan it has been decided to positively promote nuclear power in future. Therefore, it is necessary to investigate how the competition introduction affects to development of nuclear power generation and what is a market liberation model capable of harmonizing with the development on liberation of electric power market. Here was elucidated on effect of the introduction on previous and future nuclear power generation, after introducing new aspects of nuclear power problems and investigating characteristic points and investment risks specific to the nuclear power generation. And, by investigating some possibilities to development of nuclear power generation under liberation models of each market, an implication was shown on how to be future liberation on electric power market in Japan. (G.K.)

  7. Nuclear power generation cost methodology

    International Nuclear Information System (INIS)

    Delene, J.G.; Bowers, H.I.

    1980-08-01

    A simplified calculational procedure for the estimation of nuclear power generation cost is outlined. The report contains a discussion of the various components of power generation cost and basic equations for calculating that cost. An example calculation is given. The basis of the fixed-charge rate, the derivation of the levelized fuel cycle cost equation, and the heavy water charge rate are included as appendixes

  8. Nuclear power generation as seen from construction aspect

    International Nuclear Information System (INIS)

    Osaki, Yorihiko

    1984-01-01

    The measures to vitalize atomic energy industry in low economical growth age are grasped from the viewpoint of heightening the quality of technology, and the improvement of the economical efficiency of nuclear power generation as seen from construction aspect is discussed. By 2000, the nuclear power generation in Japan will be increased by about four times to 62 million kW, and the proportion of nuclear power increases steadily. Recently, the nuclear power stations in Japan have been stably operated at high level, and the capacity ratio has exceeded 70 %. However, the power generation cost tends to rise, and it is feared that the economical advantage over thermal power will be lost. Recently, the construction cost of nuclear power plants has continued to rise, which causes the high cost of nuclear power. The reason of the high construction cost is in short too much quantity of materials and long construction period. As the proposal to reduce the construction cost, three stages of the rationalization are discussed, such as the rationalization of simulated earthquake for design and the improvement of reactor building design. The promotion of technical development is indispensable for the cost reduction. (Kako, I.)

  9. Nuclear power generating costs

    International Nuclear Information System (INIS)

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

    1983-01-01

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

  10. Prediction of future dispute concerning nuclear power generation

    International Nuclear Information System (INIS)

    1981-04-01

    This investigation is the third research on the public acceptance of nuclear power generation by the National Congress on Social Economics. In this study, how the energy dispute including that concerning nuclear power generation will develop in 1980s and 1990s, how the form of dispute and the point of controversy will change, were predicted. Though the maintenance of the concord of groups strongly regulates the behavior of people, recently they have become to exercise individual rights frequently. The transition to the society of dispute is the natural result of the modernization of society and the increase of richness. The proper prediction of social problems and the planning and execution of proper countermeasures are very important. The background, objective, basic viewpoint, range and procedure of this investigation, the change of social dispute, the history of the dispute concerning nuclear power generation, the basic viewpoint in the prediction of the dispute concerning nuclear power generation, the social situation in 1980s, the prediction and avoidance of the dispute in view of social and energy situations, and the fundamental strategy for seeking a clue to the solution in 1980s and 1990s are described. The establishment of neutral mediation organs and the flexible technologies of nuclear reactors are necessary. (Kako, I.)

  11. Process of public attitudes toward nuclear power generation

    International Nuclear Information System (INIS)

    Shimooka, Hiroshi

    1993-01-01

    The Japanese public attitudes toward nuclear power generation had become negative year by year. After the Chernobyl accident, a percentage of the unfavorable respondent toward nuclear power generation has dramatically increased, and a new type of anti-nuclear movement has been observed. On the basis of our public opinion polls, the reason for this increase was found to be primarily decrease of sense of usefulness rather than increase of sense of nueasiness about nuclear safety. Particularly, social factors (change of life style, progress of civilian consciousness, credibility of the existing institutional system etc.) have influence on the attitude of either pro or anti-nuclear. Based on the above observation, we have inferred that process of the public attitudes has two flows arising from the above social factors, one is the usefulness and the other is the easiness about nuclear safety, and have formulated a model representing the process of public attitudes toward nuclear power. (author)

  12. Development of generation IV nuclear energy systems

    International Nuclear Information System (INIS)

    Matsui, Kazuaki; Oka, Yoshiaki; Ogawa, Masuro; Ichimiya, Masakazu; Noda, Hiroshi

    2003-01-01

    The fifth 'Generation IV International Forum (GIF), Policy Group Meetings' was held at the Zen-Nikku Hotel in Tokyo, on September 19-20, 2002, under participations of Abraham, Secretary of DOE in U.S.A., Columbani, Secretary of CEA in France, Fujiie, Chairman of CAE in Japan, Kano, Parliamental Minister of MIS in Japan, and so on. Ten nations entering GIF (Argentina, Brazil, Canada, France, Japan, Korea, South Africa, Switzerland, U.K., and U.S.A.) selected six next generation nuclear energy concepts for objects of international cooperative research and development aiming at its practice by 2030. These concepts applicable to not only power generation, but also hydrogen production, sea water purification, and so on, are sodium liquid metal cooled reactor (Japan), high temperature gas cooled reactor (France), Super-critical pressure water cooled reactor (SCWR: Canada), Lead metal cooled reactor (Switzerland), Gas cooled fast reactor (U.S.A.), and molten salts reactor. On the generation IV nuclear reactor systems aiming to further upgrade their sustainability, safety, economical efficiency, and nuclear non proliferation, the 'Plans on Technical Development' (Road-map) to decide priority of their R and Ds has been cooperatively discussed under frameworks of international research cooperation by the GIF members nations. Here were shared descriptions on nuclear fuel cycle as a remise of technical evaluation and adopted concepts by Japanese participants contributing to making up the Road-map. (G.K.)

  13. Prerequisites for successful nuclear generation in southern Africa

    International Nuclear Information System (INIS)

    Semark, P.

    1990-01-01

    The prerequisites and the requisites for successful nuclear powered electricity generation in southern Africa are explored. There are four elements essential to success, namely, the mission or vision; the appropriate means; the right and sufficient time, and the skilled, committed executor. The ongoing success of nuclear powered electricity generation in South Africa is discussed in the light of these four elements. 2 ills

  14. 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.

  15. Risk of nuclear power generation as business (continued)

    International Nuclear Information System (INIS)

    Sato, Satoshi

    2017-01-01

    This paper described the following: (1) fleet formation of power companies that operate nuclear power plants in the U.S., (2) collaboration, competition, and merger between plant makers, (3) stress corrosion cracking of stream generators for PWR and their thin heat transfer tubes, especially stress corrosion cracking under primary cooling water environment (PWSCC), and (4) replacement project from Inconel 600 MA to Inconel 600 TT or 690 TT of steam generator thin heat transfer tubes of PWR plants in the U.S. and others. In addition, it described the troubles at San Onofre Nuclear Power Station in California: wear of steam generator thin tubes of Units 2 and 3, and leakage from primary system to secondary system of Unit 3, and permanent shutdown. It also described the detail of damages compensation talks between South California Edison Company that operates San Onofre nuclear power plant and Mitsubishi Heavy Industries Ltd. which supplied the steam generator. Although the operation of the 1.7 million kW plant became impossible due to the bud shedding of nuclear power renaissance, these troubles might have saved the nightmare of drifting on the way. (A.O.)

  16. Relationship between students' interests in science and attitudes toward nuclear power generation

    International Nuclear Information System (INIS)

    Komiya, Izumi; Torii, Hiroyuki; Fujii, Yasuhiko; Hayashizaki, Noriyosu

    2008-01-01

    In order to study the following two points, we conducted an attitude survey among senior high school students. Study 1 The differences in attitudes between nuclear power generation and other science and technologies. Study 2 The relationship between student's interest in science and attitudes toward nuclear power generation. In the questionnaire, the attitude toward nuclear power generation consisted of four questions: (1) pros and cons, (2) safety, (3) necessity, (4) reliability of scientists and engineers who are involved in nuclear power; and we treat four science and technology issues: (1) genetically modified foods, (2) nuclear power generation, (3) humanoid and pet robots, (4) crone technology. From study 1, on attitude to security toward nuclear power generation, about 80% of respondents answered negatively and on attitude to necessity toward it, about 75% of respondents answered positively. Therefore, we found that the structure of attitude was complicated and that it was specific to nuclear power generation. From study 2, we found students' interests in science that influence the attitude toward nuclear power generation. (author)

  17. Nuclear data banks generation by interpolation

    International Nuclear Information System (INIS)

    Castillo M, J. A.

    1999-01-01

    Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesser resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, use to generate Nuclear Data Banks employing bicubic polynominal interpolation, taking as independent variables the uranium and gadolinia percents. Two proposal were worked, applying in both cases the finite element method, using one element with 16 nodes to carry out the interpolation. In the first proposals the canonic base was employed, to obtain the interpolating polynomial and later, the corresponding linear equation systems. In the solution of this systems the Gaussian elimination methods with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validation tests, a comparison was made between the values obtained with INTPOLBI and INTERTEG (create at the Instituto de Investigaciones Electricas (MX) with the same purpose) codes, and Data Banks created through the conventional process, that is, with nuclear codes normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks

  18. Three-dimensional modeling of nuclear steam generator

    International Nuclear Information System (INIS)

    Bogdan, Z.; Afgan, N.

    1985-01-01

    In this paper mathematical model for steady-state simulation of thermodynamic and hydraulic behaviour of U-tube nuclear steam generator is described. The model predicts three-dimensional distribution of temperatures, pressures, steam qualities and velocities in the steam generator secondary loop. In this analysis homogeneous two phase flow model is utilized. Foe purpose of the computer implementation of the mathematical model, a special flow distribution code NUGEN was developed. Calculations are performed with the input data and geometrical characteristics related to the D-4 (westinghouse) model of U-tube nuclear steam generator built in Krsko, operating under 100% load conditions. Results are shown in diagrams giving spatial distribution of pertinent variables in the secondary loop. (author)

  19. Recommendations relating to safety-critical real-time software in nuclear power plants

    International Nuclear Information System (INIS)

    1992-01-01

    The Advisory Committee on Nuclear Safety (ACNS) has reviewed safety issues associated with the software for the digital computers in the safety shutdown systems for the Darlington NGS. From this review the ACNS has developed four recommendations for safety-critical real-time software in nuclear power plants. These recommendations cover: the completion of the present efforts to develop an overall standard and sub-tier standards for safety-critical real-time software; the preparation of schedules and lists of responsibilities for this development; the concentration of AECB efforts on ensuring the scrutability of safety-critical real-time software; and, the collection of data on reliability and causes of failure (error) of safety-critical real-time software systems and on the probability and causes of common-mode failures (errors). (9 refs.)

  20. The Birth of Nuclear-Generated Electricity

    Science.gov (United States)

    1999-09-01

    The Experimental Breeder Reactor-I (EBR-I), built in Idaho in 1949, generated the first usable electricity from nuclear power on December 20, 1951. More importantly, the reactor was used to prove that it was possible to create more nuclear fuel in the reactor than it consumed during operation -- fuel breeding. The EBR-I facility is now a National Historic Landmark open to the public.

  1. The Birth of Nuclear-Generated Electricity

    International Nuclear Information System (INIS)

    Claflin, D.J. POC

    1999-01-01

    The Experimental Breeder Reactor-I (EBR-I), built in Idaho in 1949, generated the first usable electricity from nuclear power on December 20, 1951. More importantly, the reactor was used to prove that it was possible to create more nuclear fuel in the reactor than it consumed during operation -- fuel breeding. The EBR-I facility is now a National Historic Landmark open to the public

  2. Promotion of public awareness relating nuclear power in young generation

    International Nuclear Information System (INIS)

    Kobayashi, Yoko

    2011-01-01

    Although nuclear power presents problems of waste, safety and non-proliferation, many people understand that it is an essential energy for addressing the global climate and reducing CO2. However, a vague negative-image to the radiation and nuclear power is deep-rooted among the public. Young generation is not an exception. It is very important to transfer many information from the experienced generation in the industry to young generations. In this paper, the research that applied the information intelligence to nuclear power, which involves of the nuclear fuel cycle, and the communication related activities for the social acceptance and improvement. (author)

  3. World nuclear power generation market and prospects of industry reorganization

    International Nuclear Information System (INIS)

    Murakami, Tomoko

    2007-01-01

    In late years there are many trends placing nuclear energy with important energy in various countries in the world due to a remarkable rise to an energy price, importance of energy security and a surge of recognition to a global environment problem. Overseas nuclear industry's acquisition by a Japanese nuclear power plant maker and its capital or business tie-up with an overseas company, were announced in succession in 2006. A nuclear power plant maker has played an extremely important role supporting wide technology in all stages of a design, construction, operation and maintenance in a nuclear power generation business. After having surveyed the recent trend of world nuclear power generation situation, a background and the summary of these acquisition/tie-ups made were investigated and analyzed to consider the influence that movement of such an industry gives a world nuclear power generation market. (T. Tanaka)

  4. Is nuclear energy power generation more dangerous than power generation by wind and solar energy

    Energy Technology Data Exchange (ETDEWEB)

    Ding, Y

    1979-03-01

    Since the occurrence of the petroleum crisis, many countries have devoted a great deal of effort to search for substitute energy sources. Aside from nuclear energy, forms of power generation with wind, solar energy, and geothermal energy have all been actually adopted in one place or another. Most recently, a research report was published by the Canadian Bureau of Nuclear Energy Management stating that the use of wind and solar energy to generate electricity is much more dangerous than power generation with nuclear energy. When mining, transportation, machine manufacturing, etc. are included in the process of producing unit power, i.e. kilowatt/year, the data of various risks of death, injury, and diseases are computed in terms of man/day losses by the bureau. They indicate that of the ten forms of power generation, the danger is the least with natural gas, only about a 6 man/day, and nuclear energy is the next least dangerous, about 10 man/day. The danger of using temperature differential of sea water to generate electricity is about 25 man/day, and the most dangerous form of power generation is coal, amounting to three thousand man/day.

  5. New nuclear power generation in the UK: Cost benefit analysis

    International Nuclear Information System (INIS)

    Kennedy, David

    2007-01-01

    This paper provides an economic analysis of possible nuclear new build in the UK. It compares costs and benefits of nuclear new build against conventional gas-fired generation and low carbon technologies (CCS, wind, etc.). A range of scenarios are considered to allow for uncertainty as regards nuclear and other technology costs, gas prices and carbon prices. In the base case, the analysis suggests that there is a small cost penalty for new nuclear generation relative to conventional gas-fired generation, but that this is offset by environmental and security of supply benefits. More generally nuclear new build has a positive net benefit for a range of plausible nuclear costs, gas prices and carbon prices. This supports the UK policy of developing an enabling framework for nuclear new build in a market-based context. To the extent that assumptions in the analysis are not borne out in reality (e.g. as regards nuclear cost), this is a no regrets policy, given that the market would not invest in nuclear if it is prohibitively costly. (author)

  6. European Nuclear Young Generation. Position Paper on Nuclear Energy and the Environment

    International Nuclear Information System (INIS)

    2015-01-01

    The world population is continually growing; from 1 billion in 1800 to 7 billion in 2011, we are expected to reach 10 billion by the end of the 21. century. To sustain this population growth, an increased energy supply is required to provide sufficient clean water, health care, education, food, shelter, communication and transportation. Whereas energy access is today guaranteed in OECD countries, around 1.3 billion people still live without sufficient access to energy. Affordable and reliable sources of energy are required to sustain our development. At the same time, it is now acknowledged by the scientific community that human activities are mainly responsible for climate change. Our growing energy-intensive societies are accelerating climate change and its associated consequences: rise of ocean levels, more frequent extreme meteorological phenomena and massive loss of biodiversity; consequences that must be prevented at all costs. We need sustainable, affordable, reliable and safe sources of energy. It is our responsibility to promote low carbon energies and responsible consumer behaviors that will prevent social and environmental disasters for current and future generations. Nuclear, a solution? Nuclear power is regarded by many as being environmentally friendly. Nuclear power plants have nearly no CO 2 emission, while the nuclear industry is recognized as one of the safest industries; backed by stringent safety standards, transparency culture and international cooperation based on an evolution of lessons learnt from a variety of operations. Moreover, solutions for decommissioning and waste management exist and are already implemented in most European countries. Nuclear power is affordable and reliable. Nuclear power has one of the lowest production costs within the energy market, this stems from production costs which mainly depend upon the investment costs; fuel and operating costs have little impact on the price of nuclear electricity. Nuclear generation is

  7. Case law

    International Nuclear Information System (INIS)

    2012-01-01

    This section gathers the following case laws: 1 - Canada: Judicial review of Darlington new nuclear power plant project; Appeal decision upholding criminal convictions related to attempt to export nuclear-related dual-use items to Iran: Her Majesty the Queen V. Yadegari; 2 - European Commission: Greenland cases; 3 - France: Chernobyl accident - decision of dismissal of the Court of Appeal of Paris; 4 - Slovak Republic: Aarhus Convention compliance update; 5 - United States: Judgement of a US court of appeals upholding the NRC's dismissal of challenges to the renewal of the operating licence for Oyster Creek Nuclear Generating Station; reexamination of the project of high-level waste disposal site at Yucca Mountain

  8. Future of nuclear energy for electricity generation in Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Maiorino, Jose R.; Moreira, Joao M.L.; Carajlescov, Pedro, E-mail: joserubens.maiorino@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: pedro.carajlescov@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

    2015-07-01

    We discuss in this paper the medium- and long- terms evolution of nuclear power in Brazil considering official governmental studies and reports prepared by research groups. The documents reviewed include the national energy balance (BEN, 2014), the short-term planning (PDEE, 2023) and long-term planning (PNE-2030) documents emitted by EPE, and studies conducted by independent institutions and researchers. The studies consider different scenarios regarding gross national product growth and institutional development for the country and conclude that nuclear power should increase its role in Brazil. The generation matrix should diversity by 2030 and 2040 with hydropower decreasing its share from today's 70 % to values between 47 and 57 %. Nuclear power is considered a viable alternative for base load electricity generation in Brazil; to reduce generation risks during dry seasons, and to facilitate the operation of the whole power generation system. The share of nuclear power may reach values between 8 % and 15 % by 2040 according to different scenarios. To meet such growth and facilitate new investments, it is necessary to change the legal framework of the sector, and allow private ownership of enterprises to build and operate nuclear power plants in the country. (author)

  9. Future of nuclear energy for electricity generation in Brazil

    International Nuclear Information System (INIS)

    Maiorino, Jose R.; Moreira, Joao M.L.; Carajlescov, Pedro

    2015-01-01

    We discuss in this paper the medium- and long- terms evolution of nuclear power in Brazil considering official governmental studies and reports prepared by research groups. The documents reviewed include the national energy balance (BEN, 2014), the short-term planning (PDEE, 2023) and long-term planning (PNE-2030) documents emitted by EPE, and studies conducted by independent institutions and researchers. The studies consider different scenarios regarding gross national product growth and institutional development for the country and conclude that nuclear power should increase its role in Brazil. The generation matrix should diversity by 2030 and 2040 with hydropower decreasing its share from today's 70 % to values between 47 and 57 %. Nuclear power is considered a viable alternative for base load electricity generation in Brazil; to reduce generation risks during dry seasons, and to facilitate the operation of the whole power generation system. The share of nuclear power may reach values between 8 % and 15 % by 2040 according to different scenarios. To meet such growth and facilitate new investments, it is necessary to change the legal framework of the sector, and allow private ownership of enterprises to build and operate nuclear power plants in the country. (author)

  10. Cost of nuclear power generation judged by power rate

    International Nuclear Information System (INIS)

    Hirai, Takaharu

    1981-01-01

    According to estimation guidance, power rates in general are the proper cost plus the specific compensation and adjustment addition. However, the current system of power rates is of power-source development promotion type involving its tax. The structure of power rate determination must be restudied now especially in connection of nuclear power generation. The cost of nuclear power generation as viewed from power rate is discussed as follows: the fear of military application of power plants, rising plant construction costs, the loophole in fuel cost calculation, unreasonable unit power cost, depreciation and repair cost, business compensation, undue business compensation in nuclear power, the costs of nuclear waste management, doubt concerning nuclear power cost, personnel, pumping-up and power transmission costs in nuclear power, energy balance analysis, nuclear power viewed in entropy, the suppression of power consumption. (J.P.N.)

  11. Treatment of Nuclear Data Covariance Information in Sample Generation

    Energy Technology Data Exchange (ETDEWEB)

    Swiler, Laura Painton [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Adams, Brian M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wieselquist, William [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

    2017-10-01

    This report summarizes a NEAMS (Nuclear Energy Advanced Modeling and Simulation) project focused on developing a sampling capability that can handle the challenges of generating samples from nuclear cross-section data. The covariance information between energy groups tends to be very ill-conditioned and thus poses a problem using traditional methods for generated correlated samples. This report outlines a method that addresses the sample generation from cross-section matrices.

  12. Treatment of Nuclear Data Covariance Information in Sample Generation

    International Nuclear Information System (INIS)

    Swiler, Laura Painton; Adams, Brian M.; Wieselquist, William

    2017-01-01

    This report summarizes a NEAMS (Nuclear Energy Advanced Modeling and Simulation) project focused on developing a sampling capability that can handle the challenges of generating samples from nuclear cross-section data. The covariance information between energy groups tends to be very ill-conditioned and thus poses a problem using traditional methods for generated correlated samples. This report outlines a method that addresses the sample generation from cross-section matrices.

  13. The Japanese attitude towards nuclear power generation. Changes as seen through time series

    International Nuclear Information System (INIS)

    Kitada, Atsuko; Hayashi, Chikio

    1999-01-01

    This study is intended to determine people's attitudes toward nuclear power generation, shedding light on the changed and unchanged structures of attitudes by comparing data on nuclear power generation for 1993 and 1998. Although some nuclear facility accidents occurred during the last five years, public attitudes toward nuclear power generation remain almost the same. For the utilization of nuclear power generation, there was a slight increase in passive affirmation. The percentage of active affirmation was less than 10 percent, but if passive affirmation is included a high percentage exceeding 70 percent acknowledged the utilization of nuclear power. It was found that people's attitudes toward the utilization of nuclear power became slightly more positive in 1998 than in 1993. The difference was found in the general measure of attitudes based on many questions about nuclear power generation, and in the importance and the utility of nuclear power generation including the purpose of nuclear power generation. People are not conscious of the anxiety about nuclear power generation in ordinary life. However, when people were made to think about nuclear power generation, the degree of anxiety increases even if provided with data that prove its safety. On the other hand, it was revealed that the degree of anxiety about nuclear facility accidents remains the same in the last five years, that is, it has not increased, although a growing interest in the disposal and treatment of radioactive wastes was seen. As a result of a comparison of the structure of attitudes, based on the study by Hayashi 1994, it was found that the group that had no interest in nuclear power generation offered the most noticeable features in answering pattern in both 1993 and 1998. Moreover, it was found also that the latter group of respondents were characterized by a little opportunity to have information. A similarity in the relationship between people's attitudes toward nuclear power generation

  14. Literature study of volatile radioiodine release from ion-exchange resins during transportation

    International Nuclear Information System (INIS)

    Wren, J.C.

    1991-02-01

    A transport package is currently being developed by Ontario Hydro to carry used filters and ion-exchange columns from the Pickering and Darlington Nuclear Generating Stations to the Bruce Nuclear Generating Station for disposal. The main reason that the transport package must be licensed is the possibility that volatile radionuclides being transported in the package might be released during transport accidents. Of particular concern is the iodine that might become volatile due to the degradation of the ion exchange resin. This report reviews the literature on the thermal and radiolytic degradation of ion exchange resins and provides calculations to estimate the fraction of volatile iodine as a function of time under postulated accident conditions

  15. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    International Nuclear Information System (INIS)

    Demick, L.E.

    2011-01-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  16. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  17. Business environment change and decision making mechanism of nuclear generators

    International Nuclear Information System (INIS)

    Yamashita, Hiroko

    2010-01-01

    Change magnitude of business environment for Japanese nuclear generators is significant. It is rapidly growing in the last several years. There are possibilities that the change might impact to management model of nuclear generators. In the paper, the impact to management model, especially, decision making mechanism of the generators is discussed. (author)

  18. Young generation in Romanian nuclear system - Romanian nuclear organizations implication in nuclear knowledge management at University 'Politehnica' of Bucharest - Results and expectations

    International Nuclear Information System (INIS)

    Ghizdeanu, E.N.; Dumitrescu, M.C.; Budu, A.R.; Pavelescu, A.O.

    2004-01-01

    The knowledge management should be assumed by the major players within the nuclear community: government, industry and university. Starting from these problems this article gives an overview about Romanian nuclear knowledge management and the Young Generation implications. In Romania there are many government and non-government nuclear institutions such: CNCAN (Romanian Regulatory Body), ROMATOM (Romanian Atomic Forum), AREN (Romanian 'Nuclear Energy' Association), and companies: SNN ('Nuclearelectrica' SA National Company), CITON (Centre of Technology and Engineering for Nuclear Projects), SCN (Institute for Nuclear Research), ROMAG - PROD (Romanian Heavy Water Plant). All these institutes and companies are sustaining the national nuclear program and promoting the new technologies in the nuclear industry according with CNCAN and ROMATOM regulations. University 'POLITEHNICA' of Bucharest - Power Engineering Faculty - through Nuclear Power Plant Department is the promoter of nuclear knowledge management. It is implied in assuring and maintaining a high-quality training for young staff. Young Generation is implicated in nuclear knowledge management through University 'Politehnica' of Bucharest - Power Engineering Faculty - Nuclear Power Plant Department and AREN (Romanian 'Nuclear Energy' Association). Young Generation Department has special educational programs for attracting and supporting students. It provides adequate information and interacts with potential students. Moreover the article gives results about Romanian nuclear engineers since 1970 till now. An analysis of these data is done. Also it is discussed how University 'Politehnica' of Bucharest, the Romanian Government and the Industry work together to co-ordinate more effectively their efforts to encourage the young generation. (author)

  19. Generation IV nuclear plant design strategies

    International Nuclear Information System (INIS)

    Altin, V.

    2007-01-01

    In this presentation Generation IV nuclear reactor design criteria are examined under the light of known nuclear properties of fissile and fertile nuclei. Their conflicting nature is elucidated along with the resulting inevitability of a multitude of designs. The designs selected as candidates for further development are evaluated with respect to their potential to serve the different design criteria, thereby revealing their more difficult aspects of realization and the strong research challenges lying ahead

  20. A realistic way for graduating from nuclear power generation

    International Nuclear Information System (INIS)

    Kikkawa, Takeo

    2012-01-01

    After Fukushima Daiichi Nuclear Power Plant accident, fundamental reform of Japanese energy policy was under way. As for reform of power generation share for the future, nuclear power share should be decided by three independent elements of the progress: (1) extension of power generation using renewable energy, (2) reduction of power usage by electricity saving and (3) technical innovation toward zero emission of coal-fired thermal power. In 2030, nuclear power share would still remain about 20% obtained by the 'subtraction' but in the long run nuclear power would be shutdown judging from difficulties in solution of backend problems of spent fuel disposal. (T. Tanaka)

  1. Next generation advanced nuclear reactor designs

    International Nuclear Information System (INIS)

    Turgut, M. H.

    2009-01-01

    Growing energy demand by technological developments and the increase of the world population and gradually diminishing energy resources made nuclear power an indispensable option. The renewable energy sources like solar, wind and geothermal may be suited to meet some local needs. Environment friendly nuclear energy which is a suitable solution to large scale demands tends to develop highly economical, advanced next generation reactors by incorporating technological developments and years of operating experience. The enhancement of safety and reliability, facilitation of maintainability, impeccable compatibility with the environment are the goals of the new generation reactors. The protection of the investment and property is considered as well as the protection of the environment and mankind. They became economically attractive compared to fossil-fired units by the use of standard designs, replacing some active systems by passive, reducing construction time and increasing the operation lifetime. The evolutionary designs were introduced at first by ameliorating the conventional plants, than revolutionary systems which are denoted as generation IV were verged to meet future needs. The investigations on the advanced, proliferation resistant fuel cycle technologies were initiated to minimize the radioactive waste burden by using new generation fast reactors and ADS transmuters.

  2. Economic analysis of nuclear power generation

    International Nuclear Information System (INIS)

    Lee, Young Gun; Lee, Han Myung; Song, Ki Dong; Lee, Man Ki; Kim, Seung Su; Moon, Kee Hwan; Chung, Whan Sam; Kim, Kyung Pyo; Cho, Sang Goo

    1992-01-01

    The purpose of this study is to clarify the role of nuclear power generation under the circumstances of growing concerns about environmental impact and to help decision making in electricity sector. In this study, efforts are made to estimate electricity power generation cost of major power options by incorporating additional cost to reduce environmental impact and to suggest an optimal plant mix in this case. (Author)

  3. Nuclear energy in medium and long term energy generation of Turkey

    International Nuclear Information System (INIS)

    Sarici, L. E.; Yilmaz, S.; Guray, B. S.

    2001-01-01

    In this study; objectives and activities of Nuclear Power Plants Department and Turkish Electricity Generation and Transmission Corporation is briefly mentioned. A brief history of electricity generation, development of Turkish electrical energy sector and development of the installed capacity of country is presented. The history and future perspectives of AKZuyu Nuclear Power Plant Project is sharply outlined. In the light of the current situation in electricity generation and demand projections, importance of nuclear power among the other future electricity generation alternatives of Turkey is underlined

  4. Hardware-in-the-loop (HIL) nuclear power plant training simulation platform design and validation

    Energy Technology Data Exchange (ETDEWEB)

    Rankin, D.J. [Univ. of Western Ontario, Control and Instrumentation (CIES) Research Group, Dept. of Electrical and Computer Engineering, London, Ontario (Canada)

    2008-07-01

    The design, development and validation of a hardware-in- the-loop (HIL) simulation platform are presented. An Invensys Triconex Tricon v9 safety PLC is interfaced to a nuclear power plant (NPP) simulation suite, replicating the operation of Darlington NPP. Communication between the simulator and external hardware is supported by a National Instruments (NI) data acquisition system (DAQ) and a customized virtual instrument (VI). Event timings within the control loop are thoroughly investigated and an acceptable method for HIL platform communication is developed. A sample application (primary shutdown system (SDS1)) is implemented and evaluated. SDS1 evaluation is performed with focus on steam generator (SG) level low trip scenarios. For this purpose, a design basis accident (DBA) associated with SDS1 regulatory standards is applied to the HIL simulation environment and compared with simulated expected plant operation. Further, the role of the Tricon v9 system within the HIL loop is investigated to establish a basis for the future integration of the entire SDS1 control logic. (author)

  5. Steam generators for nuclear power plants

    International Nuclear Information System (INIS)

    Tillequin, Jean

    1975-01-01

    The role and the general characteristics of steam generators in nuclear power plants are indicated, and particular types are described according to the coolant nature (carbon dioxide, helium, light water, heavy water, sodium) [fr

  6. Young Generation in Nuclear Initiative to Promote Nuclear Science and Technology

    International Nuclear Information System (INIS)

    Kilavi Ndege, P.K.

    2015-01-01

    The Kenyan Young Generation in Nuclear (KYGN) is a recently founded not to profit organization. Its mandate is to educate, inform, promote and transfer knowledge on the peaceful, safe and secure users of nuclear science and technology in Kenya. It brings on board all scientist and students with special interest in nuclear science and related fields. KYGN is an affiliate of International Youth Nuclear Congress (YNC) whose membership with IYNC whose membership is drawn from member state of United Nations. Through our membership with IYNC, KYGN members have been able to participate in different forums. In this paper, we discuss KYGN’s prime roles opportunities as well as the challenges of the organization

  7. Radioactive Waste Generation in Pyro-SFR Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Gao, Fanxing; Park, Byung Heung; Ko, Won Il

    2011-01-01

    Which nuclear fuel cycle option to deploy is of great importance in the sustainability of nuclear power. SFR fuel cycle employing pyroprocessing (named as Pyro- SFR Cycle) is one promising fuel cycle option in the near future. Radioactive waste generation is a key criterion in nuclear fuel cycle system analysis, which considerably affects the future development of nuclear power. High population with small territory is one special characteristic of ROK, which makes the waste management pretty important. In this study, particularly the amount of waste generation with regard to the promising advanced fuel cycle option was evaluated, because the difficulty of deploying an underground repository for HLW disposal requires a longer time especially in ROK

  8. Nordic Nuclear Materials Forum for Generation IV Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Anghel, C. (Studsvik Nuclear AB, Nykoeping (Sweden)); Penttilae, S. (Technical Research Centre of Finland, VTT (Finland))

    2010-03-15

    A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the 'European Energy Research Alliance, EERA, workshop for nuclear structural materials' http://www.eera-set.eu/index.php?index=41 as external observers. Future plans include a new Nordic application for continuation of NOMAGE4 network. (author)

  9. Nordic Nuclear Materials Forum for Generation IV Reactors

    International Nuclear Information System (INIS)

    Anghel, C.; Penttilae, S.

    2010-03-01

    A network for material issues for Generation IV nuclear power has been initiated within the Nordic countries. The objectives of the Generation IV Nordic Nuclear Materials Forum (NOMAGE4) are to put the basis of a sustainable forum for Gen IV issues, especially focussing on fuels, cladding, structural materials and coolant interaction. Other issues include reactor physics, dynamics and diagnostics, core and fuel design. The present report summarizes the work performed during the year 2009. The efforts made include identification of organisations involved in Gen IV issues in the Nordic countries, update of the forum website, http://www.studsvik.se/GenerationIV, and investigation of capabilities for research within the area of Gen IV. Within the NOMAGE4 project a seminar on Generation IV Nuclear Energy Systems has been organized during 15-16th of October 2009. The aim of the seminar was to provide a forum for exchange of information, discussion on future research needs and networking of experts on Generation IV reactor concepts. As an outcome of the NOMAGE4, a few collaboration project proposals have been prepared/planned in 2009. The network was welcomed by the European Commission and was mentioned as an exemplary network with representatives from industries, universities, power companies and research institutes. NOMAGE4 has been invited to participate to the 'European Energy Research Alliance, EERA, workshop for nuclear structural materials' http://www.eera-set.eu/index.php?index=41 as external observers. Future plans include a new Nordic application for continuation of NOMAGE4 network. (author)

  10. Economics issues - nuclear power generation in North America

    International Nuclear Information System (INIS)

    Jones, R.; Taylor, J.; Santucci, J.

    1996-01-01

    The structure of the US utility industry is in transition. Political, social, and economic factors are contributing to a rapid shift from a monopoly structure (captive markets, cost-plus prices, negotiated rate of return on capital) to a highly competitive one (choices for customers, prices determined by the market place, earnings based on market price less cost). The rate of change has been accelerating. For example, what just two years ago would have been thought of as highly unlikely -- competition for the individual electric customer -- is now part of the plan in California and other states. In our view, technology is at the root of many of these structural changes with more to come. Yet another round of technological change is afoot, involving even more efficient gas turbines, new methods of utilizing transmission lines, distributed generation, and new opportunities for electricity use and service. It can be argued that the restructuring of the marketplace reflects, in some measure, anticipation for these advances. For the foreseeable future, nuclear energy will continue to play a significant role in the generating grid of North America. However, new nuclear generation will be held to standards of competition that are dictated by market forces, and by advances in competing technologies for base load generation. It is important to understand these forces, and devise a response which ensures that nuclear energy will continue to provide a viable, competitive, and environmentally superior option for generating electricity in the 21st century. The EPRI Nuclear Power program is focused on achieving these goals. (author)

  11. Advanced Ceramic Materials For Next-Generation Nuclear Applications

    International Nuclear Information System (INIS)

    Marra, J.

    2010-01-01

    Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and

  12. Major issues associated with nuclear power generation cost and their evaluation

    International Nuclear Information System (INIS)

    Matsuo, Yuji; Shimogori, Kei; Suzuki, Atsuhiko

    2015-01-01

    This paper discusses the evaluation of power generation cost that is an important item for energy policy planning. Especially with a focus on nuclear power generation cost, it reviews what will become a focal point on evaluating power generation cost at the present point after the estimates of the 'Investigation Committee on Costs' that was organized by the government have been issued, and what will be a major factor affecting future changes in costs. This paper firstly compared several estimation results on nuclear power generation cost, and extracted/arranged controversial points and unsolved points for discussing nuclear power generation cost. In evaluating nuclear power generation cost, the comparison of capital cost and other costs can give the understanding of what can be important issues. Then, as the main issues, this paper evaluated/discussed the construction cost, operation/maintenance cost, external cost, issue of discount rate, as well as power generation costs in foreign countries and the impact of fossil fuel prices. As other issues related to power generation cost evaluation, it took up expenses for decommissioning, disposal of high-level radioactive waste, and re-processing, outlined the evaluation results by the 'Investigation Committee on Costs,' and compared them with the evaluation examples in foreign countries. These costs do not account for a large share of the entire nuclear power generation costs. The most important point for considering future energy policy is the issue of discount rate, that is, the issue of fund-raising environment for entrepreneurs. This is the factor to greatly affect the economy of future nuclear power generation. (A.O.)

  13. Nuclear generation cost management and economic benefits

    International Nuclear Information System (INIS)

    Horton, E.P.; Sepa, T.R.

    1989-01-01

    The CANDU-Pressurized Heavy Water (CANDU-PHW) type of nuclear generating station has been developed jointly by Atomic Energy of Canada Limited and Ontario Hydro. This report discusses the cost management principles used for Ontario Hydro's CANDU-PHW program, current cost management initiatives, and the economic benefits of nuclear power to the provinces of Ontario and New Brunswick, in Canada

  14. Generating highly polarized nuclear spins in solution using dynamic nuclear polarization

    DEFF Research Database (Denmark)

    Wolber, J.; Ellner, F.; Fridlund, B.

    2004-01-01

    A method to generate strongly polarized nuclear spins in solution has been developed, using Dynamic Nuclear Polarization (DNP) at a temperature of 1.2K, and at a field of 3.354T, corresponding to an electron spin resonance frequency of 94GHz. Trityl radicals are used to directly polarize 13C...... and other low-γ nuclei. Subsequent to the DNP process, the solid sample is dissolved rapidly with a warm solvent to create a solution of molecules with highly polarized nuclear spins. Two main applications are proposed: high-resolution liquid state NMR with enhanced sensitivity, and the use...

  15. The trend of the public opinion upon nuclear power generation in internet blog

    International Nuclear Information System (INIS)

    Maruta, Katsuhiko; Ueda, Yoshitaka

    2011-01-01

    The authors pay attention to and survey internet information which is called 'blog' to grasp how nuclear power generation information is treated in internet and forms public opinion. Examples of the outcomes are as follows. 1) Numbers of blog reference will change by public opinion upon nuclear power generation. A lot of blog references about nuclear power plants are conducted when a big earthquake occurred. 2) As a feature of the report, numbers of the references against nuclear power generation exceed those which are positive for nuclear power. There are a lot of blog reports which are against nuclear power generation and easy to make readers believe that they are true even if they are based on misunderstanding. It is worried that such reports give people too much negative influence for the public opinion upon nuclear power generation. The authors survey short term trend of the internet public opinion after TEPCO's Fukushima Daiichi Power Plants Accident too. As a result, it is made clear that people's concern upon nuclear power became very high and the ratio of the supporters of nuclear power generation changed after the accident. (author)

  16. Commercial grade item (CGI) dedication of generators for nuclear safety related applications

    International Nuclear Information System (INIS)

    Das, R.K.; Hajos, L.G.

    1993-01-01

    The number of nuclear safety related equipment suppliers and the availability of spare and replacement parts designed specifically for nuclear safety related application are shrinking rapidly. These have made it necessary for utilities to apply commercial grade spare and replacement parts in nuclear safety related applications after implementing proper acceptance and dedication process to verify that such items conform with the requirements of their use in nuclear safety related application. The general guidelines for the commercial grade item (CGI) acceptance and dedication are provided in US Nuclear Regulatory Commission (NRC) Generic Letters and Electric Power Research Institute (EPRI) Report NP-5652, Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications. This paper presents an application of these generic guidelines for procurement, acceptance, and dedication of a commercial grade generator for use as a standby generator at Salem Generating Station Units 1 and 2. The paper identifies the critical characteristics of the generator which once verified, will provide reasonable assurance that the generator will perform its intended safety function. The paper also delineates the method of verification of the critical characteristics through tests and provide acceptance criteria for the test results. The methodology presented in this paper may be used as specific guidelines for reliable and cost effective procurement and dedication of commercial grade generators for use as standby generators at nuclear power plants

  17. Generation of nuclear data banks through interpolation

    International Nuclear Information System (INIS)

    Castillo M, J.A.

    1999-01-01

    Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesser resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, used to generate Nuclear Data Banks employing bi cubic polynomial interpolation, taking as independent variables the uranium and gadolinium percents. Two proposals were worked, applying in both cases the finite element method, using one element with 16 nodes to carry out the interpolation. In the first proposals the canonic base was employed to obtain the interpolating polynomial and later, the corresponding linear equations system. In the solution of this system the Gaussian elimination method with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validations test, a comparison was made between the values obtained with INTPOLBI and INTERTEG (created at the Instituto de Investigaciones Electricas with the same purpose) codes, and Data Banks created through the conventional process, that is, with nuclear codes normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks. (Author)

  18. Human factors engineering in the design of colour-graphic displays

    International Nuclear Information System (INIS)

    Fenton, E.F.

    1985-01-01

    The operator interface for Ontario Hydro's Darlington Nuclear Generating Station will rely extensively on the use of coloured graphic display formats. These are used for the presentation of both control and monitoring information. The displays are organized in a hierarchical relationship and a simple interactive selection method using light pens has been implemented. The application of human factors engineering principles has been a major factor in all aspects of the design. This paper describes the system and the human factors engineering function

  19. Aiming at the rebirth of the nuclear generation

    International Nuclear Information System (INIS)

    Uematsu, M.M.

    2000-01-01

    A half century has passed since Japan began an industrialization of nuclear energy. The nuclear industries of today have a variety of branches and each industry functions independently. Young professionals need opportunities for communications among industries, utilities and institutes, and also nuclear experts. We, young professionals, are in the motion of organizing the 'Young Generation Network (YGN) of Japan,' and also foresee to organize 'YGN in Asia' in the future

  20. New generation nuclear power units of PWR type integral reactors

    International Nuclear Information System (INIS)

    Mitenkov, F.M.; Kurachen Kov, A.V.; Malamud, V.A.; Panov, Yu.K.; Runov, B.I.; Flerov, L.N.

    1997-01-01

    Design bases of new generation nuclear power units (nuclear power plants - NPP, nuclear co-generation plants - NCP, nuclear distract heating plants - NDHP), using integral type PWPS, developed in OKBM, Nizhny Novgorod and trends of design decisions optimization are considered in this report. The problems of diagnostics, servicing and repair of the integral reactor components in course of operation are discussed. The results of safety analysis, including the problems of several accident localization with postulated core melting and keeping corium in the reactor vessel and guard vessel are presented. Information on experimental substantiation of the suggested plant design decisions is presented. (author)

  1. New reactor concepts for new generation of nuclear power plants: an overview, invited paper

    International Nuclear Information System (INIS)

    Vujic, J.; Greenspan, E.; Milosevic, M.

    2006-01-01

    The outlook for energy demand underscores the need to increase the share of nuclear energy production. Achieving the vision of sustainable growth of nuclear energy will require development of both advanced nuclear fuel cycles and next generation reactor technologies and advanced reprocessing and fuel treatment technologies. To achieve this vision, the US department of energy (DOE) has adopted new strategy, the Global Nuclear Energy Partnership (GNEP), which integrates earlier programs: the Generation IV Nuclear Energy Systems Initiative (Generation IV), Nuclear Hydrogen Initiative (NHI), and the Advanced Fuel Cycle Initiative (AFCI) with proliferation-resistant spent fuel reprocessing to minimize nuclear waste. Generation IV furthers this vision beyond previous energy systems, such as Generation III+, through incremental improvements in economic competitiveness, sustainability, development of passively safe systems, and breakthrough methods to reduce the routes of nuclear proliferation. This paper summarizes the main characteristics of the six most promising nuclear energy systems identified by the Generation IV Roadmap and reviews some Generation IV system designs for small-side proliferation resistant reactors being developed by University of California at Berkeley. (author)

  2. Total generating costs: coal and nuclear plants

    International Nuclear Information System (INIS)

    1979-02-01

    The study was confined to single and multi-unit coal- and nuclear-fueled electric-generating stations. The stations are composed of 1200-MWe PWRs; 1200-MWe BWRs; 800-and 1200-MWe High-Sulfur Coal units, and 800- and 1200-MWe Low-Sulfur Coal units. The total generating cost estimates were developed for commercial operation dates of 1985 and 1990; for 5 and 8% escalation rates, for 10 and 12% discount rates; and, for capacity factors of 50, 60, 70, and 80%. The report describes the methodology for obtaining annualized capital costs, levelized coal and nuclear fuel costs, levelized operation and maintenance costs, and the resulting total generating costs for each type of station. The costs are applicable to a hypothetical Middletwon site in the Northeastern United States. Plant descriptions with general design parameters are included. The report also reprints for convenience, summaries of capital cost by account type developed in the previous commercial electric-power cost studies. Appropriate references are given for additional detailed information. Sufficient detail is given to allow the reader to develop total generating costs for other cases or conditions

  3. Nuclear power generation in Chile, possibility or utopia

    International Nuclear Information System (INIS)

    Vergara Aimone, Julio

    2000-01-01

    Regardless the pressure of several groups, nuclear power stands for one sixth of worldwide electricity supply, produced from a resource that well managed could be available for centuries beyond the exhaustion of oil and natural gas. Such power option could support a macro power system with low environmental impact. The Chilean power demand is growing at a high rate. Without fossil supplies, our potential hydraulic capacity would become exhausted at an early date and our country would face a severe energy dependence, without control of generation costs and with increased atmospheric emissions, some of which would be responsible for global environmental effects. Nuclear power would stabilize generation costs in the near and mid terms and would also arrest gaseous emissions. This paper discusses the current status of the nuclear industry and those pending issues, compared to other power options. It also discusses the estimated year for the operation the of first nuclear power plant. Although nuclear power technology seems to be in a mature stage, it is suggested that the aggressive use of advanced and moreover innovative reactor designs would result in a greater nuclear technology penetration. Several of such designs or concepts await commercial demonstration within the decade. Those would also extend the benefits of nuclear power to countries with reduced or moderate power grids, as is our case. (author)

  4. The young generation - guarantors for the future of the nuclear industry

    International Nuclear Information System (INIS)

    Broy, Y.

    2000-01-01

    The concept of the 'Young Generation' has been meeting with considerable interest in many European countries for a number of years already. On the basis of the Young Generation Network initiated by Jan Runermark, Sweden, Young Generation networks have been created in a number of European countries, including Germany. Since October 1998, Germany's Young Generation has worked in a changed political environment: As a result of the outcome of the elections to the federal parliament in 1998 and the establishment of a federal government by SPD (the Social Democratic Party) and Alliance 90/The Greens, opting out of the peaceful uses of nuclear power has become one of the guiding principles and goals. Hence, the qualified and highly motivated young employees of nuclear companies are bound to ask themselves whether there is any future for them in nuclear engineering. The Young Generation will work for the future of nuclear technology by embarking on a series of activities. Discussions with the public, transfer of know-how, and also an intensification of contacts among all companies active in the nuclear field are only some of the items of their agenda. The purpose of the activities, and the principle, of the Young Generation is this: The Young Generation is aware of its responsibility for the future, and is ready to meet the challenges. (orig.) [de

  5. The young generation - guarantors for the future of the nuclear industry

    International Nuclear Information System (INIS)

    Broy, Y.

    2001-01-01

    For several years the 'YOUNG GENERATION' has been attracting great interest all over Europe. Based on the Young Generation Network of the European Nuclear Society (ENS) founded by Jan Runermark, in a lot of European countries a national Young Generation Network has been established, as well in Germany. Since October 1998 the Young Generation in Germany has been working in the frame of a difficult political situation after the decision was made about the phasing out of nuclear energy in Germany. Nowadays, our highly qualified and motivated young people who have been working for a couple of years in the nuclear field and already took over a lot of knowledge and experiences, have to decide: Is there a future for us in the nuclear industry? The paper will briefly summarise the wide range of activities of the German Young Generation. A selection of them will be chosen to highlight our fight for the future of nuclear energy in Germany, e.g. communication with the public, know-how-transfer, improvement of links between the fuel vendor and their customers. The main purpose is to point out: There is a young generation who is ready to take over the knowledge and the responsibility for the future. (author)

  6. Facts against nuclear electricity generation. 2. enlarged ed.

    International Nuclear Information System (INIS)

    Buechele, C.

    1986-01-01

    The book destroys a legend. The nuclear cartel still goes on telling the tale of safety, environmental compatibility and economic efficiency of nuclear electricity generation. But nothing in this story stands the test: Bare facts destroy the legend. Up to now, only insiders have been able to state counterarguments. The book in hand now presents in a nutshell all results and experience and facts to be brought forward against nuclear electricity generation. The material is presented in a problem-oriented, reliable and comprehensible manner. Anyone who long since suspected lies and malinformation of the public will step by step find the arguments justifying his suspicion. In an annex, Harald Gaber explains the Chernobyl disaster and its consequences. A literature index with comments is a helpful guide for further reading. (orig.) [de

  7. Thermal and nuclear power generation cost estimates using corporate financial statements

    International Nuclear Information System (INIS)

    Matsuo, Yuhji; Nagatomi, Yu; Murakami, Tomoko

    2012-01-01

    There are two generally accepted methods for estimating power generation costs: so-called 'model plant' method and the method using corporate financial statements. The method using corporate financial statements, though under some constraints, can provide useful information for comparing thermal and nuclear power generation costs. This study used this method for estimating thermal and nuclear power generation costs in Japan for the past five years, finding that the nuclear power generation cost remained stable at around 7 yen per kilowatt-hour (kWh) while the thermal power generation cost moved within a wide range of 9 to 12 yen/kWh in line with wild fluctuations in primary energy prices. The cost of nuclear power generation is expected to increase due to the enhancement of safety measures and accident damage compensation in the future, while there are reactor decommissioning, backend and many other costs that the financial statement-using approach cannot accurately estimate. In the future, efforts should be continued to comprehensively and accurately estimate total costs. (author)

  8. Hardening techniques for nuclear generated EMPs: Pt. 1

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    This article is intended as an introduction to the protection of electronic equipment against the effects of the electromagnetic pulse (EMP) generated by a nuclear explosion. For explosions at heights above 100 km the energy in the pulse is considerable over areas of many thousands of square metres. This constitutes a major threat to electronic equipments which have not been exposed to the consequences of closer nuclear explosions (namely blast, thermal and nuclear radiation)

  9. EARTHQUAKE RESEARCH PROBLEMS OF NUCLEAR POWER GENERATORS

    Energy Technology Data Exchange (ETDEWEB)

    Housner, G. W.; Hudson, D. E.

    1963-10-15

    Earthquake problems associated with the construction of nuclear power generators require a more extensive and a more precise knowledge of earthquake characteristics and the dynamic behavior of structures than was considered necessary for ordinary buildings. Economic considerations indicate the desirability of additional research on the problems of earthquakes and nuclear reactors. The nature of these earthquake-resistant design problems is discussed and programs of research are recommended. (auth)

  10. Efforts onto electricity and instrumentation technology for nuclear power generation

    International Nuclear Information System (INIS)

    Hayakawa, Toshifumi

    2000-01-01

    Nuclear power generation shares more than 1/3 of all amounts of in-land generation at present, as a supplying source of stable electric energy after 2000 either. As a recent example of efforts onto electricity and instrumentation technology for nuclear power generation, there are, on instrumentation control system a new central control board aiming at reduction of operator's load, protection of human error, and upgrading of system reliability and economics by applying high level micro-processor applied technique and high speed data transfer technique to central monitoring operation and plant control protection, on a field of reactor instrumentation a new digital control rod position indicator improved of conventional system on a base of operation experience and recent technology, on a field of radiation instrumentation a new radiation instrumentation system accumulating actual results in a wide application field on a concept of application to nuclear power plant by adopting in-situ separation processing system using local network technique, and on a field of operation maintenance and management a conservation management system for nuclear generation plant intending of further effectiveness of operation maintenance management of power plant by applying of operation experience and recent data processing and communication technology. And, in the large electric apparatus, there are some generators carried out production and verification of a model one with actual size in lengthwise dimension, to correspond to future large capacity nuclear power plant. By this verification, it was proved that even large capacity generator of 1800 MVA class could be manufactured. (G.K.)

  11. Potential growth of nuclear and coal electricity generation in the US

    International Nuclear Information System (INIS)

    Bloomster, C.H.; Merrill, E.T.

    1989-08-01

    Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity over the next fifty years. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will require solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear, the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. This report assesses the impacts associated with a range of projected growth rates in electricity demand over the next 50 years. The resource requirements and waste generation resulting from pursuing the coal and nuclear fuel options to meet the projected growth rates are estimated. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Improvements in technology and waste management practices must be pursued to mitigate environmental and safety concerns about electricity generation from both options. 34 refs., 18 figs., 14 tabs

  12. Simulation on effect of stopping nuclear power generation

    International Nuclear Information System (INIS)

    Yajima, Masayuki; Kumakura, Osamu; Sakurai, Norihisa; Nagata, Yutaka; Hattori, Tsuneaki

    1990-01-01

    The effects that the stopping of nuclear power generation exerts on the price of primary energy such as petroleum, LNG and coal and the trend of Japanese energy and economy are analyzed by using the medium term economy forecasting system. In the simulation, the case of stopping nuclear power generation in seven countries of OECD is supposed, and as for the process of stopping, two cases of immediate stopping and stopping by gradual reduction are set up. The models used for the simulation are the world energy model, the competition among energies model and the multiple category model. By the decrease of nuclear power generation, thermal power generation increases, and the demand of fossil fuel increases. As the result, the price of fossil fuel rises (the world energy model), and the price of fossil fuel imported to Japan rises. Also the quantity of fossil fuel import to Japan increase. These price rise and quantity increase exert deflation effect to Japanese economy (the multiple category model). The price rise of fossil fuel affects the competition among energies in Japan through the relative change of secondary energy price (the competition among energies model). The impact to the world and to Japan is discussed. (K.I.)

  13. Digital simulation for nuclear once-through steam generators

    International Nuclear Information System (INIS)

    Chen, A.T.

    1976-01-01

    Mathematical models for calculating the dynamic response of the Oconee type once through steam generator (OTSG) and the integral economizer once through steam generator (IEOTSG) was developed and presented in this dissertation. Linear and nonlinear models of both steam generator types were formulated using the state variable, lumped parameter approach. Transient and frequency responses of system parameters were calculated for various perturbations from both the primary coolant side and the secondary side. Transients of key parameters, including primary outlet temperature, superheated steam outlet temperature, boiling length/subcooled length and steam pressure, were generated, compared and discussed for both steam generator types. Frequency responses of delta P/sub s//deltaT/sub pin/ of the linear OTSG model were validated by using the dynamic testing results obtained at the Oconee I nuclear power station. A sensitivity analysis in both the time and the frequency domains was performed. It was concluded that the mathematical and computer models developed in this dissertation for both the OTSG and the IEOTSG are suitable for overall plant performance evaluation and steam generator related component/system design analysis for nuclear plants using either type of steam generator

  14. KOREAN STUDENTS' BEHAVIORAL CHANGE TOWARD NUCLEAR POWER GENERATION THROUGH EDUCATION

    Directory of Open Access Journals (Sweden)

    EUN OK HAN

    2014-10-01

    Full Text Available As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017, safety (p<0.000, information acquisition (p<0.000, and subjective knowledge (p<0.000, objective knowledge (p<0.000, attitude (p<0.000, and behavior (p<0.000 were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

  15. Nuclear steam generator tubesheet shield

    International Nuclear Information System (INIS)

    Nickerson, J.H.D.; Ruhe, A.

    1982-01-01

    The invention involves improvements to a nuclear steam generator of the type in which a plurality of U-shaped tubes are connected at opposite ends to a tubesheet and extend between inlet and outlet chambers, with the steam generator including an integral preheater zone adjacent to the downflow legs of the U-shaped tubes. The improvement is a thermal shield disposed adjacent to an upper face of the tubesheet within the preheater zone, the shield including ductile cladding material applied directly to the upper face of the tubesheet, with the downflow legs of the U-shaped tubes extending through the cladding into the tubesheet

  16. Nuclear heat generating plants - technical concepts and market potentials. Chapter 8

    International Nuclear Information System (INIS)

    Thoene, E.

    1988-01-01

    To determine the advantages and disadvantages of different heat generating systems, a comparison is made between nuclear heat generating plants and competing heat generating systems. Nuclear heat generating plant concepts in practice have to compete with a wide range of existing and new fossil heat generating technologies of the most different capacities, ranging from combined heat and power generation to individual heating in one-family houses. Heat generation costs are calculated by means of a dynamic annuity method from an economic point of view. The development of real prices of fossil energy sources is based on two scenarios characterized as follows: scenario I - insignificant price increase by the year 2000, then stagnant; scenario II - moderate price increase by the year 2010, then stagnant. As a result of that systems comparison it can be stated that the considered nuclear heat generating plants may be an interesting competitive heat generation option, provided the assumptions on which the study is based can be implemented. This applies especially to investment costs. At the same time those plants contribute to a diversification of energy source options on the heat market. Their use leads to a reduction of fossil fuel imports, increasing at the same time short- and long-term supply guarantees. If nuclear heat generating plants substitute fossil heat generating plants, or render the construction of new ones superfluous, they contribute to avoiding chemical air pollutants. (orig./UA) [de

  17. The nuclear electricity generating industry in England and Wales post-privatisation

    International Nuclear Information System (INIS)

    Johnson, C.B.

    1992-01-01

    This paper presents an overview of the new legal framework within which the nuclear generating industry has operated in England and Wales since 31 March 1990. It describes the formation of Nuclear Electric plc and the licensing arrangements, including the various obligations which have been placed upon Nuclear Electric by virtue of its Generation Licence. The impact of competition law is outlined, together with the commercial arrangements including electricity pooling and some of the other more important agreements which Nuclear Electric has entered into. Finally, the Paper discusses some of the constraints under which Nuclear Electric operates, and summarises Government policy towards nuclear power and its future prospects in the United Kingdom. (author)

  18. Developing the next generation of nuclear workers at OPG

    International Nuclear Information System (INIS)

    Spekkens, P.

    2007-01-01

    This presentation is about developing the next generation of nuclear workers at Ontario Power Generation (OPG). Industry developments are creating urgent need to hire, train and retain new staff. OPG has an aggressive hiring campaign. Training organization is challenged to accommodate influx of new staff. Collaborating with colleges and universities is increasing the supply of qualified recruits with an interest in nuclear. Program for functional and leadership training have been developed. Knowledge retention is urgently required

  19. Nuclear Power as a Basis for Future Electricity Generation

    Science.gov (United States)

    Pioro, Igor; Buruchenko, Sergey

    2017-12-01

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

  20. A New Approach for Nuclear Data Covariance and Sensitivity Generation

    International Nuclear Information System (INIS)

    Leal, L.C.; Larson, N.M.; Derrien, H.; Kawano, T.; Chadwick, M.B.

    2005-01-01

    Covariance data are required to correctly assess uncertainties in design parameters in nuclear applications. The error estimation of calculated quantities relies on the nuclear data uncertainty information available in the basic nuclear data libraries, such as the U.S. Evaluated Nuclear Data File, ENDF/B. The uncertainty files in the ENDF/B library are obtained from the analysis of experimental data and are stored as variance and covariance data. The computer code SAMMY is used in the analysis of the experimental data in the resolved and unresolved resonance energy regions. The data fitting of cross sections is based on generalized least-squares formalism (Bayes' theory) together with the resonance formalism described by R-matrix theory. Two approaches are used in SAMMY for the generation of resonance-parameter covariance data. In the evaluation process SAMMY generates a set of resonance parameters that fit the data, and, in addition, it also provides the resonance-parameter covariances. For existing resonance-parameter evaluations where no resonance-parameter covariance data are available, the alternative is to use an approach called the 'retroactive' resonance-parameter covariance generation. In the high-energy region the methodology for generating covariance data consists of least-squares fitting and model parameter adjustment. The least-squares fitting method calculates covariances directly from experimental data. The parameter adjustment method employs a nuclear model calculation such as the optical model and the Hauser-Feshbach model, and estimates a covariance for the nuclear model parameters. In this paper we describe the application of the retroactive method and the parameter adjustment method to generate covariance data for the gadolinium isotopes

  1. Susceptibility of CANDU steam generator preheater to cavitation erosion

    International Nuclear Information System (INIS)

    Laroche, S.L.; Sun, L.; Pietralik, J.M.

    2012-01-01

    In 2009, Darlington Steam Generator (SG) tube inspections revealed some tubes had degraded in the preheater. The tube degradation occurred at the clearance gap between the tube and the preheater baffle and reached up to 50% through-wall depth at the baffles in the middle portion of the preheater. The general pattern of the damage and the elemental composition analysis suggested that the degradation was the result of a hydrodynamic process, such as cavitation erosion. Cavitation erosion occurs when vapour bubbles exist or form in the flowing liquid and then these bubbles collapse violently in the vicinity of the wall. These bubbles collapse when steam bubbles contact water that is sufficiently subcooled, below the saturation temperature. In the gap between the tube and the preheater baffle, low flow will exist due to the pressure difference across the baffle plate. In addition, heat transfer occurs from the primary-side fluid to the secondary-side fluid within this clearance gap that is driven by the primary-to-secondary temperature difference. Factors, such as the tube position in the baffle hole and fouling, influence the local conditions and can cause subcooled boiling that result in cavitation. This paper presents a study of flow and heat transfer phenomena to determine the factors contributing to cavitation erosion in SG preheaters. The analysis used the THIRST1 code for a 3-dimensional thermalhydraulic simulation of the steam generators and the ANSYS FLUENT®2 code for detailed calculations of flow and heat transfer in the clearance gaps. This study identifies that tubes in the preheater region are susceptible to cavitation erosion and indicates that this area should be part of the station inspection program because, regardless of preheater design, some tubes may experience the thermalhydraulic conditions and undergo degradations similar to those observed for the tubes in Darlington SGs. (author)

  2. Generation IV nuclear energy systems: road map and concepts. 2. Generation II Measurement Systems for Generation IV Nuclear Power Plants

    International Nuclear Information System (INIS)

    Miller, Don W.

    2001-01-01

    Instrumentation and Control (I and C) systems in current operating plants have not changed appreciably since their original design in the 1950's. These systems depend on a variety of traditional process and radiation sensors for the measurement of safety and control variables such as temperature, pressure, and neutron flux. To improve their performance and to make them more robust, many plant control systems have been upgraded from analog to digital; most of them continue to utilize traditional single-input single-output architecture. Transmission of data, for the most part, continues to employ large coaxial cables. These cables are not the small cables used in a laboratory (i.e., RG-58 or RG-59). Because of concern about electromagnetic and radio frequency interference and other environmental effects, bulky triax cables, which are cables with two outer shields separated by an insulator, are used. In a nuclear plant there are literally miles of cables and hundreds of specialized penetrations for cables going through containment or pressure vessel walls. The I and C systems in the advanced light water reactor (ALWR) designs, i.e., Generation III reactors, do employ more advanced technology than current plants; however, they do not incorporate new technology on a broad scale. This in part is a consequence of the ALWR design philosophy that discouraged use of advanced technology if current technology was adequate. As a consequence, the I and C systems in the ALWRs continue to make use of current technology. There are two exceptions, however, which include the broad use of software-based digital systems and fiber optics for signal isolation and data transmission in nonradioactive areas. The ALWR design philosophy was a justifiably low-risk approach when considering the overall objective of 'capturing' lessons learned from current operating plants to design a plant that would exhibit performance superior to current plants and would be relatively easy to license without

  3. Electricity Generation Through the Koeberg Nuclear Power Station of Eskom in South Africa

    International Nuclear Information System (INIS)

    Dladla, G.; Joubert, J.

    2015-01-01

    The poster provides information on the process of nuclear energy generation in a nuclear power plant in order to produce electricity. Nuclear energy currently provides approximately 11% of the world’s electricity needs, with Koeberg Nuclear Power Station situated in the Western Cape providing 4.4% of South Africa’s electricity needs. As Africa’s first nuclear power station, Koeberg has an installed capacity of 1910 MW of power. Koeberg’ s total net output is 1860 MW. While there are significant differences, there are many similarities between nuclear power plants and other electrical generating facilities. Uranium is used for fuel in nuclear power plants to make electricity. With the exception of solar, wind, and hydroelectric plants, all others including nuclear plants convert water to steam that spins the propeller-like blades of a turbine that spins the shaft of a generator. Inside the generator coils of wire and magnetic fields interact to create electricity. The energy needed to boil water into steam is produced in one of two ways: by burning coal, oil, or gas (fossil fuels) in a furnace or by splitting certain atoms of uranium in a nuclear energy plant. The uranium fuel generates heat through a controlled fission process fission, which is described in this poster presentation. The Koeberg Nuclear Power Station is a Pressurised water reactor (PWR). The operating method and the components of the Koeberg Power Station are also described. The nuclear waste generated at a nuclear power station is described under three headings— low-level waste, intermediate-level waste and used or spent fuel, which can be solid, liquid or gaseous. (author)

  4. Waste generation comparison: Coal-fired versus nuclear power plants

    International Nuclear Information System (INIS)

    LaGuardia, T.S.

    1998-01-01

    Low-level radioactive waste generation and disposal attract a great deal of attention whenever the nuclear industry is scrutinized by concerned parties, be it the media, the public, or political interests. It is therefore important to the nuclear industry that this issue be put into perspective relative to other current forms of energy production. Most of the country's fossil-fueled power comes from coal-fired plants, with oil and gas as other fuel sources. Most of the generated waste also comes from coal plants. This paper, therefore, compares waste quantities generated by a typical (1150-MW(electric)) pressurized water reactor (PWR) to that of a comparably sized coal-fired power plant

  5. Reflexions on the expansion of nuclear generation in Brazil

    International Nuclear Information System (INIS)

    Freitas, Juliana de Moraes Marreco de

    2006-01-01

    This article analyses the pros and cons of the nuclear generation in Brazil, involving in a large discussion the technological perspectives both economic, social and environmental. The objective is to rise the main questions about the polemical nuclear expansion in Brazil

  6. Nuclear power generation costs in the United States of America

    International Nuclear Information System (INIS)

    Willis, W.F.

    1983-01-01

    Increasing world energy prices and shortages of fuel resources make the utilization of nuclear power extremely important. The United States nuclear power industry represents the largest body of nuclear power experience in the world. Analysis of the recent United States experience of substantial increases in the cost of nuclear power generation provides good insight into the interdependence of technological, financial, and institutional influences and their combined impact on the economic viability of nuclear power generation. The various factors influencing ultimate generation costs, including construction cost, fuel cost, regulatory reviews, and siting considerations are discussed, and their relative impacts are explored, including discussion of design complexity and related regulatory response. A closer look into the recent relatively high escalation of nuclear plant construction costs shows how differing economic conditions can affect the relative cost effectiveness of various methods of power generation. The vulnerability of capital-intensive, long-lead-time projects to changes in economic conditions and uncertainty in future power demands is discussed. Likewise, the pitfalls of new designs and increased sophistication are contrasted to the advantages which result from proven designs, reliable engineering, and shorter lead times. The value of reliable architect-engineers experienced in the design and construction of the plant is discussed. A discussion is presented of additional regulatory requirements stemming from public safety aspects of nuclear power. These include recognition of requirements for the very large effort for quality assurance of materials and workmanship during plant construction and operation. Likewise, a discussion is included of the demanding nature of operations, maintenance, and modification of plants during the operational phase because of the need for highly qualified operations and maintenance personnel and strict quality assurance

  7. Environmental and health effects of fossil fuel and nuclear power generation

    International Nuclear Information System (INIS)

    Naqvi, S.J.; Black, D.B.; Phillips, C.R.

    1978-03-01

    The objective of this study was to identify and assess the present and future dimensions of environmental effects and impacts of various energy generation alternatives, and to place safety and environmental risks associated with the nuclear industry in Canada in perspective with the risks from other sources. It was found that nuclear power generation involves a comparable risk to that of conventional methods of thermoelectric power generation

  8. New steam generators slated for nuclear units

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This article is a brief discussion of Duke Power's plans to replace steam generators at its McGuire and Catawba nuclear units. A letter of intent to purchase (from Babcock and Wilcox) the 12 Westinghouse steam generators has been signed, but no constructor has been selected at this time. This action is brought about by the failures of more than 3000 tubes in these units

  9. Fifteen years of radioactive waste management at Ontario Hydro

    International Nuclear Information System (INIS)

    Carter, T.J.; Rao, P.K.M.

    1985-01-01

    Ontario Hydro is a large Canadian utility producing 84% (7394 MWe) of the Nuclear Electricity generated in Canada. The low- and intermediate-level radioactive wastes generated by the Ontario Hydro program are currently being managed at the Bruce Nuclear Power Development with various volume reduction, packaging and interim storage systems. Ontario Hydro also owns and operates a radioactive waste transportation system. Studies are in progress for final disposal of these wastes in a suitable geology in Ontario. Since its inception in 1971, Ontario Hydro's radioactive waste management program has evolved into providing a full fledged radioactive waste management capability to the utility's two nuclear generation centres at Pickering and Bruce, and later in the decade, to Darlington. This paper summarizes the various developments in this program; highlights the major facilities both in-service and planned to be built; reviews the experiences gained over fifteen years of in-house waste management; and discusses the proposed reorientation towards ultimate disposal of these wastes. 2 refs., 8 figs., 1 tab

  10. Laser peening applications for next generation of nuclear power facilities

    International Nuclear Information System (INIS)

    Rankin, J.; Truong, C.; Walter, M.; Chen, H.-L.; Hackel, L.

    2008-01-01

    Generation of electricity by nuclear power can assist in achieving goals of reduced greenhouse gas emissions. Increased safety and reliability are necessary attributes of any new nuclear power plants. High pressure, hot water and radiation contribute to operating environments where Stress Corrosion Cracking (SCC) and hydrogen embrittlement can lead to potential component failures. Desire for improved steam conversion efficiency pushes the fatigue stress limits of turbine blades and other rotating equipment. For nuclear reactor facilities now being designed and built and for the next generations of designs, laser peening could be incorporated to provide significant performance life to critical subsystems and components making them less susceptible to fatigue, SCC and radiation induced embrittlement. These types of components include steam turbine blades, hubs and bearings as well as reactor components including cladding material, housings, welded assemblies, fittings, pipes, flanges, vessel penetrations, nuclear waste storage canisters. Laser peening has proven to be a commercial success in aerospace applications and has recently been put into use for gas and steam turbine generators and light water reactors. An expanded role for this technology for the broader nuclear power industry would be a beneficial extension. (author)

  11. Location condition of nuclear power generation at a viewpoint of location area

    International Nuclear Information System (INIS)

    Kawase, Kazuharu

    1999-01-01

    In the thirty years memorial meeting of the National Nuclear Power Generation located Commune Conference (NNGC) held in October, 1998, an extremely important fact was clarified, relation deeply to main aim of NNGC that permanent development was not promised at the location area even if a nuclear power plant was constructed there. Therefore, it is required that Japan government receives operation of three laws on electric source development as soon as possible, establishes a basic target on permanent area promotion in the nuclear power generation located commune, realizes some examples on development of the commune together with nuclear power generation and intends to promoted its location. (G.K.)

  12. French nuclear power plants for heat generation

    International Nuclear Information System (INIS)

    Girard, Y.

    1984-01-01

    The considerable importance that France attributes to nuclear energy is well known even though as a result of the economic crisis and the energy savings it is possible to observe a certain downward trend in the rate at which new power plants are being started up. In July 1983, a symbolic turning-point was reached - at more than 10 thousand million kW.h nuclear power accounted, for the first time, for more than 50% of the total amount of electricity generated, or approx. 80% of the total electricity output of thermal origin. On the other hand, the direct contribution - excluding the use of electricity - of nuclear energy to the heat market in France remains virtually nil. The first part of this paper discusses the prospects and realities of the application, at low and intermediate temperatures, of nuclear heat in France, while the second part describes the French nuclear projects best suited to the heat market (excluding high temperatures). (author)

  13. The Carem reactor: Bridging the gap to nuclear power generation

    International Nuclear Information System (INIS)

    Ordonez, J.P.

    1998-01-01

    An idea is presented as an alternative for the introduction of nuclear power in presently non-nuclear countries. This idea involves going through an intermediate step between the traditional research reactor and the first commercial nuclear power plant. This intermediate step would consist of a very small nuclear power plant, with the principal goal of gaining in experience in the country on all the processes involved in introducing commercial nuclear generation. (author)

  14. Recognition of people with an opinion that nuclear power generation causes global warming

    International Nuclear Information System (INIS)

    Fukue, Chiyokazu

    2004-01-01

    Almost a half of the people are thinking that nuclear power generation causes global warming. We conducted a survey in order to explore the recognition and background for the thinking of people. Consequently, the existence of the right knowledge ''nuclear power generation does not discharge carbon dioxide at the time of power generation'' influenced most the idea which nuclear power generation prevents global warming. On the other hand, the misunderstanding as ''the radioactive material produced from a nuclear power plant advances global warming'' has influenced the idea considered as a cause, and it is though that this misunderstanding depend on the negative image to nuclear power generation. Moreover, many people do not recognize the mechanism of global warming, and it is thought that they confuse global warming with the other global environment problems, such as acid rain or ozone layer destruction. Therefore, it is required to spread the knowledge that nuclear power generation does not discharge carbon dioxide, and to promote the understanding that a radioactive material is not related to global warming. Furthermore, it is required to distinguish global warming from the other global environment problems, and to explain them intelligibly. (author)

  15. Challenges of deploying nuclear energy for power generation in Malaysia

    Science.gov (United States)

    Jaafar, Mohd Zamzam; Nazaruddin, Nurul Huda; Lye, Jonathan Tan Thiam

    2017-01-01

    Under the 10th Malaysia Plan (2010-2015) and the Economic Transformation Programme (ETP), nuclear energy was identified as a potential long-term option to be explored for electricity generation in Peninsular Malaysia. The energy sector in Malaysia currently faces several concerns including depleting domestic gas supply which will affect security and reliability of supply as well as overdependance on fossil fuels - mainly gas and imported coal, and nuclear energy may offer a possible solution to these issues as well as global climate change concern. Pursuing the nuclear option, Malaysia Nuclear Power Corporation (MNPC) is undertaking a series of comprehensive studies to facilitate an informed Government decision on the matter. This paper aims to discuss the many challenges towards the peaceful use of nuclear energy for electricity generation in the context of the New Energy Policy 2010 to achieve a balanced and sustainable energy mix. This effort will continue in the 11th Malaysia Plan (2016-2020) with emphasis on implementing a comprehensive communications plan and public awareness programme for the potential use of nuclear energy in the future. In analysing the challenges for the development of nuclear energy in Malaysia, the traditional triple bottom line (TBL) framework for sustainability, encompassing economic, social and environmental objectives is utilized. An additional factor, technical, is also included in the analysis to provide a more holistic view. It is opined that the main challenges of developing nuclear energy for electricity generation in a newcomer country like Malaysia can be attributed primarily to domestic non-technical factors compared to the technical factor.

  16. Nuclear Energy In Switzerland: It's going ahead. Challenges For The Swiss Nuclear Society Young Generation Group

    International Nuclear Information System (INIS)

    Streit, Marco; Bichsel, Thomas; Fassbender, Andre; Horvath, Matthias

    2008-01-01

    Swiss energy policy is focused on generating domestic electric power without combusting fossil fuels for already four decades. Roughly 60% of the electricity is generated in hydroelectric plants, which is possible due to the country's favourable topography; the remaining 40% are produced by the country's five nuclear power plants (NPPs). As in any other country nuclear power has its enemies in Switzerland. Due to the direct democracy system in Switzerland the nuclear opposition has a lot of possibilities to disturb the energy policy. Since 1969, when the first Swiss nuclear power plant went online, four plebiscites were held on the issue of civil use of nuclear energy. Four times Swiss citizens voted in favour of further operation of the existing plants also in the latest battle for nuclear energy, which was won in 2003. In 2005 and 2006 several Swiss studies about the future energy situation, especially the electricity situation, have been published. All off them show clearly that there will be a big gab around the year 2020 when the oldest three nuclear power plants will fade out. A public debate was started, how to solve the problem. Beside others, building new nuclear power plants was mentioned and discussed rationally. In 2007 the energy police of the Swiss government changed into a more nuclear friendly position and at the end of the same year some electricity companies lunched a new build program. Hosting the International Youth Nuclear Congress 2008 (IYNC 2008) in Switzerland seems to be just the right moment for the nuclear industry in our country. The slightly changed surroundings effected the organization of Swiss Nuclear Society (SNS) and SNS Young Generation Group (SNSYG) and enlarged the fields of activities for SNSYG. Those activities mentioned in the previous chapters will be developed in the future. The discussion about new builds in Switzerland has started and because of that more nuclear activities in Switzerland will occur. And surely there will

  17. Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant

    Energy Technology Data Exchange (ETDEWEB)

    Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

    2009-03-01

    The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

  18. Creation of a new-generation research nuclear facility

    International Nuclear Information System (INIS)

    Girchenko, A.A.; Matyushin, A.P.; Kudryavtsev, E.M.; Skopin, V.P.; Shchepelev, R.M.

    2013-01-01

    The SO-2M research nuclear facility operated on the industrial area of the institute. The facility is now removed from service. In view of this circumstance, it is proposed to restore the facility at the new qualitative level, i.e., to create a new-generation research nuclear facility with a very high safety level consisting of a subcritical bench and a proton accelerator (electronuclear facility). Competitive advantages and design features have been discussed and the productive capacity of the research nuclear facility under development has been evaluated [ru

  19. Nuclear and conventional baseload electricity generation cost experience

    International Nuclear Information System (INIS)

    1993-04-01

    The experienced costs of electricity generation by nuclear and conventional plants and the expected costs of future plants are important for evaluating the economic attractiveness of various power projects and for planning the expansion of electrical generating systems. The main objective of this report is to shed some light on recent cost experience, based on well authenticated information made available by the IAEA Member States participating in this study. Cost information was provided by Canada (Ontario Hydro), Czechoslovakia, Hungary, India, the Republic of Korea and Spain. Reference is also made to information received from Brazil, China, France, Russia and the United States of America. The part of the report that deals with cost experience is Section 2, where the costs of both nuclear and fossil fired plants are reviewed. Other sections give emphasis to the analysis of the major issues and relevant cost elements influencing the costs of nuclear power plants and to a discussion of cost projections. Many of the conclusions can also be applied to conventional plants, although they are usually less important than in the case of nuclear plants. 1 ref., figs and tabs

  20. Glas generator for the steam gasification of coal with nuclear generated heat

    International Nuclear Information System (INIS)

    Buchner, G.

    1980-01-01

    The use of heat from a High Temperature Reactor (HTR) for the steam gasification of coal saves coal, which otherwise is burnt to generate the necessary reaction heat. The gas generator for this process, a horizontal pressure vessel, contains a fluidized bed of coal and steam. An ''immersion-heater'' type of heat exchanger introduces the nuclear generated heat to the process. Some special design problems of this gasifier are presented. Reference is made to the present state of development of the steam gasification process with heat from high temperature reactors. (author)

  1. Electrosleeve process for in-situ nuclear steam generator repair

    International Nuclear Information System (INIS)

    Renaud, E.; Brennenstuhl, A.M.; Stewart, D.R.; Gonzalez, F.

    2000-01-01

    Degradation of steam generator tubing by localized corrosion is a widespread problem in the nuclear industry that can lead to costly forced outages, unit derating, steam generator replacement or even the permanent shutdown of a reactor. In response to the onset of steam generator degradation at Ontario Power Generation's Pickering Nuclear Generating Station (PNGS) Unit 5, and the determined unsuitability of conventional repair methods (mechanically expanded or welded sleeves) for Alloy 400, an alternative repair technology was developed. Electrosleeve is a non-intrusive, low-temperature process that involves the electrodeposition of a nanocrystalline nickel microalloy forming a continuously bonded, structural layer over the internal diameter of the degraded region. This technology is designed to provide a long-term pressure boundary repair, fully restoring the structural integrity of the damaged region to its original state. This paper describes the Electrosleeve process for steam generator tubing repair and the unique properties of the advanced sleeve material. The successful installation of fourteen Electrosleeves that have been in service for more than six years in Alloy 400 tubing at the Pickering-S CANDU unit, and the more recent (Nov. 99) extension of the technology to Alloy 600 by the installation of 57 sleeves in a U.S. pressurized water reactor (PWR) at Callaway, is presented. The Electrosleeve process has been granted a conditional license by the U.S. Nuclear Regulatory Commission (NRC). In Canada, the process of licensing Electrosleeve with the CNSC / TSSA has begun. (author)

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

    International Nuclear Information System (INIS)

    Zare Shahneh, Abolghasem.

    1995-03-01

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

  3. Nuclear power plants and their position in the competitive generation industry of the USA

    International Nuclear Information System (INIS)

    Petroll, M.R.

    2000-01-01

    One effect to be observed in the USA is that power trading in the deregulated electricity sector initiates a 'comeback' of the nuclear power stations, reputed to be dead by anti-nuclear power policy followers. Quite to the contrary, growing competition in the generation industry and the resulting upward pressure on costs increasingly induce power generation companies to enter into competitive buying of nuclear power stations, which offer better availability and prolonged service life. The article gives the technical details and explains the economic reasons for this trend in an analysis comparing nuclear power generation with conventional or new non-nuclear generation technologies. (orig./CB) [de

  4. Iran's nuclear program - for power generation or nuclear weapons?

    International Nuclear Information System (INIS)

    Kippe, Halvor

    2008-11-01

    would withdraw from the Nuclear Non-proliferation Treaty (NPT), has generated enough concern among several of the dominant nations in the world, that they have gone to great lengths to try to dissuade Tehran from the continued pursuit of its in principle legal nuclear activities. As this report is issued, Iran still has some way ahead before its infrastructure can readily provide it with nuclear weapons on demand. But Iran seems almost to have overcome the presumably highest technological threshold, namely full-scale uranium enrichment. Today's infrastructure is far from sufficiently developed to be able to fully support Iran's planned nuclear power developments, but on the other hand the need for indigenously produced nuclear fuel is also several years ahead, as long as Iran's first self-constructed nuclear power plant is far from completion. The known and assumed uranium deposits, however, are of minute proportions compared to the stated ambitions of their nuclear power programme (20 GWe within 2030). Iran's future reactors will hardly be able to go online before they become dependent on fuel from abroad. The uranium deposits are, on the other hand, abundant for the future production of several thousands of nuclear weapons. And if the infrastructure that is arising today is actually directed towards that purpose, Iran will in theory some day be able to produce more than a hundred nuclear weapons a year. (Author)

  5. Nuclear data processing and multigroup cross section generation

    International Nuclear Information System (INIS)

    Kim, Jeong Do; Kil, Chung Sub

    1996-01-01

    The multigroup constants for WIMS/CASMO were updated with ENDF/B-VI and were tested. The continuous energy MCNP library developed last year was validated against the LWR-simulated critical experiments. The MCNP library will be used to design and analyze nuclear and shielding facilities. The system for generation of MATXS multigroup library and TRANSX code, which is able to prepare the data for the discrete ordinates and diffusion codes from the MATXS library, was established. The MATXS libraries for analyses of thermal and fast critical experiments were generated and tested. The MATXS/TRANSX system for the discrete ordinates and diffusion codes will be useful for nuclear analyses. 10 tabs., 5 figs., 17 refs. (Author)

  6. Prerequisites for successful nuclear generation in Southern Africa

    International Nuclear Information System (INIS)

    Semark, P.M.

    1990-01-01

    In this paper, the General Manager (Generation) of Eskom shares his view of what is required to be addressed to ensure the ongoing success of nuclear powered electricity generation in South Africa. The task, the means, the timing and the human factors are discussed from the practical viewpoint of the plant owner and operator. (author)

  7. Prerequisites for successful nuclear generation in Southern Africa

    Energy Technology Data Exchange (ETDEWEB)

    Semark, P M [ESKOM, Johannesburg (South Africa)

    1990-06-01

    In this paper, the General Manager (Generation) of Eskom shares his view of what is required to be addressed to ensure the ongoing success of nuclear powered electricity generation in South Africa. The task, the means, the timing and the human factors are discussed from the practical viewpoint of the plant owner and operator. (author)

  8. World nuclear generating capacity and uranium requirements to 2005

    International Nuclear Information System (INIS)

    Anon.

    1991-01-01

    The outlook for the world nuclear power industry through 2005 is more positive than some may believe. Installed nuclear electric generating capacity is forecast to grow at an average rate of 2.4 percent per year, and reach 448 gigawatts electric (GWe) by 2005. Consequently, annual world uranium requirements also will grow, reaching over 200 million pounds equivalent U 3 O 8 by 2005. This article presents data and summarizes installed nuclear generating capacity and charts its increase as a function of time through the year 2005. This data is also charted by reactor type as well as reactor status: under construction, planned, or estimated future construction. In a similar fashion, the data is also charted by country and continent. Historical and projected data is also given for capacity factor

  9. Attitude changes toward nuclear power generation. Analysis of data from a longitudinal survey

    International Nuclear Information System (INIS)

    Matsuda, Toshihiro

    1998-01-01

    The Attitude changes toward nuclear power generation in response to incidents/accidents at the nuclear facilities were examined, using a longitudinal survey. A replicated survey was conducted in Kansai area following the incidents in 1995 and 1997, and a panel survey was conducted in 1997, using the same subjects as those in the survey conducted by C. Hayashi in 1993 about the attitude toward nuclear power generation. The results of the panel survey showed that an anxiety about a nuclear incident/accident tended to increase and that the number of those who decreased an anxiety about a nuclear incident/accident was relatively small, compared to an anxiety about other incidents/accidents. Using the quantification theory to analyze the group that showed changes in attitude toward nuclear power generation, it was suggested that the increase or decrease in the level of anxiety about a nuclear power incident/accident had an influence on the changes in attitude. However, the influence was not the most significant one compared to other factors. With the inclusion of the group that showed no change in attitude, the general population structure that the approval for nuclear power generation because of inevitable use of nuclear energy accounted for sixty percent remained with no significant change. (author)

  10. Energy Balance of Nuclear Power Generation. Life Cycle Analyses of Nuclear Power

    International Nuclear Information System (INIS)

    Wallner, A.; Wenisch, A.; Baumann, M.; Renner, S.

    2011-01-01

    The accident at the Japanese nuclear power plant Fukushima in March 2011 triggered a debate about phasing out nuclear energy and the safety of nuclear power plants. Several states are preparing to end nuclear power generation. At the same time the operational life time of many nuclear power plants is reaching its end. Governments and utilities now need to take a decision to replace old nuclear power plants or to use other energy sources. In particular the requirement of reducing greenhouse gas emissions (GHG) is used as an argument for a higher share of nuclear energy. To assess the contribution of nuclear power to climate protection, the complete life cycle needs to be taken into account. Some process steps are connected to high CO2 emissions due to the energy used. While the processes before and after conventional fossil-fuel power stations can contribute up to 25% of direct GHG emission, it is up to 90 % for nuclear power (Weisser 2007). This report aims to produce information about the energy balance of nuclear energy production during its life cycle. The following key issues were examined: How will the forecasted decreasing uranium ore grades influence energy intensity and greenhouse emissions and from which ore grade on will no energy be gained anymore? In which range can nuclear energy deliver excess energy and how high are greenhouse gas emissions? Which factors including ore grade have the strongest impact on excess energy? (author)

  11. Regional projections of nuclear and fossil electric power generation costs

    International Nuclear Information System (INIS)

    Smolen, G.R.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

    1983-12-01

    The total busbar electric generating costs were estimated for locations in ten regions of the United States for base load nuclear and coal-fired power plants with a startup date of January 1995. A complete data set is supplied which specifies each parameter used to obtain the comparative results. When the comparison is based on reference cost parameters, nuclear- and coal-fired generation costs are found to be very close in most regions of the country. Nuclear power is favored in the South Atlantic region where coal must be transported over long distances, while coal-fired generation is favored in the Central and North Central regions where large reserves of cheaply mineable coal exist. The reference data set reflects recent electric utility construction experience. Significantly lower nuclear capital investment costs would result if regulatory reform and improved construction practices were instituted. The electric power generation costs for base load oil- and natural gas-fired plants were also estimated. These plants were found to be noncompetitive in all regions for those scenarios most likely to develop. Generation cost sensitivity to changes in various parameters was examined at a reference location. The sensitivity parameters included capital investment costs, lead times, capacity factors, costs of money, and coal and uranium prices. In addition to the levelized lifetime costs, year-by-year cash flows and revenue requirements are presented. The report concludes with an analysis of the economic merits of recycling spent fuel in light-water reactors

  12. Pulse generator circuit triggerable by nuclear radiation

    International Nuclear Information System (INIS)

    Fredrickson, P.B.

    1980-01-01

    A pulse generator circuit triggerable by a pulse of nuclear radiation is described. The pulse generator circuit includes a pair of transistors arranged, together with other electrical components, in the topology of a standard monostable multivibrator circuit. The circuit differs most significantly from a standard monostable multivibrator circuit in that the circuit is adapted to be triggered by a pulse of nuclear radiation rather than electrically and the transistors have substantially different sensitivities to radiation, due to different physical and electrical characteristics and parameters. One of the transistors is employed principally as a radiation detector and is in a normally non-conducting state and the other transistor is normally in a conducting state. When the circuit is exposed to a pulse of nuclear radiation, currents are induced in the collector-base junctions of both transistors but, due to the different radiation sensitivities of the transistors, the current induced in the collector-base junction of the radiation-detecting transistor is substantially greater than that induced in the collector-base junction of the other transistor. The pulse of radiation causes the radiation-detecting transistor to operate in its conducting state, causing the other transistor to operate in its non-conducting state. As the radiation-detecting transistor operates in its conducting state, an output signal is produced at an output terminal connected to the radiation-detecting transistor indicating the presence of a predetermined intensity of nuclear radiation

  13. Korean students' behavioral change toward nuclear power generation through education

    International Nuclear Information System (INIS)

    Han, Eun Ok; Kim, Jae Rok; Choi, Yoon Seok

    2014-01-01

    As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017), safety (p<0.000), information acquisition (p<0.000), and subjective knowledge (p<0.000), objective knowledge (p<0.000), attitude (p<0.000), and behavior (p<0.000) were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

  14. Korean students' behavioral change toward nuclear power generation through education

    Energy Technology Data Exchange (ETDEWEB)

    Han, Eun Ok; Kim, Jae Rok; Choi, Yoon Seok [Dept. of Education and Research, Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2014-10-15

    As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017), safety (p<0.000), information acquisition (p<0.000), and subjective knowledge (p<0.000), objective knowledge (p<0.000), attitude (p<0.000), and behavior (p<0.000) were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

  15. Present status and future outlook of nuclear power generation in Japan

    International Nuclear Information System (INIS)

    Kunikazu Aisaka

    1987-01-01

    The structure of energy consumption in Japan is heavily dependent on imported oil, therefore Japan has been making its greatest effort in developing nuclear power among other alternatives of oil. The capacity factor of the nuclear power plants in Japan marked 76% in FY 1986, exceeding 70% level for the past several years. The share of nuclear power is expected to increase steadily in the future. Future scale of the nuclear power generation is projected as 62,000 MW in year 2000 and as 137,000 MW in 2030. Nuclear power is expected to produce 58% of the nation's total power generation in 2030. Under the present circumstances, Janpan is executing a nuclear energy policy based on the following guidelines: 1. Promoting the safety advancement program; 2. Improving LWR technologies; 3. Program on use of plutonium in thermal reactors; 4. Advanced thermal reactors (ATRs); 5. Promotion of FBR development; 6. Nuclear fuel cycle. (Liu)

  16. Revalidation program for nuclear standby diesel generators

    International Nuclear Information System (INIS)

    Muschick, R.P.

    1985-01-01

    This paper describes the program which Duke Power Company carried out to revalidate the diesel engines used in diesel generators for nuclear standby service at Unit 1 of the Catawba Nuclear Station. The diesels operated satisfactorily during the tests, and only relatively minor conditions were noted during the test and inspections, with one exception. This exception was that cracks were detected in the piston skirts. The piston skirts have been replaced with improved design skirts. The diesels have been fully revalidated for their intended service, and have been declared operable

  17. An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems

    International Nuclear Information System (INIS)

    Leahy, Timothy J.

    2010-01-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated 'toolkit' consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

  18. Strain measurements of nuclear power plant steam generator antiseismic supports

    International Nuclear Information System (INIS)

    Kulichevsky, R.

    1997-01-01

    The nuclear power plants steam generators have different types of structural supports. One of these types are the antiseismic supports, which are intended to be under stress only if a seismic event takes place. Nevertheless, the antiseismic supports lugs, that are welded to the steam generator vessel, are subjected to thermal fatigue because of the temperature cycles related with the shut down and start up operations performed during the life of the nuclear power plant. In order to evaluate the stresses that the lugs are subjected to, several strain gages were welded on two supports lugs, positioned at two heights of one of the Embalse nuclear power plant steam generators. In this paper, the instrumentation used and the strain measurements obtained during two start up operations are presented. The influence of the plant start up operation parameters on the lugs strain evolution is also analyzed. (author) [es

  19. Research on the response of various persons to information about nuclear power generation

    International Nuclear Information System (INIS)

    Maruta, Katsuhiko

    2014-01-01

    The author surveyed blogs readily available on the Internet for three purposes: (1) to grasp the public response to nuclear problems after the accident at the Fukushima Daiichi Nuclear Power Station, (2) to determine changes in the number of blogs based on an article search, and (3) to identify the stance of bloggers on the necessity of nuclear power generation based on reading contribution contents. Furthermore the author conducted a questionnaire survey of public response in reference to the results of the blog survey. From the blog survey, it was found that immediately after the accident, the number of blogs which were negative toward nuclear power generation drastically increased, but as time has passed, blogs which are positive are increasing in number somewhat in expectation of stabilized economic and living conditions. The main results of the questionnaire survey are as follows. (1) Many persons want power generation that is non-nuclear; this is because they have good expectations for renewable energy sources or new thermal power generation as an alternative energy and they strongly feel anxious about the issue of disposal of spent nuclear fuel. (2) Because of the risk of negative impacts which electricity shortages bring on the economy and lifestyles, some persons do not want immediate decommissioning of nuclear power reactors, they favor a phase-out of nuclear power generation. Though public opinion about nuclear problems includes the expectation that one alternative energy can be selected, there is a possibility that this opinion will shift to find an optimum energy mix of plural energy sources. (author)

  20. Nuclear economics 2000: Deterministic and probabilistic projections of nuclear and coal electric power generation costs for the year 2000

    International Nuclear Information System (INIS)

    Williams, K.A.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

    1987-06-01

    The total busbar electric generating costs were estimated for locations in ten regions of the United States for base-load nuclear and coal-fired power plants with a startup date of January 2000. For the Midwest region a complete data set that specifies each parameter used to obtain the comparative results is supplied. When based on the reference set of input variables, the comparison of power generation costs is found to favor nuclear in most regions of the country. Nuclear power is most favored in the northeast and western regions where coal must be transported over long distances; however, coal-fired generation is most competitive in the north central region where large reserves of cheaply mineable coal exist. In several regions small changes in the reference variables could cause either option to be preferred. The reference data set reflects the better of recent electric utility construction cost experience (BE) for nuclear plants. This study assumes as its reference case a stable regulatory environment and improved planning and construction practices, resulting in nuclear plants typically built at the present BE costs. Today's BE nuclear-plant capital investment cost model is then being used as a surrogate for projected costs for the next generation of light-water reactor plants. An alternative analysis based on today's median experience (ME) nuclear-plant construction cost experience is also included. In this case, coal is favored in all ten regions, implying that typical nuclear capital investment costs must improve for nuclear to be competitive

  1. Foresight of nuclear generation at long term in Mexico

    International Nuclear Information System (INIS)

    Guadarrama L, R.; Sanchez R, O. E.; Martin del Campo M, C.

    2009-10-01

    This paper presents an analysis of the nuclear generation expansion for the period 2008-2030. The main objective is to plan the expansion of electrical generation system at long term taking into account four decision criteria. These are, the total cost of generation, the risk associated whit changes in fuel prices, the diversity of the generation park and polluting emissions of global impact (greenhouse effect gases) and local effects (acid rain and suspended particles). The analyzed expansion plans were developed using a model of uni nodal planning called WASP-IV. The analysis methodology was based on four steps. The first consisted in developing, with model WASP-IV, different expansion plans of the electrical generation system that fulfill the energy demand and certain conditions of the study in which was optimized the additions program of generator units searching the minimal cost of electrical generation. The second step was to calculate the generation costs of each plan for two scenarios of fuel prices, also with model WASP-IV. Later was calculated the diversity index and the accumulated emissions during the expansion and the avoided emission of CO 2 when units of combined cycle that burn natural gas are replaced by nuclear power units. (Author)

  2. Aging mitigation and improved programs for nuclear service diesel generators

    International Nuclear Information System (INIS)

    Hoopingarner, K.R.; Zaloudek, F.R.

    1989-12-01

    Recent NRC sponsored aging research work on nuclear service diesel generators has resulted in a recommendation that an improved engine management program should be adopted for aging mitigation and reliability improvement. The center of attention should be to ensure diesel-generator operational readiness. This report emphasizes a ''healthy engine concept'' and recommends parameters to be monitored to determine engine condition. The proposed program and approach recommended in this report represent balanced management where diesel generator testing, inspections, monitoring, trending, training, and maintenance all have appropriate importance. Fast-starting and fast-loading test of nuclear service diesels causes very rapid wear of certain engine components. This report documents this aging and wear mechanism and recommends ways to largely eliminate this unique aging stressor. Current periodic intrusive maintenance and engine overhaul practice have been found to be less favorable for safety assurance than engine overhauls based on monitoring and trending results or on a need to correct specific engine defects. This report recommends that the periodic overhaul requirements be re-evaluated. Diesel generator research on aging and wear is sponsored by the US Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research. The research reported in this report was conducted by Pacific Northwest Laboratory (PNL), which is operated for the Department of Energy by Battelle Memorial Institute. 23 refs., 3 figs., 8 tabs

  3. Facing the challenges of nuclear power at Ontario Power Generation

    International Nuclear Information System (INIS)

    Howes, H.

    1999-01-01

    Nuclear power represents a major portion of Ontario Power Generation's generation mix and it will be the bedrock upon which we build a successful, competitive company. Our nuclear units offer many environmental and economic benefits, the one most relevant to this meeting is their significant contribution to the relatively low carbon intensity of Ontario's and Canada's electricity supply. In recent weeks, we have listened with great interest to the endorsement by our federal Minister of the Environment of nuclear technology as a means of reducing global warming. But endorsements of this type alone are not sufficient to ensure that nuclear remains an acceptable option for managing greenhouse gas emissions. Without public acceptance and support, the entire nuclear investment is endangered. At OPG we face three challenges to building this public support: we must continue to improve our safety margins and operating performance; we must continue to improve the environmental performance at our stations; and we must increase our community outreach. Today I would like to focus on the last two challenges and the actions that we are taking to maintain our social and environmental 'licence to operate.' But before I describe these initiatives, I will tell you about: the new company - Ontario Power Generation; the changes in store for Ontario's electricity sector; and our greenhouse gas emissions - the legacy from Ontario Hydro. (author)

  4. Salt disposal of heat-generating nuclear waste

    International Nuclear Information System (INIS)

    Leigh, Christi D.; Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United

  5. Salt disposal of heat-generating nuclear waste.

    Energy Technology Data Exchange (ETDEWEB)

    Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from

  6. Generation of Matxs-formated nuclear data libraries

    International Nuclear Information System (INIS)

    Vontobel, P.

    1989-01-01

    Using the NJOY nuclear data processing system, three multigroup MATXS-formated nuclear data libraries were generated based on the European data files JEF-1 and EFF-1. After processing with TRAMIX, TRANSX, or TRANSX-CTR these libraries can be red into most transport and diffusion codes. For the neutron analysis of gas-cooled or water moderated thermal reactor systems (including high converter PWR's) a 70-group WIMS-BOXER structured library was generated. A general purpose fine group library in 308 groups is provided for thermal as well as for fast reactor systems. A coupled 175 neutron/42 photon-group library in VITAMIN-J structure was created for the analysis of shielding problems and fusion blanket design. A problem found when using CRAY's CFT77 compiler to implement NJOY87 is discussed. The problem of irregular selfshielding factors from UNRESR for some isotopes and (σ 0 , material temperature)-combinations in the unresolved resonance range is addressed

  7. Wavelet network controller for nuclear steam generators

    International Nuclear Information System (INIS)

    Habibiyan, H; Sayadian, A; Ghafoori-Fard, H

    2005-01-01

    Poor control of steam generator water level is the main cause of unexpected shutdowns in nuclear power plants. Particularly at low powers, it is a difficult task due to shrink and swell phenomena and flow measurement errors. In addition, the steam generator is a highly complex, nonlinear and time-varying system and its parameters vary with operating conditions. Therefore, it seems that design of a suitable controller is a necessary step to enhance plant availability factor. The purpose of this paper is to design, analyze and evaluate a water level controller for U-tube steam generators using wavelet neural networks. Computer simulations show that the proposed controller improves transient response of steam generator water level and demonstrate its superiority to existing controllers

  8. Change of public awareness on nuclear power generation in 2010

    International Nuclear Information System (INIS)

    Shimooka, Hiroshi

    2011-01-01

    The eighth attitude survey for nuclear power generation was carried out by two methods (the written questionnaire survey and online survey), from 22nd in October to 22nd in November, 2010. The survey population of the first method was 500, 250 of male and 250 female from over twenty years old lived within 30 km from Tokyo station. That of second method was 500 from over twenty years old lived in the Metropolitan area. The questionnaire consisted of four items such as awareness on the general public and life, energy problems, nuclear power generation and others. The written questionnaire survey showed almost same results as the previous surveys. New results showed some subjects (23%) thought the nuclear power generation was useful at that time but not useful in the future. Outline of survey, the main results, the analytical results and comparison between the written questionnaire survey and online survey were reported. (S.Y.)

  9. Generation of nuclear magnetic resonance images

    International Nuclear Information System (INIS)

    Beckmann, N.X.

    1986-01-01

    Two generation techniques of nuclear magnetic resonance images, the retro-projection and the direct transformation method are studied these techniques are based on the acquisition of NMR signals which phases and frequency components are codified in space by application of magnetic field gradients. The construction of magnet coils is discussed, in particular a suitable magnet geometry with polar pieces and air gap. The obtention of image contrast by T1 and T2 relaxation times reconstructed from generated signals using sequences such as spin-echo, inversion-recovery and stimulated echo, is discussed. The mathematical formalism of matrix solution for Bloch equations is also presented. (M.C.K.)

  10. Basic recognition on safety of nuclear electric power generation

    International Nuclear Information System (INIS)

    Miyazaki, Keiji

    1995-01-01

    The safety of nuclear electric power generation is not to inflict radiation damage on public. Natural radiation is about 1 mSv every year. As far as the core melting on large scale does not occur, there is not the possibility of exerting serious radiation effect to public. The way of thinking on ensuring the safety is defense in depth. The first protection is the prevention of abnormality, the second protection is the prevention of accidents, and the third protection is the relaxation of effect. As design base accidents, the loss of coolant accident due to the breakdown of inlet pipings of reactors and the breaking of fine tubes in steam generators are included. The suitability of location is evaluated. As the large scale accidents of nuclear power stations in the past, Chernobyl accident and Three Mile Island accident are explained. The features of the countermeasures to the accident in Mihama No. 2 plant are described. The countermeasures to severe accidents, namely accident management and general preventive maintenance are explained. The background of the nonconfidence feeling to nuclear electric power generation and the importance of opening information to public are shown. (K.I.)

  11. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sup; Min, Byung Joo; Lee, Jong Tai [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-01-01

    In nuclear or shielding design analysis for reactors or other facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multi-group constant library using the newly compiled data files and the code systems. As the results of this project, the latest version of NJOY nuclear data processing system, NJOY91.38 which is capable of processing data in ENDF-6 format, was compiled and installed in Cyber 960-31(OS : NOS/VE) and HP710 workstation. A 50-group constant library for fast reactor was generated with NJOY91.38 using evaluated data from JEF-1 and benchmark test of this library was performed. The newly generated library has been found to do an excellent job of calculating integral quantities for fast critical assemblies and is expected to be positively used to develop fast reactors. (Author).

  12. Nuclear data banks generation by interpolation; Generacion de bancos de datos nucleares mediante interpolacion

    Energy Technology Data Exchange (ETDEWEB)

    Castillo M, J A

    1999-07-01

    Nuclear Data Bank generation, is a process in which a great amount of resources is required, both computing and humans. If it is taken into account that at some times it is necessary to create a great amount of those, it is convenient to have a reliable tool that generates Data Banks with the lesser resources, in the least possible time and with a very good approximation. In this work are shown the results obtained during the development of INTPOLBI code, use to generate Nuclear Data Banks employing bicubic polynominal interpolation, taking as independent variables the uranium and gadolinia percents. Two proposal were worked, applying in both cases the finite element method, using one element with 16 nodes to carry out the interpolation. In the first proposals the canonic base was employed, to obtain the interpolating polynomial and later, the corresponding linear equation systems. In the solution of this systems the Gaussian elimination methods with partial pivot was applied. In the second case, the Newton base was used to obtain the mentioned system, resulting in a triangular inferior matrix, which structure, applying elemental operations, to obtain a blocks diagonal matrix, with special characteristics and easier to work with. For the validation tests, a comparison was made between the values obtained with INTPOLBI and INTERTEG (create at the Instituto de Investigaciones Electricas (MX) with the same purpose) codes, and Data Banks created through the conventional process, that is, with nuclear codes normally used. Finally, it is possible to conclude that the Nuclear Data Banks generated with INTPOLBI code constitute a very good approximation that, even though do not wholly replace conventional process, however are helpful in cases when it is necessary to create a great amount of Data Banks.

  13. Reliability of diesel generators in the Finnish and Swedish nuclear power plants

    International Nuclear Information System (INIS)

    Pulkkinen, U.; Huovinen, T.; Norros, L.; Vanhala, J.

    1989-10-01

    Diesel generators are used as emergency AC-power sources in nuclear power plants and they produce electric power for other emergency systems during accidents in which offsite power is lost. The reliability of diesel generators is thus of major concern for overall safety of nuclear power plants. In this study we consider the reliability of diesel generators in the Swedish and Finnish nuclear power plants on the basis of collected operational experience. We classify the occurred failures according to their functional criticality, type and cause. The failures caused by human errors in maintenance and testing are analysed in detail. We analyse also the reliability of the diesel generator subsystems. Further, we study the effect of surveillance test and the type of test on the reliability. Finally we construct an unavailability model for single diesel generator unit and discuss the findings of the study giving some practical recommendations

  14. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop

    International Nuclear Information System (INIS)

    Hoopingarner, K.R.; Vause, J.W.

    1987-08-01

    Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system

  15. Improving nuclear generating station response for electrical grid islanding

    International Nuclear Information System (INIS)

    Chou, Q.B.; Kundur, P.; Acchione, P.N.; Lautsch, B.

    1989-01-01

    This paper describes problems associated with the performance characteristics of nuclear generating stations which do not have their overall plant control design functions co-ordinated with the other grid controls. The paper presents some design changes to typical nuclear plant controls which result in a significant improvement in both the performance of the grid island and the chances of the nuclear units staying on-line following the disturbance. This paper focuses on four areas of the overall unit controls and turbine governor controls which could be modified to better co-ordinate the control functions of the nuclear units with the electrical grid. Some simulation results are presented to show the performance of a typical electrical grid island containing a nuclear unit with and without the changes

  16. Materials for generation-IV nuclear reactors

    International Nuclear Information System (INIS)

    Alvarez, M. G.

    2009-01-01

    Materials science and materials development are key issues for the implementation of innovative reactor systems such as those defined in the framework of the Generation IV. Six systems have been selected for Generation IV consideration: gas-cooled fast reactor, lead-cooled fast reactor, molten salt-cooled reactor, sodium-cooled fast reactor, supercritical water-cooled reactor, and very high temperature reactor. The structural materials need to resist much higher temperatures, higher neutron doses and extremely corrosive environment, which are beyond the experience of the current nuclear power plants. For this reason, the first consideration in the development of Generation-IV concepts is selection and deployment of materials that operate successfully in the aggressive operating environments expected in the Gen-IV concepts. This paper summarizes the Gen-IV operating environments and describes the various candidate materials under consideration for use in different structural applications. (author)

  17. Radioactive release data from Canadian nuclear generating stations 1872-1987

    International Nuclear Information System (INIS)

    1989-03-01

    All nuclear generating stations emit small quantities of radioactive effluent both into the atmosphere and in the form of liquid effluent, into the adjoining water body, be it river, lake or sea. The purpose of this document is to report on the magnitude of these emissions for each nuclear generating station in Canada and to indicate how these emissions compare with the relevant limitations imposed by the Atomic Energy Control Board as part of its regulatory and licensing program. This report incorporates histograms indicating the annual releases of tritium in air, noble gases, iodine-131, airborne particulates, tritium in water and waterborne gross beta activity for each nuclear generating station. In addition, for Pickering NGS 'A', annual released of carbon-14 are depicted for the years 1986 and 1987. In each case the emission data are compared to the Derived Emission Limit (DEL) in order that the data may be placed in perspective. At present, only Pickering NGS 'A' is required to monitor and report carbon-14 emissions. Environmental monitoring for C-14 is conducted around the Bruce site to determine the environmental impact of its emission and whether effluent monitoring will be necessary in future years. Three nuclear generating stations have been permanently taken out of service during the last few years (Gentilly NGS-1, Douglas Point NGS and NPD NGS). Some small emissions from these sites do still occur, however, due to decontamination and decommissioning operations. (11 tabs., 26 figs.)

  18. Prospective thorium fuels for future nuclear energy generation

    International Nuclear Information System (INIS)

    Lainetti, Paulo E.O.

    2017-01-01

    In the beginning of the Nuclear Era, many countries were interested on thorium, particularly during the 1950 1970 periods. Nevertheless, since its discovery almost two centuries ago, the use of thorium has been restricted to gas mantles employed in gas lighting. The future world energy needs will increase and, even if we assumed a conservative contribution of nuclear generation, it will be occur a significant increasing in the uranium prices, taking into account that uranium, as used in the present thermal reactors, is a finite resource. Nowadays approximately the worldwide yearly requirement of uranium for about 435 nuclear reactors in operation is 65,000 metric t. Therefore, alternative solutions for future must be developed. Thorium is nearly three times more abundant than uranium in The Earth's crust. Despite thorium is not a fissile material, 232 Th can be converted to 233 U (fissile) more efficiently than 238 U to 239 Pu. Besides this, thorium is an environment alternative energy source and also inherently resistant to proliferation.. Many countries had initiated research on thorium in the past, Nevertheless, the interest evanesced due new uranium resources discoveries and availability of enriched uranium at low prices from obsolete weapons. Some papers evaluate the thorium resources in Brazil over 1.200.000 metric t. Then, the thorium alternative must be seriously considered in Brazil for strategic reasons. A brief history of thorium and its utilization are presented, besides a very short discussion about prospective thorium nuclear fuels for the next generation of nuclear reactors. (author)

  19. Prospective thorium fuels for future nuclear energy generation

    Energy Technology Data Exchange (ETDEWEB)

    Lainetti, Paulo E.O., E-mail: lainetti@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    In the beginning of the Nuclear Era, many countries were interested on thorium, particularly during the 1950 1970 periods. Nevertheless, since its discovery almost two centuries ago, the use of thorium has been restricted to gas mantles employed in gas lighting. The future world energy needs will increase and, even if we assumed a conservative contribution of nuclear generation, it will be occur a significant increasing in the uranium prices, taking into account that uranium, as used in the present thermal reactors, is a finite resource. Nowadays approximately the worldwide yearly requirement of uranium for about 435 nuclear reactors in operation is 65,000 metric t. Therefore, alternative solutions for future must be developed. Thorium is nearly three times more abundant than uranium in The Earth's crust. Despite thorium is not a fissile material, {sup 232}Th can be converted to {sup 233}U (fissile) more efficiently than {sup 238}U to {sup 239}Pu. Besides this, thorium is an environment alternative energy source and also inherently resistant to proliferation.. Many countries had initiated research on thorium in the past, Nevertheless, the interest evanesced due new uranium resources discoveries and availability of enriched uranium at low prices from obsolete weapons. Some papers evaluate the thorium resources in Brazil over 1.200.000 metric t. Then, the thorium alternative must be seriously considered in Brazil for strategic reasons. A brief history of thorium and its utilization are presented, besides a very short discussion about prospective thorium nuclear fuels for the next generation of nuclear reactors. (author)

  20. Production of gel 99mTc generators for Nuclear Medicine at the Nuclear Power Institute of China, Chengdu

    International Nuclear Information System (INIS)

    Boyd, R.E.

    1996-07-01

    The development and testing of the gel-type 99m Tc generator technology has been going on for several years at the Nuclear Power Institute of China. This generator type has already been licensed by the Ministry of Health. With the co-operation of the IAEA, under Model Project CPR/2/006,it is intended to upgrade and optimise the existing facility for large scale production and continue to improve the generator performance in terms of quality and reliability of its use in nuclear medicine. The expert mission objective was to carry out final laboratory tests to assess the performance of the gel- type 99m Tc, locally produced, as well as to assess the suitability of the corresponding 99m Tc eluate for nuclear medicine studies. In particular, the expert tested the suitability of the 99m Tc for the labelling of sensitive biomolecules and its general performance in a nuclear medicine service

  1. Nuclear power - strategic planning for the next generation

    International Nuclear Information System (INIS)

    Turner, K.H.

    1989-01-01

    Regardless of the real or perceived causes of the nuclear power industry's current difficulties, a number of recent trends-increasing electricity demand, foreign oil dependency, and attention paid to acid rain and the greenhouse effect-taken together, point of the most favorable atmosphere in recent history for nuclear power. Already, serious public discussion of its advantages have begun anew. Thus, the time is ripe to consider the developmental structure of nuclear power's next generation. Although much uncertainty still surrounds the nuclear industry, valuable lessons have been learned, and the evolution of the industry from this point cannot be left to chance. The purpose of this paper is to discuss a framework for nuclear power strategic planning activities. The strategic planning objectives outlined in this paper span issues that affect virtually every aspect of the nuclear power industry. Piecemeal responses to the vagaries of random stimuli will not be adequate. A proactive, integrated, industry-wide initiative-an Institute of Nuclear Power Planning, actively supported by the members of the industry-should be undertaken immediately to fill the strategic planning role. In so doing, the industry will not only be acting in its own best interest but will also be helping the nation realize the real and important benefits of its nuclear power technology

  2. Some consideration on nuclear power development. Topics aroused by U.S. proposed 'Generation IV Nuclear Power System

    International Nuclear Information System (INIS)

    Wang Chuanying; Chen Shiqi

    2001-01-01

    U.S. proposed 'Generation IV Nuclear Power System' concept. Its origin and proposed goals for it are analyzed; goals are compared with requirements of URD. In particular, discussed issues on nuclear fuel cycle and Non-proliferation. A well-considered nuclear power development plan, paying close attention to international trend and considering comprehensively domestic situation, is expected

  3. The competitive economics of a middle aged multi unit nuclear generating station

    International Nuclear Information System (INIS)

    Talbot, K.H.

    1994-01-01

    In 1992 Ontario Hydro's 15 year old 4 x 850 MWe Candu, Bruce A Nuclear Generating Station was predicted to need considerable capital investment to replace pressure tubes, steam generators and other prematurely ageing equipment in order to restore the station to high performance. Over the subsequent two years the station has undergone 2 major economic assessment studies which have confirmed the economic viability of continued operation of the plant. Declining demand for electricity in Ontario combined with a excess of generating capacity and a need to stabilise electricity rates have however forced significant operational cost reductions and reduced capital availability for rehabilitation work, it's medium and long term future remains in question. This presentation offers a practical illustration of the need to maintain steady high performance from nuclear generating plant via the appropriate life management techniques. The avoidance of mid life infusion of capital is considered as essential if nuclear generation is to successfully survive major changes in economic conditions. 2 tabs., 7 figs

  4. Nuclear power - a business driver for the next generation

    Energy Technology Data Exchange (ETDEWEB)

    Hoffman, D.R. [American Nuclear Society, La Grange Park, Illinois (United States)

    2013-07-01

    This paper the business aspects of nuclear power. It gives a snapshot of energy sources in the US and the distribution of electricity generation between coal, natural gas, hydropower, renewables such as biomass, geothermal, solar, wind, petroleum and other gases. Nuclear power continues to be an important source of electricity. It outlines the impact of new construction in creating jobs, economics and price stability of electricity.

  5. Background submission to the Royal Commission on Nuclear Power Generation

    International Nuclear Information System (INIS)

    1976-12-01

    The Royal Commission on Nuclear Power Generation in New Zealand is required to inquire into and report upon the likely consequences of a nuclear power programme. The New Zealand Electricity Department would have prime responsibilty for implementing the construction, operation and maintenance of nuclear power plants should the need be established and should this be acceptable to the Government. In this submission the Department has attempted to present the issues raised by the introduction of nuclear power in relatively simple terms on the assumption that elaboration can be provided later if necessary

  6. Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01

    The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

  7. Generation of artificial earthquakes for dynamic analysis of nuclear power plant

    International Nuclear Information System (INIS)

    Tsushima, Y.; Hiromatsu, T.; Abe, Y.; Tamaki, T.

    1979-01-01

    A procedure for generating artificial earthquakes for the purpose of the dynamic analysis of the nuclear power plant has been studied and relevant computer codes developed. This paper describes brieafly the generation procedure employed in the computer codes and also deals with the results of two artificial earthquakes generated as an example for input motions for the aseismic design of a BWR-type reactor building. Using one of the generated artificial earthquakes and two actually recorded earthquakes, non-linear responses of the reactor building were computed and the results were compared with each other. From this comparison, it has been concluded that the computer codes are practically usable and the generated artificial earthquakes are useful and powerful as input motions for dynamic analysis of a nuclear power plant. (author)

  8. Nuclear Energy In Switzerland: It's going ahead. Challenges For The Swiss Nuclear Society Young Generation Group

    Energy Technology Data Exchange (ETDEWEB)

    Streit, Marco [Aare-Tessin Ltd for Electricity, Bahnhofquai 12, CH-4601 Olten (Switzerland); Bichsel, Thomas [BKW FMB Energie AG, NPP Muehleberg, CH-3203 Muehleberg (Switzerland); Fassbender, Andre [NPP Goesgen-Daeniken AG, CH-4658 Daeniken (Switzerland); Horvath, Matthias [National Emergency Operations Centre, CH-8044 Zurich (Switzerland)

    2008-07-01

    Swiss energy policy is focused on generating domestic electric power without combusting fossil fuels for already four decades. Roughly 60% of the electricity is generated in hydroelectric plants, which is possible due to the country's favourable topography; the remaining 40% are produced by the country's five nuclear power plants (NPPs). As in any other country nuclear power has its enemies in Switzerland. Due to the direct democracy system in Switzerland the nuclear opposition has a lot of possibilities to disturb the energy policy. Since 1969, when the first Swiss nuclear power plant went online, four plebiscites were held on the issue of civil use of nuclear energy. Four times Swiss citizens voted in favour of further operation of the existing plants also in the latest battle for nuclear energy, which was won in 2003. In 2005 and 2006 several Swiss studies about the future energy situation, especially the electricity situation, have been published. All off them show clearly that there will be a big gab around the year 2020 when the oldest three nuclear power plants will fade out. A public debate was started, how to solve the problem. Beside others, building new nuclear power plants was mentioned and discussed rationally. In 2007 the energy police of the Swiss government changed into a more nuclear friendly position and at the end of the same year some electricity companies lunched a new build program. Hosting the International Youth Nuclear Congress 2008 (IYNC 2008) in Switzerland seems to be just the right moment for the nuclear industry in our country. The slightly changed surroundings effected the organization of Swiss Nuclear Society (SNS) and SNS Young Generation Group (SNSYG) and enlarged the fields of activities for SNSYG. Those activities mentioned in the previous chapters will be developed in the future. The discussion about new builds in Switzerland has started and because of that more nuclear activities in Switzerland will occur. And surely

  9. The potential of nuclear energy to generate clean electric power in Brazil

    International Nuclear Information System (INIS)

    Stecher, Luiza C.; Sabundjian, Gaiane; Menzel, Francine; Giarola, Rodrigo S.; Coelho, Talita S.

    2013-01-01

    The generation of electricity in Brazil is concentrated in hydroelectric generation, renewable and clean source, but that does not satisfy all the demand and leads to necessity of a supplementary thermal sources portion. Considering the predictions of increase in demand for electricity in the next years, it becomes necessary to insert new sources to complement the production taking into account both the volume being produced and the needs of environmental preservation. Thus, nuclear power can be considered a potential supplementary source for electricity generation in Brazil as well as the country has large reserves of fissile material, the generation emits no greenhouse gases, the country has technological mastery of the fuel cycle and it enables the production of large volumes of clean energy. The objective of this study is to demonstrate the potential of nuclear energy in electricity production in Brazil cleanly and safely, ensuring the supplies necessary to maintain the country's economic growth and the increased demand sustainable. For this, will be made an analysis of economic and social indicators of the characteristics of our energy matrix and the availability of our sources, as well as a description of the nuclear source and arguments that justify a higher share of nuclear energy in the matrix of the country. Then, after these analysis, will notice that the generation of electricity from nuclear source has all the conditions to supplement safely and clean supply of electricity in Brazil. (author)

  10. The generation IV nuclear reactor systems - Energy of future

    International Nuclear Information System (INIS)

    Ohai, Dumitru; Jianu, Adrian

    2006-01-01

    Ten nations joined within the Generation IV International Forum (GIF), agreeing on a framework for international cooperation in research. Their goal is to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in an economically competitive way while addressing the issues of safety, proliferation, and other public perception concerns. The objective is for the Gen IV systems to be available for deployment by 2030. Using more than 100 nuclear experts from its 10 member nations, the GIF has developed a Gen IV Technology Roadmap to guide the research and development of the world's most advanced, efficient and safe nuclear power systems. The Gen IV Technology Roadmap calls for extensive research and development of six different potential future reactor systems. These include water-cooled, gas-cooled, liquid metal-cooled and nonclassical systems. One or more of these reactor systems will provide the best combination of safety, reliability, efficiency and proliferation resistance at a competitive cost. The main goals for the Gen IV Nuclear Energy Systems are: - Provide sustainable energy generation that meets clean air objectives and promotes long-term availability of systems and effective fuel use for worldwide energy production; - Minimize and manage their nuclear waste and noticeably reduce the long-term stewardship burden in the future, improving the protection of public health and the environment; - Increase the assurance that these reactors are very unattractive and the least desirable route for diversion or theft of weapons-usable materials, and provide increased protection against acts of terrorism; - Have a clear life-cycle cost advantage over other energy sources; - Have a level of financial risk comparable to other energy projects; - Excel in safety and reliability; - Have a low likelihood and degree of reactor core damage. (authors)

  11. Nuclear power for the next generation. Proceedings. Kernenergie fuer die naechste Generation. Berichte

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The Chernobyl reactor accident was just the last but not the only occasion that threw out the question of whether nuclear power generation has reached its peak, or probably already is on the decline, or whether there will be new chances for nuclear energy on the power market. The answer to these questions depends on a variety of factors, among which the development of demand for energy, and especially electrical energy, certainly is the decisive factor. The summarizing statements published in the proceedings in hand have been written in January 1986, i.e. before the Chernobyl reactor accident; but they still are relevant, as the long-term problems of energy policy persist, and nuclear energy has to tackle the same problems as before.

  12. National need for utilizing nuclear energy for process heat generation

    International Nuclear Information System (INIS)

    Gambill, W.R.; Kasten, P.R.

    1984-01-01

    Nuclear reactors are potential sources for generating process heat, and their applications for such use economically competitive. They help satisfy national needs by helping conserve and extend oil and natural gas resources, thus reducing energy imports and easing future international energy concerns. Several reactor types can be utilized for generating nuclear process heat; those considered here are light water reactors (LWRs), heavy water reactors (HWRs), gas-cooled reactors (GCRs), and liquid metal reactors (LMRs). LWRs and HWRs can generate process heat up to 280 0 C, LMRs up to 540 0 C, and GCRs up to 950 0 C. Based on the studies considered here, the estimated process heat markets and the associated energy markets which would be supplied by the various reactor types are summarized

  13. Effects of the accident at Mihama Nuclear Power Plant Unit 3 on the public's attitude to nuclear power generation

    International Nuclear Information System (INIS)

    Kitada, Atsuko

    2005-01-01

    As part of an ongoing public opinion survey regarding nuclear power generation, which started in 1993, a survey was carried out in the Kansai and Kanto regions two months after the accident at Unit 3 of the Mihama Nuclear Power Plant. In addition to analyzing the statistically significant changes that have taken place since the previous survey (taken in 2003), increase and decrease of the ratio of answers to all the questions related to nuclear power before and after the two accidents were compared in the case of the accidents which occurred in the Mihama Unit 3 and the JCO company's nuclear-fuel plant. In the Kansai region, a feeling of uneasiness about the risky character of nuclear power generation increased to some extent, while the public's trust in the safety of nuclear power plants decreased somewhat. After a safety-related explanation on ''Early detection of troubles'' and Accident prevention'' was given from a managerial standpoint, people felt a little less at ease than they had before. Uneasiness, however, did not increase in relation to the overall safety explanation given about the engineering and technical functioning of the plant. There was no significant negative effect on the respondents' evaluation of or attitude toward nuclear power generation. It was found that the people's awareness about the Mihama Unit 3 accident was lower and the effect of the accident on their awareness of nuclear power generation was more limited and smaller when compared with the case of the JCO accident. In the Kanto region, people knew less about the Mihama Unit 3 accident than those living in the Kansai region, and they remembered the JCO accident, the subsequent cover-up by Tokyo Electric Power Company, and the resulting power shortage better than those living in Kansai. This suggested that there was a little difference in terms of psychological distance in relation to the accidents an incidents depending on the place where the events occurred and the company which

  14. Safety assessment for Generation IV nuclear systems

    International Nuclear Information System (INIS)

    Leahy, T.J.

    2012-01-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Recent RSWG work has focused on the definition of an integrated safety assessment methodology (ISAM) for evaluating the safety of Generation IV systems. ISAM is an integrated 'tool-kit' consisting of 5 analytical techniques that are available and matched to appropriate stages of Generation IV system concept development: 1) qualitative safety features review - QSR, 2) phenomena identification and ranking table - PIRT, 3) objective provision tree - OPT, 4) deterministic and phenomenological analyses - DPA, and 5) probabilistic safety analysis - PSA. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time

  15. Nuclear steam generator tube to tubesheet joint optimization

    International Nuclear Information System (INIS)

    McGregor, Rod

    1999-01-01

    Industry-wide problems with Stress Corrosion Cracking in the Nuclear Steam Generator tube-to-tubesheet joint have led to costly repairs, plugging, and replacement of entire vessels. To improve corrosion resistance, new and replacement Steam Generator developments typically employ the hydraulic tube expansion process (full depth) to minimize tensile residual stresses and cold work at the critical transition zone between the expanded and unexpanded tube. These variables have undergone detailed study using specialized X-ray diffraction and analytical techniques. Responding to increased demands from Nuclear Steam Generator operators and manufacturers to credit the leak-tightness and strength contributions of the hydraulic expansion, various experimental tasks with complimentary analytical modelling were applied to improve understanding and control of tube to hole contact pressure. With careful consideration to residual stress impact, design for strength/leak tightness optimization addresses: Experimentally determined minimum contact pressure levels necessary to preclude incipient leakage into the tube/hole interface. The degradation of contact pressure at surrounding expansions caused by the sequential expansion process. The transient and permanent contact pressure variation associated with tubesheet hole dilation during Steam Generator operation. An experimental/analytical simulation has been developed to reproduce cyclic Steam Generator operating strains on the tubesheet and expanded joint. Leak tightness and pullout tests were performed during and following simulated Steam Generator operating transients. The overall development has provided a comprehensive understanding of the fabrication and in-service mechanics of hydraulically expanded joints. Based on this, the hydraulic expansion process can be optimized with respect to critical residual stress/cold work and the strength/leakage barrier criteria. (author)

  16. How power is generated in a nuclear reactor

    International Nuclear Information System (INIS)

    Swaminathan, V.

    1978-01-01

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

  17. Design and construction features of steam generators at a nuclear power station

    International Nuclear Information System (INIS)

    Chakrabarti, A.K.; Gupta, K.N.; Bapat, C.N.; Sharma, V.K.

    1996-01-01

    The Indian nuclear power programme is based on Pressurised Heavy Water Reactors (PHWRs) using natural uranium as fuel and heavy water as reactor coolant as well as moderator. The nuclear heat is generated in the fuel located in the pressure tubes. Pressurised heavy water in the primary heat transport (PHT) system is circulated through the tubes which picks up the heat from the fuel and transfers it to ordinary water in steam generators (SGs) to produce steam. The steam is used for providing power to the turbine. The steam generator is a critical equipment in the nuclear steam supply system (NSSS) of a nuclear reactor. SG tube surface area constitute about 80% of total primary circuit surface area. A typical value in a 220 MWe reactor is 9000 m 2 which can release considerable amount of corrosion products unless very low corrosion rates are achieved by proper design, material selection and water chemistry control. Design and construction features of SGs are given. 1 tab

  18. The role of nuclear energy in the generation of electricity in Brazil

    International Nuclear Information System (INIS)

    Rosa, L.P.

    1981-01-01

    A comparative calculation of the potential of conventional electricity-generating energy sources-hydroelectric, coal, nuclear - according to different cost levels of generated energy is presented. Assuming a plausible estimate of the demand increase for electricity in the country, calculations show that nuclear energy will have an important role in Brazil only in the second decade of the next century. The potential of some other alternative electricity generating sources is calculated - shale and biomass (bagasse and biogas of vinhoto are discussed) - indicating that by that time nuclear energy will indeed be an option, but not necessarily the only one or the best. Finally a chronological table has been worked out indicating a construction schedule for the reactors in case the option is for nuclear energy - keeping in mind that this option does not depend exclusively on technical and economic but also political criteria and therefore requires a democratic decision-making process. (Author) [pt

  19. A century of nuclear science. Important contributions of early generation Chinese physicist to nuclear science

    International Nuclear Information System (INIS)

    Zheng Chunkai; Xu Furong

    2003-01-01

    The great discoveries and applications of nuclear science have had tremendous impact on the progress and development of mankind over the last 100 years. In the 1920's to 1940's, many young Chinese who yearned to save the country through science and education went to west Europe and north America to study science, including physics. Studying and working with famous physicists throughout the world, they made many important contributions and discoveries in the development of nuclear science. This paper describes the historical contributions of the older generation of Chinese physicists to nuclear science

  20. A High Intensity Multi-Purpose D-D Neutron Generator for Nuclear Engineering Laboratories

    International Nuclear Information System (INIS)

    Ka-Ngo Leung; Jasmina L. Vujic; Edward C. Morse; Per F. Peterson

    2005-01-01

    This NEER project involves the design, construction and testing of a low-cost high intensity D-D neutron generator for teaching nuclear engineering students in a laboratory environment without radioisotopes or a nuclear reactor. The neutron generator was designed, fabricated and tested at Lawrence Berkeley National Laboratory (LBNL)

  1. Why nuclear power generation must be developed? A many-faceted verification of its irreplaceable role

    International Nuclear Information System (INIS)

    Kawai, Yuichi; Oda, Toshiyuki

    1998-01-01

    Given the poor public acceptance right now, the future of nuclear power development is not necessarily bright. Yet, from the energy security aspect, the role of nuclear power, already responsible for about 30% of Japan's generated output, is never negligible. Also, Japan could hardly meet the GHG reduction target under the Kyoto Protocol without carbon-free nuclear power generation. While Japan is required to deal with both energy security and global warming from now on, to satisfy the two concurrently without nuclear power development is nearly impossible in practical terms. We have to consider calmly how nuclear power generation should be understood and treated in our effort to ensure energy supply and mitigate global warming. With this study, the need for nuclear power development was verified anew by reevaluating nuclear power generation from many facets, which are energy (electricity) supply and demand, environmental measures, energy security, and cost. Verification results showed: On supply and demand, the absence of nuclear power causes an electricity shortage during peak hours; On environment, no GHG-free power sources but nuclear currently have a sufficient supply capacity; On energy security, nuclear fuel procurement sources are diverse and located in relatively stable areas; On cost, the strong yen and cheap oil favors fossil fuels, and the weak yen and dear oil does nuclear power, though depending on unpredictable elements to send their cost up, typically waste disposal cost incurred in nuclear power, and CO 2 reduction cost in fossil fuels. With all these factors taken into consideration, the best mix of power sources should be figured out. From the verification results, we can conclude that nuclear power is one of irreplaceable energy sources for Japan. To prepare for growing electricity demand and care the environment better, Japan has few choices but to increase the installed capacity of nuclear power generation in the years to come. (author)

  2. Steam Generator control in Nuclear Power Plants by water mass inventory

    Energy Technology Data Exchange (ETDEWEB)

    Dong Wei [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States); Doster, J. Michael [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States)], E-mail: doster@eos.ncsu.edu; Mayo, Charles W. [North Carolina State University, Department of Nuclear Engineering, Box 7909, Raleigh, NC 27695-7909 (United States)

    2008-04-15

    Control of water mass inventory in Nuclear Steam Generators is important to insure sufficient cooling of the nuclear reactor. Since downcomer water level is measurable, and a reasonable indication of water mass inventory near steady-state, conventional feedwater control system designs attempt to maintain downcomer water level within a relatively narrow operational band. However, downcomer water level can temporarily react in a reverse manner to water mass inventory changes, commonly known as shrink and swell effects. These complications are accentuated during start-up or low power conditions. As a result, automatic or manual control of water level is difficult and can lead to high reactor trip rates. This paper introduces a new feedwater control strategy for Nuclear Steam Generators. The new method directly controls water mass inventory instead of downcomer water level, eliminating complications from shrink and swell all together. However, water mass inventory is not measurable, requiring an online estimator to provide a mass inventory signal based on measurable plant parameters. Since the thermal-hydraulic response of a Steam Generator is highly nonlinear, a linear state-observer is not feasible. In addition, difficulties in obtaining flow regime and density information within the Steam Generator make an estimator based on analytical methods impractical at this time. This work employs a water mass estimator based on feedforward neural networks. By properly choosing and training the neural network, mass signals can be obtained which are suitable for stable, closed-loop water mass inventory control. Theoretical analysis and simulation results show that water mass control can significantly improve the operation and safety of Nuclear Steam Generators.

  3. Steam Generator control in Nuclear Power Plants by water mass inventory

    International Nuclear Information System (INIS)

    Dong Wei; Doster, J. Michael; Mayo, Charles W.

    2008-01-01

    Control of water mass inventory in Nuclear Steam Generators is important to insure sufficient cooling of the nuclear reactor. Since downcomer water level is measurable, and a reasonable indication of water mass inventory near steady-state, conventional feedwater control system designs attempt to maintain downcomer water level within a relatively narrow operational band. However, downcomer water level can temporarily react in a reverse manner to water mass inventory changes, commonly known as shrink and swell effects. These complications are accentuated during start-up or low power conditions. As a result, automatic or manual control of water level is difficult and can lead to high reactor trip rates. This paper introduces a new feedwater control strategy for Nuclear Steam Generators. The new method directly controls water mass inventory instead of downcomer water level, eliminating complications from shrink and swell all together. However, water mass inventory is not measurable, requiring an online estimator to provide a mass inventory signal based on measurable plant parameters. Since the thermal-hydraulic response of a Steam Generator is highly nonlinear, a linear state-observer is not feasible. In addition, difficulties in obtaining flow regime and density information within the Steam Generator make an estimator based on analytical methods impractical at this time. This work employs a water mass estimator based on feedforward neural networks. By properly choosing and training the neural network, mass signals can be obtained which are suitable for stable, closed-loop water mass inventory control. Theoretical analysis and simulation results show that water mass control can significantly improve the operation and safety of Nuclear Steam Generators

  4. Socio-economic impacts of nuclear generating stations: summary report on the NRC post-licensing studies

    International Nuclear Information System (INIS)

    Chalmers, J.; Pijawka, D.; Branch, K.; Bergmann, P.; Flynn, J.; Flynn, C.

    1982-07-01

    Information is presented concerning the conceptual framework for the assessment of socioeconomic impacts; methodology for the post-licensing case studies; socioeconomic changes due to the construction and operation of nuclear generating stations; public response to the construction and operation of nuclear generating stations; socioeconomic consequences of the accident at Three Mile Island; the significance of socioeconomic change due to the construction and operation of nuclear generating stations; findings of the post-licensing studies relative to the nuclear station impact literature; and implications of the findings for projective assessments and planning studies

  5. Determination of leveled costs of electric generation for gas plants, coal and nuclear

    International Nuclear Information System (INIS)

    Alonso V, G.; Palacios H, J.C.; Ramirez S, J.R.; Gomez, A.

    2005-01-01

    The present work analyzes the leveled costs of electric generation for different types of nuclear reactors known as Generation III, these costs are compared with the leveled costs of electric generation of plants with the help of natural gas and coal. In the study several discount rates were used to determine their impact in the initial investment. The obtained results are comparable with similar studies and they show that it has more than enough the base of the leveled cost the nuclear option it is quite competitive in Mexico. Also in this study it is also thinks about the economic viability of a new nuclear power station in Mexico. (Author)

  6. Generation of multigroup cross sections from ENDF/B-IV nuclear data library

    International Nuclear Information System (INIS)

    Chapot, J.L.C.; Thome Filho, Z.D.

    1980-04-01

    The generation of nuclear data compacted in energy groups is made. The nuclear data library ENDF/B-IV, Evaluated Nuclear Data File, and the new version of the codes ETOG-3 and ETOT-3 are utilized. The data obtained are compared with data from other sources. (L.F.) [pt

  7. Three Mile Island Nuclear Station steam generator chemical cleaning

    International Nuclear Information System (INIS)

    Hansen, C.A.

    1992-01-01

    The Three Mile Island-1 steam generators were chemically cleaned in 1991 by the B and W Nuclear Service Co. (BWNS). This secondary side cleaning was accomplished through application of the EPRI/SGOG (Electric Power Research Institute - Steam Generator Owners Group) chemical cleaning iron removal process, followed by sludge lancing. BWNS also performed on-line corrosion monitoring. Corrosion of key steam generator materials was low, and well within established limits. Liquid waste, subsequently processed by BWNS was less than expected. 7 tabs

  8. Analysis of corrosion-product transport using nondestructive XRF and MS techniques

    International Nuclear Information System (INIS)

    Sawicka, B.D.; Sawicki, J.A.

    1998-01-01

    This paper describes the application of X-ray fluorescence (XRF) and Moessbauer spectroscopy (MS) techniques to monitor corrosion-product transport (CPT) in water circuits of nuclear reactors. The combination of XRF and MS techniques was applied in studies of CPT crud filters from both primary- and secondary-side water circuits (i.e., radioactive and nonradioactive specimens) of CANDU reactors. The XRF-MS method allows nondestructive analysis of species collected on filters and provides more complete information about corrosion products than commonly used digestive methods of chemical analysis. Recent analyses of CPT specimens from the Darlington Nuclear Generating Station (NGS) primary side and the Bruce B NGS feedwater system are shown as examples. Some characteristics of primary and secondary water circuits are discussed using these new data. (author)

  9. US central station nuclear electric generating units: significant milestones

    International Nuclear Information System (INIS)

    1979-09-01

    Listings of US nuclear power plants include significant dates, reactor type, owners, and net generating capacity. Listings are made by state, region, and utility. Tabulations of status, schedules, and orders are also presented

  10. Nuclear the next generation. 34th Annual Canadian Nuclear Society conference and 37th CNS/CNA student conference

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-01

    The 34th Annual Canadian Nuclear Society Conference and 37th CNS/CNA Student Conference was held in Toronto, Ontario, Canada on June 10-13, 2013. With the theme of the conference, 'Nuclear the Next Generation{sup ,} the conference actively engaged 400 participants in the many facets of this well-rum event. The conference combined excellent plenary speakers, a full set of technical papers, challenging student poster competitions, and interesting exhibits. The plenary session focussed on the themes: 'Nuclear Power - a Business Driver for the Next Generation'; and, 'Designing - the Next Generation'. The technical session titles were: Reactor and Radiation Physics; Environment and Spent Fuel Management; Operations and Maintenance; Fusion Science and Technology; Advanced Reactors and Fuels; Plant Life Extension, Refurbishment and Aging; Safety and Licensing; Chemistry and Materials; and, Thermalhydraulics. The student conference session was well attended and completed the 4 day event.

  11. Knowledge Transfer and Leadership Development in Coordination with Young Generation in Nuclear (YGN) Societies

    International Nuclear Information System (INIS)

    Batra, Chirayu; Janin, Denis

    2017-01-01

    IYNC in a Nutshell: The mission - IYNC (International Youth Nuclear Congress) is the global network of a new generation of nuclear professionals to: •Communicate the benefits of nuclear science and applications •Promote the peaceful use of nuclear power •Provide a platform for networking •Facilitate knowledge transfer between generations and across boundaries; The structure - IYNC is a non-profit organization run by: •11 Officers •Board of Directors •50 National Representatives (e.g. YGN) •20 Members at Large •Dedicated committees and team for projects (30+) → more than 80 volunteers; The activities - •Biannual Congress (IYNCWiN18) •Grants Committee •YGN Startup & Support •Bulletin, Newsletter – sign up www.iync.org •Innovation4Nuclear (I4N) •Nuclear4Climate •Annual Board of Directors. YGN (Young Generation Network): What is a YGN? • A group of young professionals and students interested in nuclear science and technology; Benefits: •Knowledge transfer •Train the future international leaders •Networking •Attracts, develops and retains young professionals

  12. Regional comparison of nuclear and fossil electric power generation costs

    International Nuclear Information System (INIS)

    Bowers, H.I.

    1984-01-01

    Nuclear's main disadvantages are its high capital investment cost and uncertainty in schedule compared with alternatives. Nuclear plant costs continue to rise whereas coal plant investment costs are staying relative steady. Based on average experience, nuclear capital investment costs are nearly double those of coal-fired generation plants. The capital investment cost disadvantage of nuclear is balanced by its fuel cost advantages. New base load nuclear power plants were projected to be competitive with coal-fired plants in most regions of the country. Nuclear power costs wre projected to be significantly less (10% or more) than coal-fired power costs in the South Atlantic region. Coal-fired plants were projected to have a significant economic advantage over nuclear plants in the Central and North Central regions. In the remaining seven regions, the levelized cost of power from either option was projected to be within 10%. Uncertainties in future costs of materials, services, and financing affect the relative economics of the nuclear and coal options significantly. 10 figures

  13. Reducing Risk for the Next Generation Nuclear Plant

    Energy Technology Data Exchange (ETDEWEB)

    John M. Beck II; Harold J. Heydt; Emmanuel O. Opare; Kyle B. Oswald

    2010-07-01

    The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.

  14. Reducing Risk for the Next Generation Nuclear Plant

    International Nuclear Information System (INIS)

    Beck, John M. II; Heydt, Harold J.; Opare, Emmanuel O.; Oswald, Kyle B.

    2010-01-01

    The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.

  15. Relationship between people's awareness of environmental capabilities of saving energy, photovoltaic power generation and nuclear power generation

    International Nuclear Information System (INIS)

    Hashiba, Takashi

    2001-01-01

    In this research, relationship between people's awareness of environmental capabilities of saving energy, photovoltaic power generation (PV) and nuclear power generation was investigated using questionnaire method. The results showed that saving energy is conducted without reference to its environment preservation effect. However the older people tend to regard saving energy as contribution to environment preservation. The attitude toward usage of PV has a close relationship to awareness of energy environmental concerns. Acceptance of cost sharing for the introducing of wide-scale PV systems to society is related to environment protection image of PV and the attitude toward loss of social convenience lost as a result of saving energy activities. The older people become, the more priority people put on environment protection before the social convenience. There is little relationship between environmental capabilities of nuclear power generation, that never discharge CO 2 on generation, and awareness of energy environmental concerns. (author)

  16. Building on our past... building for the future. 33rd Annual Canadian Nuclear Society conference and 36th CNS/CNA student conference

    International Nuclear Information System (INIS)

    2012-01-01

    The 33rd Annual Canadian Nuclear Society Conference and 36th CNS/CNA Student Conference was held in Saskatoon, Saskatchewan, Canada on June 10-13, 2012. With the theme of the conference, 'Building on our Past... Building for the Future', the conference specifically noted the 50th anniversary of the first-nuclear-produced electricity in Canada by the small Nuclear Power Demonstration (NPD) plant on June 4, 1962 and the 60th anniversary of the creation of Atomic Energy of Canada Limited in April 1952. The conference brought together over 360 delegates for the technical sessions with very broad subject matter of: physics, environment and waste management, safety and licensing, life extension, fusion technology, fuel and advanced reactors, reactor materials, uranium mining, I and C process, and, thermalhydraulics. Two plenary sessions focussed on: Small Modular Reactors; and, radioisotopes primarily for medical applications. The student conference was well attended with plenary sessions focussing on: Nuclear Industry Power Developments: The Renaissance; and a panel discussion on the overview of the proposed refurbishment of the Darlington four-unit station.

  17. GC Side Event: Future of Nuclear Energy: Engaging the Young Generation. Presentations

    International Nuclear Information System (INIS)

    2017-01-01

    This event presented the IAEA’s programmes for the education and training of a new generation of nuclear professionals. It also featured the annual European Master of Science in Nuclear Engineering (EMSNE) award ceremony

  18. The nuclear safety regulation in Japan and the response to changes of circumstances surrounding the nuclear electricity generation

    International Nuclear Information System (INIS)

    Hombu, K.; Hirota, M.; Taniguchi, T.; Tanaka, N.; Akimoto, S.

    2001-01-01

    The influences of external factors on nuclear safety are discussed in this paper, based on the views on the circumstances of nuclear electricity generation. The following external factors, which might have some potential impacts on nuclear safety, are selected for discussion: (1) The deregulation in the electricity generation industry; (2) The modification of approval/certification system in the regulation of electricity generation; (3) The influences on social atmosphere due to the occurrence of a series of troubles; (4) The government reform and the structural adjustment of industry and (5) Others. Our further discussion seems to focus on the following 2 issues: (a) Whether nuclear power and the other electrical sources should compete with each other for short term economical cost, or whether factors of cost stability and competitiveness as well as longer term energy supply security and global environmental issues ranging over several decades should be considered; (b) How to realize the appropriate regulation from the perspective of public acceptance and confidence (when a series of troubles occur) without imposing unnecessary burdens on industry and without jeopardizing safety. These issues may be common among many countries and can be widely discussed. (author)

  19. A linear current injection generator for the generation of electrons in a nuclear reactor

    International Nuclear Information System (INIS)

    Kar, Moutushi; Thakur, Satish Kumar; Agiwal, Mamta; Sholapurwala, Zarir H.

    2011-01-01

    While, operating a nuclear reactor it is absolutely necessary for generating a chain reaction or fission. A chain reaction can be initiated by bombardment of a heavy nucleus with fast moving particles. One of the common methods used for generating a fast moving particle is injecting a very high voltage into a particle accelerator and accelerating high energy particle beams using machine like cyclotron, synchrotron, linear accelerators i.e. linac and similar equipment. These equipment generated and run by several high voltage applications like simple high voltage DC systems and supplies or pulsed electron systems. (author)

  20. Current status of nuclear power generation in Japan and directions in water cooled reactor technology development

    International Nuclear Information System (INIS)

    Miwa, T.

    1991-01-01

    Electric power demand aspects and current status of nuclear power generation in Japan are outlined. Although the future plan for nuclear power generation has not been determined yet the Japanese nuclear research centers and institutes are investigating and developing some projects on the next generation of light water reactors and other types of reactors. The paper describes these main activities

  1. Radioactive waste assessment using 'moderate growth in nuclear electricity generation' scenario

    International Nuclear Information System (INIS)

    Richardson, J.A.; Goodill, D.R.; Tymons, B.J.

    1985-05-01

    This report describes an assessment of radioactive waste management arisings from a defined nuclear power generation scenario -Scheme 3. Scheme 3 assumes a moderate growth in nuclear generation scenario with raw waste arisings from 3 main groups: (i) existing and committed commercial reactors; (ii) fuel reprocessing plants; (iii) research, industry and medicine. No decommissioning wastes are considered except for arisings from the final fuel cores from decommissioned reactors. The study uses the SIMULATION2 code which models waste material flows through the system. With a knowledge of the accumulations and average production rates of the raw wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data bases for the inventory calculations and the assumptions concerning future operation of nuclear facilities were those current in 1983. Both the inventory data and plans for the future of existing nuclear installations have been updated since these calculations were completed. Therefore the results from this assessment do not represent the most up-to-date information available. The report does, however, illustrate the methodology of assessment, and indicates the type of information that can be generated. (author)

  2. Adoption of nuclear power generation

    International Nuclear Information System (INIS)

    Sommers, P.

    1980-01-01

    This article develops a model of the innovation-adoption decision. The model allows the economic situation of a utility and its perception of uncertainty associated with an innovation to affect the probability of adopting it. This model is useful when uncertainties affecting decisions about adoption persist throughout the diffusion process, thereby making the usual adoption model implicit in rate-of-diffusion studies inappropriate. An empirical test of the model finds that firm size, power pool size, and selected aspects of uncertainty about the innovation are significant predictors of US utility companies' decisions on whether or not to adopt nuclear power generation. 17 references, 2 tables

  3. International project GT-MHR - New generation of nuclear reactors

    International Nuclear Information System (INIS)

    Vasyaev, A.; Kodochigov, N.; Kuzavkov, N.; Kuznetsov, L.

    2001-01-01

    Gas turbine-modular helium reactor (GT-MHR) is the reactor of new generation, which satisfies the requirements of the progressing large-scale nuclear power engineering. The activities in GT-MHR Project started in 1995. In 1997 the Conceptual Design was developed under four-side Agreement (MINATOM, General Atomics, FRAMATOME, Fuji Electric); it has passed through the internal and international reviews, has been approved and recommended for further development as one of new trends in creation of new generation plants. Starting from 1999, the activities in the development of the Preliminary Design of the plant were deployed under the Agreement between the Government of the United States of America and the Government of the Russian Federation on Scientific and Technical Cooperation in the Management of Plutonium That Has Been Withdrawn From Nuclear Military Programs dated July 24, 1998. The activities are established under the Contract between MINATOM and OKBM Russia, and under the General Agreement between Department of Energy (DOE), USA and OKBM. The GT-MHR Project is included into 'Development Strategy of Russian Nuclear Power in the first Half of the XXI-st Century' providing for 'the participation in an international project on the development and construction of GT-MHR nuclear power plant till year 2010 and 'operation of GT-MHR prototype unit and creation of fuel fabrication facility (within framework of International Project) till year 2030'. (author)

  4. Study on economic potential of nuclear-gas combined cycle power generation in Chinese market

    International Nuclear Information System (INIS)

    Zhou Zhiwei; Bian Zhiqiang; Yang Mengjia

    2004-01-01

    Facing the challenges of separation of electric power plant and grid, and the deregulation of Chinese electricity supplying market in near future, nuclear power plants mainly operated as based load at the present regulated market should look for new operation mode. The economics of electric generation with nuclear-natural gas combined cycle is studied based on current conditions of natural gas and nuclear power plants in China. The results indicate that the technology development of nuclear-natural gas combined cycle for power generation is of potential prospects in Chinese electric market. (authors)

  5. Nuclear Power and Ghana's Future Electricity Generation

    International Nuclear Information System (INIS)

    Ennison, I.; Dzobo, M.

    2011-01-01

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

  6. Least cost analysis of Belarus electricity generation system with focus on nuclear option

    International Nuclear Information System (INIS)

    Mikhalevich, A.; Yakushau, A.

    2004-01-01

    A basic feature of the Belarus electricity system is that about 50% of the installed power capacity is used to produce heat for the central heating supply system. The Republic has one of the most developed districts heating system in Europe. The installation started in 1930, and developed very fast after 1945. Co-generation of electricity and thermal energy in central power plants has played a fundamental role in the local economy. Presently, Belarus electricity generation system includes: Total installed capacities of condensing turbines 3665 MW; Total installed capacities of co-generation turbines 3889 MW. It is expected that in 2020 in accordance with electricity demand forecast peak load demand will be equaled approximately 9500 MW. Taking into account that operation time of 60 % existent co-generation turbine and 70 % of condensing turbine can be extended up to 2020 during the period 2005 - 2020 it is necessity to install about 1500 MW of new co-generation units and about 2000 MW of condensing turbines. To select the least cost scenario for electricity generation system expansion improved computer code WASP-IV for Windows had been used. As far code WASP-IV do not allow finding out optimal solution for electricity generation system with high share of co-generation directly the methodology of application of this program for this case had been developed. Methodology is based on utilization of code WASP-IV for simulation condensing turbines and module BALANCE for modeling co-generation part of the system. The scenarios for the electricity system expansion plan included only conventional technologies. Presently, the works connected with the preparedness for NPP construction in the Republic including site survey for NPP are being carried out. The first stage of siting process according to the IAEA classification has been completed. It was based on a set of criteria answered to A Safety Guide of the IAEA Site Survey for Nuclear Power Plants and requirements to be

  7. The feature of emergency diesel generator relaying protection in Tianwan nuclear power station

    International Nuclear Information System (INIS)

    Jiang Xiaopeng; Shi Yan; Li Cong

    2014-01-01

    This paper mainly introduces the function and feature of emergency diesel generator in nuclear power plant, which plays an important role in nuclear accident. It minutely tells about the feature and configuration of relay protection and discusses the rationality of protection scheme, which shows that it can be completely contented all kinds of operation states. It is an analysis and argument about the principle of relay protection in detail, that would operate correctly when emergency diesel generator be in abnormal operating and serious fault conditions, such as cut off emergency diesel generator in order to avoid more harm to emergency diesel generator. It analyzes how the relay responses quickly and locks up the protection action under perturbations in the external power, so it can avoid unnecessary resection of emergency diesel generator to emergency power supply loss and effect of nuclear safety. It also analyzes the flexible use of protection setting of the protective relay to meet various operating status. It elaborates the particularity of relay protection which is due to the particularity of nuclear safety. It analyses the possibility of relay protection which has to be applied to other equipment and the protection setting that was provided by design institute, and puts forward the author's viewpoints. (authors)

  8. Aiming at the rebirth of the nuclear generation

    International Nuclear Information System (INIS)

    Uematsu, M.M.

    2001-01-01

    The nuclear industries of today have a variety of branches and each industry functions independently, and young professionals need opportunities for communicating among themselves across the different fields of industries, utilities and institutes. We, young professionals, are in the motion of organizing the 'Young Generation Network (YGN) of Japan'. (authors)

  9. A study of wet deposition of atmospheric tritium releases at the Ontario Power Generation, Pickering Nuclear Generating Station

    International Nuclear Information System (INIS)

    Crooks, G.; DeWilde, J.; Yu, L.

    2001-01-01

    The Ontario Power Generation,Pickering Nuclear Generating Station (PNGS) has been investigating deposition of atmospheric releases of tritium on their site. This study has included numerical dispersion modelling studies conducted over the past three years, as well as an ongoing field monitoring study. The following paper will present results of the field monitoring study and make comparisons to the numerical modelling. The results of this study could be of potential use to nuclear stations in quantifying tritium deposition in near field regions where building wake effects dominate pollutant dispersion

  10. Operating performance of LWR nuclear generating units

    International Nuclear Information System (INIS)

    Pia, S.

    1984-01-01

    This work aims at reviewing, on the basis of historical data, the operational problem areas which explain the degree of availability and productivity achieved up to now by nuclear power plants in commercial operation in the world. The operating performance data of nuclear power plants area analysed with respect to plant type, size and other significant reference parameters and they are evaluated also by comparison with fossil generating unit data. Major performance indices data are presented for both nuclear and fossil units type and distribution of outage causes. Unplanned full outages caused by nuclear power plant equipment and components failure are particulary emphasized. The trend for unplanned full outages due to the failure of components shows decreasing numerical values in 1981 with respect to the previous years. But this result should be weighed with the increasing plant unavailability hours needed for maintenance and repair action (chiefly preventive maintenance on critical components). This means that the number and downtime of forced outage must be drastically reduced for economic reasons (production losses and problems associated with the unavailable unit unplanned replacement) as well as for plant safe and reliable operation (sudden unavailability of key components and frequency of transients associated with plant shutdown and routine startup operation)

  11. Draining down of a nuclear steam generating system

    International Nuclear Information System (INIS)

    Jawor, J.C.

    1987-01-01

    The method is described of draining down contained reactor-coolant water from the inverted vertical U-tubes of a vertical-type steam generator in which the upper, inverted U-shaped ends of the tubes are closed and the lower ends thereof are open. The steam generator is part of a nuclear powered steam generating system wherein the reactor coolant water is normally circulated from and back into the reactor via a loop comprising the steam generator and inlet and outlet conduits connected to the lower end of the steam generator. The method comprises continuously introducing a gas which is inert to the system and which is under pressure above atmospheric pressure into at least one of the downwardly facing open ends of each of the U-tubes from below the tube sheet in which the open ends of the U-tubes are mounted adjacent the lower end of the steam generator, while permitting the water to flow out from the open ends of the U-tubes

  12. NNSA Program Develops the Next Generation of Nuclear Security Experts

    Energy Technology Data Exchange (ETDEWEB)

    Brim, Cornelia P.; Disney, Maren V.

    2015-09-02

    NNSA is fostering the next generation of nuclear security experts is through its successful NNSA Graduate Fellowship Program (NGFP). NGFP offers its Fellows an exceptional career development opportunity through hands-on experience supporting NNSA mission areas across policy and technology disciplines. The one-year assignments give tomorrow’s leaders in global nuclear security and nonproliferation unparalleled exposure through assignments to Program Offices across NNSA.

  13. Steam generator for use in nuclear power plants

    International Nuclear Information System (INIS)

    Cella, A.

    1980-01-01

    An improved steam generator is described for use in a nuclear power plant of the pressurized water type in which a turbine generator is driven by the steam output of the steam generator to provide electrical power therefrom. The improvement comprises providing a vertically movable grid structure vertically extending within the interior of the lower housing portion of the steam generator through which individual tubes comprising a vertically extending tube bundle extend. The tube bundle has a tube sheet at one end thereof supporting the tube bundle for the tubes extending through the tube sheet in flow through communication with a heat exchange fluid inlet. The grid structure defines grid apertures therein through which the individual tubes extend with each of the grid apertures being in surrounding relationship with a portion of an associated one of the tubes. The grid structure is movable for a predetermined vertical extent, such as by hydraulic means, such as a piston, along the tubes for vertically displacing the means defining the grid apertures by a sufficient amount for removing the previously surrounded portion of each of the tubes from the associated grid apertures whereby an enhanced reading of the condition of the tubes at the previously surrounded portion is enabled. The steam generator may comprise vertically assemblable modules which are removably mounted together in sealing relationship, with the modules comprising a base module, a tube bundle module removably mountable on the base module in sealing relationship therewith and an uppermost drier module removably mountable on the tube bundle module in sealing relationship therewith whereby ready access to removal of the tube bundle module in situ from the nuclear power plant steam generator is facilitated

  14. Strategic thinking about nuclear energy: implications of the emerging market structure in electric generation

    International Nuclear Information System (INIS)

    Bodde, D.L.

    1998-01-01

    Global environmental concerns provide strong motivation for electric generating technologies that reduce greenhouse gas emissions. By itself however, this incentive is probably not sufficient to reverse the long-term decline in the market share of nuclear energy. This is because the power plants now offered by the nuclear vendors mesh poorly with the needs of competitive generating markets. Where managers of generating companies are held accountable to share owners in a competitive environment, the nuclear power plants now offered in the market for new generating capacity are at a distinct disadvantage. As much of the world moves toward the competitive model, this disadvantage will become increasingly limiting. An alternative nuclear power plant concept and fuel cycle is needed, a radical departure from current practice, designed with the competitive marketplace in mind. To accomplish this, a new kind of institution is required: multinational in scope, oriented toward the market, and able to master the politics of the fuel cycle. (author)

  15. Diagnostic knowledge generation of nuclear power plants using knowledge compilers

    International Nuclear Information System (INIS)

    Yoshikawa, Shinji; Endou, Akira; Ikeda, Mitsuru; Mizoguchi, Riichiro

    1994-01-01

    This paper discusses a method to generate diagnostic knowledge of nuclear power plants, from commonly accepted physical knowledge and design information about plant configuration. This method is based on qualitative reasoning, which is advantageous to numerical information processing in the sense that system can explain why and how directly applicable knowledge is correctly generated, and that knowledge base is highly reusable and expandable because it is independent on detailed numerical design specifications. However, reasoning ambiguity has been found as the largest problem in applying the technique to nuclear power plants. The proposed approach mainly consists of a knowledge representation scheme, reasoning algorithm, and qualitative model construction method. (author). 4 refs, 8 figs, 1 tab

  16. Design Features and Technology Uncertainties for the Next Generation Nuclear Plant

    Energy Technology Data Exchange (ETDEWEB)

    John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

    2004-06-01

    This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

  17. 76 FR 45301 - PSEG Nuclear LLC, Hope Creek Generating Station; Notice of Issuance of Renewed Facility Operating...

    Science.gov (United States)

    2011-07-28

    ... NUCLEAR REGULATORY COMMISSION Docket No. 50-354 [NRC-2009-0391] PSEG Nuclear LLC, Hope Creek... operator of the Hope Creek Generating Station (HCGS). Renewed Facility Operating License No. NPF- 57... Renewal of Nuclear Power Plants, Supplement 45, Regarding Hope Creek Generating Station and Salem Nuclear...

  18. Tritium in groundwater investigation at the Pickering Nuclear Generating Station

    International Nuclear Information System (INIS)

    DeWilde, J.; Yu, L.; Wootton, R.; Belanger, D.; Hansen, K.; McGurk, E.; Teare, A.

    2001-01-01

    Ontario Power Generation Inc. (OPG) investigated tritium in groundwater at the Pickering Nuclear Generating Station (PNGS). The objectives of the study were to evaluate and define the extent of radionuclides, primarily tritium, in groundwater, investigate the causes or sources of contamination, determine impacts on the natural environment, and provide recommendations to prevent future discharges. This paper provides an overview of the investigations conducted in 1999 and 2000 to identity the extent of the tritium beneath the site and the potential sources of tritium released to the groundwater. The investigation and findings are summarized with a focus on unique aspects of the investigation, on lessons learned and benefits. Some of the investigative techniques discussed include process assessments, video inspections, hydrostatic and tracer tests, Helium 3 analysis for tritium age dating, deuterium and tritium in soil analysis. The investigative techniques have widespread applications to other nuclear generating stations. (author)

  19. Quantum information generation, storage and transmission based on nuclear spins

    Science.gov (United States)

    Zaharov, V. V.; Makarov, V. I.

    2018-05-01

    A new approach to quantum information generation, storage and transmission is proposed. It is shown that quantum information generation and storage using an ensemble of N electron spins encounter unresolvable implementation problems (at least at the present time). As an alternative implementation we discuss two promising radical systems, one with N equivalent nuclear spins and another with N nonequivalent nuclear spins. Detailed analysis shows that only the radical system containing N nonequivalent nuclei is perfectly matched for quantum information generation, storage and transmission. We develop a procedure based on pulsed electron paramagnetic resonance (EPR) and we apply it to the radical system with the set of nonequivalent nuclei. The resulting EPR spectrum contains 2N transition lines, where N is the number of the atoms with the nuclear spin 1/2, and each of these lines may be encoded with a determined qudit sequence. For encoding the EPR lines we propose to submit the radical system to two magnetic pulses in the direction perpendicular to the z axis of the reference frame. As a result, the radical system impulse response may be measured, stored and transmitted through the communications channel. Confirming our development, the ab initio analysis of the system with three anion radicals was done showing matching between the simulations and the theoretical predictions. The developed method may be easily adapted for quantum information generation, storage, processing and transmission in quantum computing and quantum communications applications.

  20. 76 FR 1197 - Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of...

    Science.gov (United States)

    2011-01-07

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-528, 50-529, 50-530; NRC-2009-0012] Arizona Public Service Company, Palo Verde Nuclear Generating Station; Notice of Availability of the Final Supplement 43... of operation for the Palo Verde Nuclear Generating Station (PVNGS). Possible alternatives to the...

  1. A leak-before-break strategy for CANDU primary piping systems

    International Nuclear Information System (INIS)

    Aggarwal, M.L.; Kozluk, M.J.; Lin, T.C.; Manning, B.W.; Vijay, D.K.

    1986-01-01

    Recent advances in elastic-plastic fracture mechanics have made it possible to assess the stability of cracks in ductile piping systems. These technological developments have been used by Ontario Hydro as the nucleus of an approach for demonstrating that CANDU primary heat transport piping systems will not break catastrophically; at worst they would leak at a detectable rate. This leak-before-break approach has been taken on the Darlington nuclear generating station as a design stage alternative to the provision of pipe whip restraints on large diameter, primary heat transport system piping. Positive conclusions reached via this approach are considered sufficient to exclude the requirement to provide protective devices, such as pipe whip restraints. In arriving at the proposed leak-before-break approach a review of current and proposed leak-before-break licensing positions of other jurisdictions (particularly those in the United States and the Federal Republic of Germany) was carried out. The approach presented makes use of recent American developments in the area of elastic-plastic fracture mechanics. It also gives consideration to aspects which are unique to the pressurized heavy water (CANDU) reactors used by Ontario Hydro. The proposed leak-before-break approach is described and its use is illustrated by applying it to the Darlington generating station primary heat transport system pump suction piping. (author)

  2. Fluidized bed nuclear reactor as a IV generation reactor

    International Nuclear Information System (INIS)

    Sefidvash, Farhang

    2002-01-01

    The object of this paper is to analyze the characteristics of the Fluidized Bed Nuclear Reactor (FBNR) concept under the light of the requirements set for the IV generation nuclear reactors. It is seen that FBNR generally meets the goals of providing sustainable energy generation that meets clean air objectives and promotes long-term availability of systems and effective fuel utilization for worldwide energy production; minimize and manage their nuclear waste and notably reduce the long term stewardship burden in the future, thereby improving protection for the public health and the environment; increase the assurance that it is a very unattractive and least desirable route for diversion or theft of weapons-usable materials; excel in safety and reliability; have a very low likelihood and degree of reactor core damage; eliminate the need for offsite emergency response; have a clear life-cycle cost advantage over other energy sources; have a level of financial risk comparable to other energy projects. The other advantages of the proposed design are being modular, low environmental impact, exclusion of severe accidents, short construction period, flexible adaptation to demand, excellent load following characteristics, and competitive economics. (author)

  3. Nuclear data evaluation and group constant generation for reactor analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jung Do; Gil, Choong Sup [Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)

    1993-12-01

    In nuclear or shielding design analysis for reactors including nuclear facilities, nuclear data are one of the primary importances. Research project for nuclear data evaluation and their effective applications has been continuously performed. The objectives of this project are (1) to compile the latest evaluated nuclear data files, (2) to establish their processing code systems, and (3) to evaluate the multigroup constant library using the newly compiled data files and the code systems. As the results of this project, JEF-2.2 which is latest version of Joint Evaluated File developed at OECD/NEA was compiled and COMPLOT and EVALPLOT utility codes were installed in personal computer, which are able to draw ENDF/B-formatted nuclear data for comparison and check. Computer system (NJOY/ACER) for generating continuous energy Monte Carlo code MCNP library was established and the system was validated by analyzing a number of experimental data. (Author).

  4. Current Status and Future Outlook of Nuclear Power Generation in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Yasuro; Yoshii, Ryosuke

    2007-07-01

    For Japan, a country poor in natural resources, in light of the tough energy situation in recent times, a National Energy Strategy with energy security at its core was established in May 2006. The key point of the Strategy is nuclear power generation, and the aim is to ensure that nuclear power generation continues to account for 30 to 40 percent or more of total electricity generated even after 2030. The first step to achieving this goal is to make maximum use of existing plants (55 plants, 49580MWe), and the aim is to achieve a 60-year service life by making improvements to plant operation and maintenance, such as extending current monitoring and maintenance of plant condition, and the implementation of plant aging management. In Japan, plant construction has been continuous since the 1970s. The current new plant construction plan (13 plants, 17230MWe) is to be achieved with a concerted, cohesive national effort. In addition, in order to complete the nuclear fuel cycle, a reprocessing plant is being constructed strictly for peaceful use, and construction of a site for disposing of high-level radioactive waste is also proceeding. Development of the next generation light water reactors and fast breeder reactor cycle is also underway. (auth)

  5. Public attitudes toward nuclear power generation. Focusing on measurement of attitude intensity

    International Nuclear Information System (INIS)

    Nagai, Yasuko; Hayashi, Chikio

    1999-01-01

    The purpose of the present study was to 1) examine the differences of the perception between nuclear power generation (NPG) and electric power generation by nuclear fusion, 2) find the structural characteristics of the attitude toward NPG, 3) shed light on the characteristics of knowledge about NPG, and 4) develop a scale to measure the intensity in attitude toward NPG. Subjects (N = 1,582) were randomly assigned into 4 groups and were asked to answer a questionnaire including public attitudes toward NPG and related matters. The results were as follows: 1) the perception of electric power generation by nuclear fusion was less favorable than that of NPG; 2) Items which correlated with attitudes toward NPG were: 'sense of anxiety,' sensitivity to risk,' 'trust in science and technology,' 'evaluation of Japan's nuclear policy', 'evaluation of electric power companies,' and interest in life and environmental issues.' Moreover, people with a strong attitude tended to be rational and had a better knowledge of NPG; 3) The evaluation of the amount of subjective knowledge concerning nuclear power and electric power generation was reliable as a measure of objective knowledge; 4) The measurement method used in this study was characterized by the use of biased questions(ten positively and ten negatively biased questions) which were shown to the subjects using the split-half method. An attempt was made to measure the attitude and its intensity taking into consideration gender, positive or negative attitude toward NPG, level of knowledge about NPG, age, and occupation. As a result, differences in intensity between different attributes were found. (author)

  6. Nuclear power generation and nuclear nonproliferation

    International Nuclear Information System (INIS)

    Walske, C.

    1978-01-01

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

  7. Emergency makeup of nuclear steam generators in blackout conditions

    International Nuclear Information System (INIS)

    Korolev, A.V.; Derevyanko, O.V.

    2014-01-01

    The paper describes an original solution for using steam energy to organize makeup of NPP steam generators in blackout conditions. The proposed solution combines a disk friction turbine and an axial turbine in a single housing to provide a high overall technical effect enabling the replenishment of nuclear steam generators with steam using the pump turbine drive assembly. The application of the design is analyzed and its efficiency and feasibility are shown

  8. Ultrasonic Cleaning of Nuclear Steam Generator by Micro Bubble

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Woo Tae [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of); Kim, Sang Tae; Yoon, Sang Jung [Sae-An Engineering Co., Seoul (Korea, Republic of)

    2012-05-15

    In this paper, we present ultrasonic cleaning technology for a nuclear steam generator using micro bubble. We could extend the boundary of ultrasonic cleaning by using micro bubbles in water. Ultrasonic energy measured was increased about 5 times after the generation of micro bubbles in water. Furthermore, ultrasound energy was measured to be strong enough to create cavitation even though the ultrasound sensor was about 2 meters away from the ultrasonic transducer

  9. Method and system of nuclear energy generation

    International Nuclear Information System (INIS)

    Wilke, W.

    1975-01-01

    The method is based on the nuclear reaction Li 6 (n,α)H 3 . Thermal neutrons, whose generation require a power reactor, are fed to a lithium deuterite target in such a manner that part of the tritons produced in this reaction undergo nuclear fusion of the kind d(T,n)α with the deuterons of the target. The remaining tritons are reacted with additional deuterons. The tritium produced in this reaction is processed and fed back to the lithium target over a triton source. It is also possible to process the tritium to a target, feed deuterons to it, and in addition to give the neutrons produced from the T(d,n)α reaction after slowing down to thermal energy to the lithium target. (DG/LH) [de

  10. Management of radioactive waste generated in nuclear medicine; Gestion de los residuos radiactivos generados en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Lorenz Perez, P.

    2015-07-01

    Nuclear medicine is a clinical specialty in which radioactive material is used in non-encapsulated form, for the diagnosis and treatment of patients. Nuclear medicine involves administering to a patient a radioactive substance, usually liquid, both diagnostic and therapeutic purposes. This process generates solid radioactive waste (syringes, vials, gloves) and liquid (mainly the patient's urine). (Author)

  11. A comparative study of health hazards and environmental impacts for electricity generation through nuclear energy hidroelectricity and coal fired thermoeletrical generation

    International Nuclear Information System (INIS)

    Guimaraes, C.A.

    1982-01-01

    Environmental impacts and health hazards were comparatively assessed in regard to electricity generation via nuclear energy, hidraulic dams and coal firing. The main aspects covered the nuclear reactor and its associated nuclear fuel cycle, coal fired thermoelectrical power plant its associated coal industry, and hidroelectrical power plant and its dam. Besides specific comparisons of impacts in the air, water, soil and health hazards an evaluation for the Brazilian case was made based on a forecast of electricity demand up to the year 2020. For the nuclear option the consequences were analysed based on American data since no data is yet available for Brazil. Coal firing option was also analised for based heavily on American data due to small Brazilian experience in this sector of energy generation. For hydroelectrical option Brazilian data were used mostly from CESP for comparative purposes. These alternatives for generation of electricity considered in this study are the most relevant for the next four decades for Brazil. (Author) [pt

  12. Environmental and other considerations in development of new nuclear power generation

    International Nuclear Information System (INIS)

    Wan, P.K.

    2005-01-01

    Power generation is well recognized as a major prerequisite for a country's economic development. When developing a new nuclear power project, major environmental issues range from understanding of the environmental regulations of the country where the project is going to be built and the policies of the financial institution(s) involved, to dealing with the logistical issues associated with the acquisition of in country consultants, and language and cultural differences in producing the required environmental documents. One of the important pre-construction environmental efforts for nuclear power project is preparation of an Environmental Impact Assessment (EIA). An EIA is typically required to be performed for both the host country and the financial institutions engaged. The primary issues addressed in the EIA prepared for the country and that prepared for the bank are not necessarily the same, nor are the level of analyses likely to be conducted for a given environmental topic. The consequences for the development of a nuclear power project can be far-reaching, since the proposed project has the potential to cause significant socioeconomic impacts on local population and government, if it is not properly sited and/or designed. Thus, many of the financial institutions (such as the World Bank) require environmental and social-economic impact assessments as pre-requisite for funding approval. In addition, sustainable development objectives must be identified and fulfilled to alleviate the risks associated with project go-ahead decision. This paper addresses environmental and other considerations in development of nuclear power generation systems under an electric power industry privatization environment. Case studies of recent permitting activities for new nuclear power generation projects in the United States and funding issues for a nuclear power plant recently built in China are also discussed. (authors)

  13. Water level control for a nuclear steam generator

    International Nuclear Information System (INIS)

    Wen Tan

    2011-01-01

    Research highlights: → A water level control system for a nuclear steam generator (SG) is proposed. → The parameters of the control system are directly related to those of the plant model thus scheduling is easy to implement in practice. → The proposed gain-scheduled controller can achieve good performance at both low and high power levels. - Abstract: A water level control system for a nuclear steam generator (SG) is proposed. The control system consists of a feedback controller and a feedforward controller. The feedback controller is of first order, the feedforward controller is of second order, and parameters of the two controllers are directly related to the parameters of plant model thus scheduling is easy to implement in practice. Robustness and performance of the feedback and the feedforward controllers are analyzed in details and tuning of the two parameters of the controllers are discussed. Comparisons among a single robust controller, a multi-model controller and a gain-scheduled controller are studied. It is shown that the proposed gain-scheduled controller can achieve good performance at both low and high power levels.

  14. Generation Mix Study Focusing on Nuclear Power by Practical Peak Forecast

    International Nuclear Information System (INIS)

    Shin, Jung Ho; Roh, Myung Sub

    2013-01-01

    The excessive underestimation can lead to a range of problem; expansion of LNG plant requiring short construction period, the following increase of electricity price, low reserve margin and inefficient configuration of power source. With regard to nuclear power, the share of the stable and economic base load plant, nuclear power, can reduce under the optimum level. Amongst varied factors which contribute to the underestimate, immoderate target for demand side management (DSM) including double deduction of the constraint amount by DSM from peak demand forecast is one of the causes. The hypothesis in this study is that the better optimum generation mix including the adequate share of nuclear power can be obtained under the condition of the peak demand forecast without deduction of DSM target because this forecast is closer to the actual peak demand. In this study, the hypothesis is verified with comparison between peak demand forecast before (or after) DSM target application and the actual peak demand in the 3 rd through 5 th BPE from 2006 to 2010. Furthermore, this research compares and analyzes several generation mix in 2027 focusing on the nuclear power by a few conditions using the WASP-IV program on the basis of the 6 th BPE in 2013. According to the comparative analysis on the peak demand forecast and actual peak demand from 2006 to 2010, the peak demand forecasts without the deduction of the DSM target is closer to the actual peak demand than the peak demand forecasts considering the DSM target in the 3 th , 4 th , 5 th entirely. In addition, the generation mix until 2027 is examined by the WASP-IV. As a result of the program run, when considering the peak demand forecast without DSM reflection, since the base load plants including nuclear power take up adequate proportion, stable and economic supply of electricity can be achieved. On the contrary, in case of planning based on the peak demand forecast with DSM reflected and then compensating the shortage by

  15. Qualifying commercial grade instruments for use in nuclear power generating stations

    International Nuclear Information System (INIS)

    Lamothe, R.J.; Scally, C.R.

    1983-01-01

    Nuclear environmental qualification of instrumentation has been successfully accomplished by many commercial grade equipment manufacturers. This paper was prepared as a guide to those manufacturers who want some insight into a qualification program. The areas addressed are the regulations and documents, the qualification program, and a case history of a chart recorder qualifications. The principal standards relating to a nuclear qualification program are IEEE Std. 323-1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 344-1975 IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations and 10CFR50.49. Previously NUREG 0588 Interim Staff Position on Environmental Qualification of Safety-Related Equipment. These define the intent and purpose of the qualification. The qualification program itself consists of several distinct parts which require explanation, including the determination of qualified life, choice of test samples, selection of appropriate acceptance criteria, aging program, radiation testing, seismic testing, abnormal environment tests and others. The case history illustrates the qualification program and the thought processes involved

  16. An experimental study on the effect of TV commercials on the attitudes towards nuclear power generation

    International Nuclear Information System (INIS)

    Tada, Yasuyuki

    1999-01-01

    The present study is about the effect TV commercials have on the subjects' attitudes towards nuclear power generation. A number of 191 female students participated in the experiment. It was hypothesized that TV commercials would have a positive effect on the viewer's attitude towards nuclear power generation. The main results of the study supported this hypothesis, demonstrating that TV commercials constitute an effective means for changing people's perception of nuclear power generation. (author)

  17. Pressurized-water coolant nuclear reactor steam generator

    International Nuclear Information System (INIS)

    Mayer, H.; Schroder, H.J.

    1975-01-01

    A description is given of a pressurized-water coolant nuclear reactor steam generator having a vertical housing for the steam generating water and containing an upstanding heat exchanger to which the pressurized-water coolant passes and which is radially surrounded by a guide jacket supporting a water separator on its top. By thermosiphon action the steam generating water flows upward through and around the heat exchanger within the guide chamber to the latter's top from which it flows radially outwardly and downwardly through a down draft space formed between the outside of the jacket and the housing. The water separator discharges separated water downwardly. The housing has a feedwater inlet opening adjacent to the lower portion of the heat exchanger, providing preheating of the introduced feedwater. This preheated feedwater is conveyed by a duct upwardly to a location where it mixes with the water discharged from the water separator

  18. Generic test procedure for the qualification of a nuclear emergency generator

    International Nuclear Information System (INIS)

    Simonis, J.C.; Bowman, S.W.

    1985-01-01

    This paper describes the proposed analytical and experimental procedures for the qualification of the standby generators and exciters used in the Emergency Diesel Generator Systems in a nuclear power plant. The components which require qualification are identified through a failure mode analysis of the systems conducted using engineering drawings updated to include all field changes. The qualification of each component includes the margins given in IEEE Std. 323-1974, ''Qualifying Class 1E Equipment for Nuclear Power Generating Stations.'' These margins are combined with the plant specific data to define an enveloping set of environmental parameters. This set of enveloping parameters, plus margin, form the bases for the analysis or test qualification tasks. Proposed qualification of the composite electrical insulation systems used in the generator and exciter on the form or random wound coils is by traceable testing. However, before testing the thermal and radiation degradation data used in the design of the generator and exciter are evaluated to identify if these data are sufficiently traceable to eliminate the need for additional insulation tests. The required tests are guided by applicable standards

  19. Artificial earthquake generation for nuclear power plant design

    International Nuclear Information System (INIS)

    King, A.C.Y.; Chen, C.

    1977-01-01

    The time history method has been one of the analytical tools applied in the seismic resistant design of nuclear power plants. The time histories used are required to be consistent with the specified design Spectra. Since the spectra of recorded strong motion earthquake or conventionally generated artificial time history have local peaks and valleys, iteration procedures must be applied to generate the artificial time history with desired spectra. The paper describes a detailed method for generating a time history which is consistent with a specified design spectra. There are several advantages of this method described herein. First of all, frequency content of the time history is well under control. Secondly, if one wishes to generate the three components of an earthquake at one site, the inherent nature of this method will make the correlations among these three components to simulate closely the actual recorded time histories. Thirdly, a single time history can be generated to match a spectra for different damping values. (auth.)

  20. Scaling back French nuclear generation poses risk to trade deficit

    International Nuclear Information System (INIS)

    Mavroleon, Beatrice

    2013-01-01

    Increasing electricity costs weigh on the performance of France's exports, and this should lead to 'prudence' regarding the rate at which France's nuclear plants are taken out of service, says a report from the council of economic analysis (CAE), an economic think tank that advises the French prime minister. Reducing the proportion of nuclear energy in the country's generation mix was part of French president Francois Hollande's agreement with the country's green parties during his election campaign and is one of the key issues being discussed in France's energy transition debate. The government has said that nuclear energy's share in the generation mix should be reduced from 75% to 50% by 2025. The only nuclear plant the government has committed to closing is France's oldest, the 1.8 GW Fessenheim plant. It is scheduled to close at the end of 2016, but the move has generated much debate. 'Nobody knows why Fessenheim should be closed. Because it is old? So what?' said a legal source close to the French energy market who asked to remain anonymous. 'It's a shame that the French energy transition debate is not dealing with fundamental questions. It's too political', said the source. Low electricity prices are a key factor in maintaining France's economic competitiveness in relation to other European countries, said the CAE report, which was published on 16 May. A 10% increase in power prices paid by industrial consumers would lead to a 1.9% average reduction in the value of France's exports, it said. The market share of France's exports fell 19% in 2005-10, one of the largest slumps in Europe, according to a report published last summer by the European Commission. The country's current account recorded a growing deficit from 2005 onwards, reaching -2.2% in 2011, with the trade balance for goods accounting for most of this deterioration, said the report. Although France's trade deficit improved in 2012, driven by aerospace sector sales and weak domestic demand, the

  1. Valve maintainability in CANDU-PHW nuclear generating stations

    International Nuclear Information System (INIS)

    Pothier, N.E.; Crago, W.A.

    1977-09-01

    Design, application, layout and administrative factors which affect valve maintainability in CANDU-PHW power reactors are identified and discussed. Some of these are illustrated by examples based on prototype reactor operation experience. Valve maintainability improvements resulting from laboratory development and maintainability analysis, have been incorporated in commercial CANDU-PHW nuclear generating stations. These, also, are discussed and illustrated. (author)

  2. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

    Energy Technology Data Exchange (ETDEWEB)

    BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

    2003-06-01

    OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from

  3. A study of the public opinion concerning nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Oiso, Shinichi

    2008-01-01

    In this study, I surveyed the outcome of opinion poll about people's attitude toward nuclear power and analysed their awareness of nuclear power generation in the United States. As a result, it was found that percentage of the people who have positive attitude toward nuclear power has been over 60% since 1998. This result corresponds to the fact that people's preference is tending more toward nuclear power generation which is called the nuclear power Renaissance in the United States. Furthermore, analysis of the outcome of the opinion poll in power stations site region was also conducted and it was found that attitude of the people in the site region was more positive than that of average level in the United States. (author)

  4. 76 FR 24064 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice...

    Science.gov (United States)

    2011-04-29

    ... Service Company, Palo Verde Nuclear Generating Station, Units 1, 2, and 3, Notice of Issuance of Renewed... Company (licensee), the operator of the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (PVNGS... Plants: Supplement 43, Regarding Palo Verde Nuclear Generating Station,'' issued January 2011, discusses...

  5. Nuclear systems of the future: international forum generation 4 and research and development projects at the Cea

    International Nuclear Information System (INIS)

    Carre, F.

    2003-01-01

    To advance nuclear energy to meet future energy needs, ten countries have agreed to develop a future generation of nuclear energy systems, known as Generation 4. A technology road map to guide the Generation 4 effort was begun. This document presents the goals for these nuclear systems and the research programs of the Cea on the gas technology, GT-MHR, VHTR and GFR and the other systems as sodium Fast Neutron reactors, supercritical water and space nuclear. (A.L.B.)

  6. Generation IV Nuclear Energy Systems Ten-Year Program Plan Fiscal Year 2005, Volume 1

    International Nuclear Information System (INIS)

    None

    2005-01-01

    As reflected in the U.S. ''National Energy Policy'', nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S. energy portfolio, but also in the world's future energy portfolio. Accordingly, on September 20, 2002, U.S. Energy Secretary Spencer Abraham announced that, ''The United States and nine other countries have agreed to develop six Generation IV nuclear energy concepts''. The Secretary also noted that the systems are expected to ''represent significant advances in economics, safety, reliability, proliferation resistance, and waste minimization''. The six systems and their broad, worldwide research and development (R and D) needs are described in ''A Technology Roadmap for Generation IV Nuclear Energy Systems'' (hereafter referred to as the Generation IV Roadmap). The first 10 years of required U.S. R and D contributions to achieve the goals described in the Generation IV Roadmap are outlined in this Program Plan

  7. An experimental study on the effect of TV commercials on the attitudes towards nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Tada, Yasuyuki [Institute of Nuclear Safety System Inc., Seika, Kyoto (Japan)

    1999-09-01

    The present study is about the effect TV commercials have on the subjects' attitudes towards nuclear power generation. A number of 191 female students participated in the experiment. It was hypothesized that TV commercials would have a positive effect on the viewer's attitude towards nuclear power generation. The main results of the study supported this hypothesis, demonstrating that TV commercials constitute an effective means for changing people's perception of nuclear power generation. (author)

  8. Nuclear-fuel-cycle facility deployment and price generation

    International Nuclear Information System (INIS)

    Andress, D.A.

    1981-04-01

    The enrichment process and how it is to be modeled in the International Nuclear Model (INM) is described. The details of enrichment production, planning, unit price generation, demand estimation and ordering are examined. The enrichment process from both the producer's and the utility's point of view is analyzed. The enrichment separative-work-unit (SWU) contracts are also discussed. The relationship of the enrichment process with other sectors of the nuclear fuel cycle, expecially uranium mining and milling is considered. There are portions of the enrichment process that are not completely understood at the present time. These areas, which require further study, will be pinpointed in the following discussion. In many cases, e.g., the advent of SMU brokerage activities, the answers will emerge only in time. In other cases, e.g., political trends, uncertainties will always remain. It is possible to cast the uncertainties in a probabilistic framework, but this is beyond the scope of this report. INM, a comprehensive model of the international nuclear industry, simulates the market decision process based on current and future price expectations under a broad range of scenario specifications. INM determines the proper reactor mix as well as the planning, operation, and unit price generation of the attendant nuclear fuel cycle facilities. The level of detail of many of the enrichment activities presented in this report, e.g., the enrichment contracts, is too fine to be incorporated into INM. Nevertheless, they are presented in a form that is ammendable to modeling. The reasons for this are two-fold. First, it shows the level of complexity that would be required to model the entire system. Second, it presents the structural framework for a detailed, stand-alone enrichment model

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

    International Nuclear Information System (INIS)

    Nakamura, Shinsuke; Nogami, Hitoshi.

    1992-01-01

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

  10. Comparison of costs of electricity generation based on nuclear energy and pit coal

    International Nuclear Information System (INIS)

    1981-01-01

    Despite of a meanwhile considerable increase in costs of installation, especially of nuclear power stations, the differences in costs have increased in favour of nuclear electricity generation. The cost advantages are estimated 4 German Pfennig per kilowatt-hour in the base-load field for plants coming into operation at the end of this decade compared with the most profitable variant of pit coal utilization on which this investigation is based; compared to the use of German hard coal, assuming a relatively optimistic development of prices for domestic hard coal in the future, the cost advantage is estimated 8 German Pfennig per kilowatt-hour. The main reason is that in the past years the price for German hard coal as well as for imported coal considerably rose and for the future further increases have to be expected whereas the largest share of the costs of nuclear electricity generation doesn't increase, after the plant is completed. Considering the importance of the fuel costs within the total costs of electricity generation in coal power stations this must have its effects on the total result. These results also prove to be valid for a variation of important cost parameters. Only if the unlikely assumption that considerable variations of influences on costs - each unfavourable effecting nuclear electricity generation - would come together would prove to be true the economic efficiency of nuclear energy would be reduced or questioned. (UA) [de

  11. Evaluating nuclear power as the next baseload generation option

    International Nuclear Information System (INIS)

    Jackson, K.J.; Sanford, M.O.

    1992-01-01

    Numerous factors must be taken into account when planning to meet baseload generating needs of the next century. Examining nuclear power as an option to meet these needs offers significant challenges with respect to evaluating and managing the business risks. This paper describes one mechanism to accomplish this while continuing to participate in industry activities targeted at advancing the nuclear option. One possible model of pursuing high-risk, long-term projects, like nuclear power, is to spread these risks among the project participants and for each organization to commit slowly. With this model of progressive engagement, participants may invest in early information gathering with the objective of uncertainty reduction at preliminary stages in the project, before large investments must be made. For nuclear power, a partnership between a utility (or utility group) and a supplier team may well be the best means of implementing such a model. A partnership also provides opportunity to develop the long-term relationships within the industry which are imperative

  12. 75 FR 52045 - Arizona Public Service Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental...

    Science.gov (United States)

    2010-08-24

    ... Company, Palo Verde Nuclear Generating Station, Unit 3; Environmental Assessment and Finding of No.... NPF-74, issued to Arizona Public Service Company (APS, the licensee), for operation of Palo Verde... Statement for the Palo Verde Nuclear Generating Station, NUREG-0841, dated February 1982. Agencies and...

  13. Informing the next nuclear generation - how does the Ginna plant branch do it?

    International Nuclear Information System (INIS)

    Saavedra, A.

    1995-01-01

    Most of us are familiar with the latest advertising phrase, ''Our children are our future.'' This phrase has been used in so many instances - from concerns about waste, Social Security, and the federal deficit to drug abuse and violence. One more area can be added to the list and advertised nuclear power. Since the establishment of the Ginna plant branch (GPB) in 1992, our target audience has been the next nuclear generation (our children), but our vehicle for dissemination has been the current generation (the adults). Have you ever thought about how often your opinions affect the children you come in contact with? One of GPB's goals is to provide as much information as possible to teachers, neighbors, and civic organizations of our community so that there is a nuclear future that can be carried on by the next generation

  14. Nuclear information and knowledge. News from the INIS and Nuclear Knowledge Management Section. No. 4, September 2007

    International Nuclear Information System (INIS)

    Dyck, E.

    2007-09-01

    This bi-annual newsletter reports about the activities of the INIS and Nuclear Knowledge Management Section of the IAEA Department of Nuclear Energy. Issue no. 4 focuses on work of the Section in IAEA Member States. Strengthening relationships with Member States is exemplified in articles on visits of the Section Head, Mr. R. Workman, to Canada, China and India during spring and summer 2007. Key articles also cover the International Conference on Knowledge Management in Nuclear facilities, held at the IAEA on 18-21 June 2007, in particular the findings and recommendations from four conference sessions (Session 1: Knowledge Management (KM) for Safety and Regulations; Session 2: KM for Improved Performance and Economics; Session 3: KM for Innovation; and Session 4: Human Resources, Education, Training and Public Information) and an interview with the Chair of the conference, Mr. D.F. Torgerson, Senior Vice President and Chief Technology Officer at Atomic Energy of Canada Limited (AECL). Articles report on Nuclear Knowledge Management missions ('Assist Visits'), which constitute a direct service for IAEA Member States, that were undertaken to the Ignalina nuclear power plant, Lithuania, and two Canadian nuclear generating stations, i.e. Ontario Power Generation (OPG) Darlington and Bruce Power L.P. in 2007. Applying nuclear knowledge management (NKM) guidance in IAEA Member States is another example of work on site, and the newsletter reports about regional workshops in Karlsruhe, Germany, Obninsk, Russian Federation, and Tokyo, Japan. Guidance publications in NKM that have been developed through several technical meetings held at the IAEA will result in the following forthcoming publications: Nuclear Knowledge Management Objectives; Knowledge Management for Radioactive Waste Management; and Developing Portals for Nuclear Power Plants. The newsletter also reports about the Technical Meeting on the Development of New Nuclear Information Resources and their Integration

  15. Nuclear Energy Cost Data Base: A reference data base for nuclear and coal-fired powerplant power generation cost analysis

    International Nuclear Information System (INIS)

    Delene, J.G.; Bowers, H.I.

    1986-12-01

    A reference data base and standard methodology are needed for performing comparative nuclear and fossil power generation cost analyses for the Department of Energy, Office of Nuclear Energy. This report contains such a methodology together with reference assumptions and data to be used with the methodology. It is intended to provide basic guidelines or a starting point for analyses and to serve as a focal point in establishing parameters and methods to be used in economic comparisons of nuclear systems with alternatives. The data base is applicable for economic comparisons of new base load light-water reactors on either the current once-through cycle or self-generated recycle, high- and low-sulfur coal-fired plants, and oil- and natural gas-fired electric generating plants coming on line around the turn of the century. In additions to light-water reactors and fossil fuel-fired plants, preliminary cost information is also presented on liquid metal reactor plants. This report includes a data base containing proposed technical and economic assumptions to be used in analyses, discussions of recommended methodology to be used in calculating power generation costs, and a sample calculation for illustrative benchmark purposes

  16. Nuclear Energy Cost Data Base: a reference data base for nuclear and coal-fired powerplant power generation cost analysis

    International Nuclear Information System (INIS)

    1985-06-01

    A reference data base and standard methodology are needed for performing comparative nuclear and fossil power generation cost analyses for the Department of Energy, Office of Nuclear Energy. This report contains such a methodology together with reference assumptions and data to be used with the methodology. It is intended to provide basic guidelines or a starting point for analyses and to serve as a focal point in establishing parameters and methods to be used in economic comparisons of nuclear systems with alternatives. The data base is applicable for economic comparisons of new base load light-water reactors on either the current once-through cycle or self-generated recycle, high- and low-sulfur coal-fired plants, and oil- and natural gas-fired electric generating plants coming on line in the last decade of this century. In addition to light-water reactors and fossil fuel-fired plants, preliminary cost information is also presented on liquid metal reactor plants. This report includes a data base containing proposed technical and economic assumptions to be used in analyses, discussions of a recommended methodology to be used in calculating power generation costs, and a sample calculation for illustrative and benchmark purposes

  17. The paperclip and the nuclear generating station

    International Nuclear Information System (INIS)

    Mussard, J.A.

    1981-01-01

    The article presents some reflections upon the circumstances of the recent rejection by the Swiss Federal Government of a project for building a nuclear generating plant at Kaiseraugst. The following points are made: The use of conventional publicity and public relations techniques to try to convince the public of the desirability or at least of the harmlessness of such projects may very well be counter-productive, given the public's not altogether ill-founded suspicion of such types of pressure. Nor is it helpful to accuse opponents of nuclear developments of indulging in emotional reaction, emotion being entirely legitimate. The proponents of such schemes should confine themselves to objective discussion of the questions Where How Why and At what cost (cost being interpreted in the widest, not merely financial, sense). They should avoid the trap of appearing to be for (as distinct from against) nuclear energy. Finally both sides should abjure (and so far as possible the community should outlaw) methods of conducting disputes that border on lying, charlatanism, demagogy and above all, illegality, and confine themselves to serious discussion of the questions that arise, which are far from being confined to technology and economics. (C.J.O.G.)

  18. Requirements for the next generation of nuclear databases and services

    Energy Technology Data Exchange (ETDEWEB)

    Pronyaev, Vladimir; Zerkin, Viktor; Muir, Douglas [International Atomic Energy Agency, Nuclear Data Section, Vienna (Austria); Winchell, David; Arcilla, Ramon [Brookhaven National Laboratory, National Nuclear Data Center, Upton, NY (United States)

    2002-08-01

    The use of relational database technology and general requirements for the next generation of nuclear databases and services are discussed. These requirements take into account an increased number of co-operating data centres working on diverse hardware and software platforms and users with different data-access capabilities. It is argued that the introduction of programming standards will allow the development of nuclear databases and data retrieval tools in a heterogeneous hardware and software environment. The functionality of this approach was tested with full-scale nuclear databases installed on different platforms having different operating and database management systems. User access through local network, internet, or CD-ROM has been investigated. (author)

  19. Power systems with nuclear-electric generators - Modelling methods

    International Nuclear Information System (INIS)

    Valeca, Serban Constantin

    2002-01-01

    This is a vast analysis on the issue of sustainable nuclear power development with direct conclusions regarding the Nuclear Programme of Romania. The work is targeting specialists and decision making boards. Specific to the nuclear power development is its public implication, the public being most often misinformed by non-professional media. The following problems are debated thoroughly: - safety, nuclear risk, respectively, is treated in chapter 1 and 7 aiming at highlighting the quality of nuclear power and consequently paving the way to public acceptance; - the environment considered both as resource of raw materials and medium essential for life continuation, which should be appropriately protected to ensure healthy and sustainable development of human society; its analysis is also presented in chapter 1 and 7, where the problem of safe management of radioactive waste is addressed too; - investigation methods based on information science of nuclear systems, applied in carrying out the nuclear strategy and planning are widely analyzed in the chapter 2, 3 and 6; - optimizing the processes by following up the structure of investment and operation costs, and, generally, the management of nuclear units is treated in the chapter 5 and 7; - nuclear weapon proliferation as a possible consequence of nuclear power generation is treated as a legal issue. The development of Romanian NPP at Cernavoda, practically, the core of the National Nuclear Programme, is described in chapter 8. Actually, the originality of the present work consists in the selection and adaptation from a multitude of mathematical models applicable to the local and specific conditions of nuclear power plant at Cernavoda. The Romanian economy development and power development oriented towards reduction of fossil fuel consumption and protection of environment, most reliably ensured by the nuclear power, is discussed in the frame of the world trends of the energy production. Various scenarios are

  20. Thermo hydrodynamical analyses of steam generator of nuclear power plant

    International Nuclear Information System (INIS)

    Petelin, S.; Gregoric, M.

    1984-01-01

    SMUP computer code for stationary model of a U-tube steam generator of a PWR nuclear power plant was developed. feed water flow can enter through main and auxiliary path. The computer code is based on the one dimensional mathematical model. Among the results that give an insight into physical processes along the tubes of steam generator are distribution of temperatures, water qualities, heat transfer rates. Parametric analysis permits conclusion on advantage of each design solution regarding heat transfer effects and safety of steam generator. (author)

  1. Cogeneration using a nuclear reactor to generate process heat

    International Nuclear Information System (INIS)

    Alonso, Gustavo; Ramirez, Ramon

    2009-01-01

    Some of the new nuclear reactor technologies (Generation III+) are claiming the production of process heat as an additional value to electricity generation. These technologies are still under development and none of them has shown how this can be possible and what will be the penalty in electricity generation to have this additional product. The current study assess the likeliness of generate process heat from a Pebble Bed Modular Reactor to be used for a refinery showing different plant balance and alternatives to produce and use that process heat. An actual practical example is presented to demonstrate the cogeneration viability using the fact that the PBMR is a modular small reactor and also the challenges that this option has. (author)

  2. Effects of the criticality accident at Tokai-mura on the public's attitude to nuclear power generation

    International Nuclear Information System (INIS)

    Kitada, Atsuko; Hayashi, Chikio

    2000-01-01

    The objective of our study was to clarify the effects on the public's attitude of nuclear power and the criticality accident that occurred at the JCO plant in Tokai-mura, Ibaraki Prefecture. For this purpose, we conducted an awareness survey in the Kansai and Kanto areas two months after the accident. Analysis was made on the basis of the comparison of the survey results with the data that the Institute of Nuclear Safety System had accumulated through continuous awareness surveys on nuclear power generation (regular surveys) since 1993. The public's reactions were twofold. On one hand, there were emotional reactions about accidents in nuclear facilities and a reduction in the sense of security. On the other hand, there were reactions concerning the image of nuclear power plant workers and demand on electricity utilities for enhanced employee education and training. The latter reactions correspond to the problems pointed out after the JCO accident. Regarding the utilization of nuclear power generation, the opinion that 'the utilization of nuclear power generation is unavoidable' accounts for 60% of those surveyed. With the opinion that 'nuclear power generation should be utilized' added, 70% of those surveyed take an affirmative attitude to nuclear power utilization. This situation has remained about the same since 1998, the year before the JCO accident. Using the quantification method III to analyze a number of questionnaires about nuclear power generation such as the anxiety about it, we determined overall attitude indexes regarding nuclear power to perform a time sequence comparison. The comparison shows that the attitude after the JCO accident tended to be more negative than in 1998. However, no significant difference in the overall indexes is seen between 1993 and 1998. Judging the comparison results on the basis of the time span starting in 1993 allows us to conclude that the JCO accident has not greatly contributed to worsening the attitude towards nuclear

  3. Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux

    Science.gov (United States)

    Bowman, Charles D.

    1992-01-01

    Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

  4. Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux

    Science.gov (United States)

    Bowman, C.D.

    1992-11-03

    Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

  5. Outlook for world nuclear power generation and long-term energy supply and demand situations

    International Nuclear Information System (INIS)

    Matsuo, Yuhji

    2012-01-01

    In this article, the author presents a long-term outlook for the world's nuclear generating capacity, taking into account the nuclear policy changes after Fukushima Daiichi nuclear power plant accident. World primary energy demand will grow from 11.2 billion tons of oil equivalent (toe) in 2009 to 17.3 billion toe in 2035. Along with this rapid increase in global energy consumption, the world's nuclear generating capacity will grow from 392 GW in 2010 to 484 GW in 2020 and 574 GW in 2035 in the 'Reference scenario'. Even in the 'Low nuclear scenario', where the maximum impact of Fukushima accident to the nuclear policies of each government is assumed, it will continue to grow in the future, exceeding 500 GW in 2035. In particular, Asian countries such as China and India will lead the growth both in the energy demand and in the nuclear power capacity. Therefore, it is essential to better ensure the safety of nuclear power generation. It is important for technologically developed countries, including Japan, to make active contributions to the establishment of a global nuclear safety control system. On the other hand, energy security and global warming will continue to be major issues, which will make it indispensable to make the best effort to save energy and expand renewable energy utilization. Japan is competitive in energy-saving and environmental conservation technologies, thus further development and utilization of there technologies should be a key option of Japan's growth growth strategy in the future. (author)

  6. Fate of Gases generated from Nuclear Wastes

    Energy Technology Data Exchange (ETDEWEB)

    Srinivasulu, M.; Francis, A. J. [Pohang Univ. of Science and Technology, Pohang (Korea, Republic of); Francis, A. J. [Brookhaven National Laboratory, New York (United States)

    2013-05-15

    The backfill materials such as cement, bentonite or crushed rock are used as engineered barriers against groundwater infiltration and radionuclide transport. Gas generation from radioactive wastes is attributed to radiolysis, corrosion of metals, and degradation of organic materials. Corrosion of steel drums and biodegradation of organic materials in L/ILW can generate gas which causes pressure build up and has the potential to compromise the integrity of waste containers and release the radionuclides and other contaminants into the environment. Performance assessment therefore requires a detailed understanding of the source and fate of gas generation and transport within the disposal system. Here we review the sources and fate of various type of gases generated from nuclear wastes and repositories. Studies on modeling of the fate and transport of repository gases primarily deal with hydrogen and CO{sub 2}. Although hydrogen and carbon dioxide are the major gases of concern, microbial transformations of these gases in the subterranean environments could be significant. Metabolism of hydrogen along with the carbon dioxide results in the formation of methane, low molecular weight organic compounds and cell biomass and thus could affect the total inventory in a repository environment. Modeling studies should take into consideration of both the gas generation and consumption processes over the long-term.

  7. Generation Mix Study Focusing on Nuclear Power by Practical Peak Forecast

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jung Ho; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    The excessive underestimation can lead to a range of problem; expansion of LNG plant requiring short construction period, the following increase of electricity price, low reserve margin and inefficient configuration of power source. With regard to nuclear power, the share of the stable and economic base load plant, nuclear power, can reduce under the optimum level. Amongst varied factors which contribute to the underestimate, immoderate target for demand side management (DSM) including double deduction of the constraint amount by DSM from peak demand forecast is one of the causes. The hypothesis in this study is that the better optimum generation mix including the adequate share of nuclear power can be obtained under the condition of the peak demand forecast without deduction of DSM target because this forecast is closer to the actual peak demand. In this study, the hypothesis is verified with comparison between peak demand forecast before (or after) DSM target application and the actual peak demand in the 3{sup rd} through 5{sup th} BPE from 2006 to 2010. Furthermore, this research compares and analyzes several generation mix in 2027 focusing on the nuclear power by a few conditions using the WASP-IV program on the basis of the 6{sup th} BPE in 2013. According to the comparative analysis on the peak demand forecast and actual peak demand from 2006 to 2010, the peak demand forecasts without the deduction of the DSM target is closer to the actual peak demand than the peak demand forecasts considering the DSM target in the 3{sup th}, 4{sup th}, 5{sup th} entirely. In addition, the generation mix until 2027 is examined by the WASP-IV. As a result of the program run, when considering the peak demand forecast without DSM reflection, since the base load plants including nuclear power take up adequate proportion, stable and economic supply of electricity can be achieved. On the contrary, in case of planning based on the peak demand forecast with DSM reflected and then

  8. A 1500-MW(e) HTGR nuclear generating station

    International Nuclear Information System (INIS)

    Stinson, R.C.; Hornbuckle, J.D.; Wilson, W.H.

    1976-01-01

    A conceptual design of a 1500-MW(e) HTGR nuclear generating station is described. The design concept was developed under a three-party arrangement among General Atomic Company as nuclear steam supply system (NSSS) supplier, Bechtel Power Corporation as engineer-constructors of the balance of plant (BOP), and Southern California Edison Company as a potential utility user. A typical site in the lower Mojave Desert in southeastern California was assumed for the purpose of establishing the basic site criteria. Various alternative steam cycles, prestressed concrete reactor vessel (PCRV) and component arrangements, fuel-handling concepts, and BOP layouts were developed and investigated in a programme designed to lead to an economic plant design. The paper describes the NSSS and BOP designs, the general plant arrangement and a description of the site and its unique characteristics. The elements of the design are: the use of four steam generators that are twice the capacity of GA's steam generators for its 770-MW(e) and 1100-MW(e) units; the rearrangement of steam and feedwater piping and support within the PCRV; the elimination of the PCRV star foundation to reduce the overall height of the containment building as well as of the PCRV; a revised fuel-handling concept which permits the use of a simplified, grade-level fuel storage pool; a plant arrangement that permits a substantial reduction in the penetration structure around the containment while still minimizing the lengths of cable and piping runs; and the use of two tandem-compound turbine generators. Plant design bases are discussed, and events leading to the changes in concept from the reference 8-loop PCRV 1500-MW(e) HTGR unit are described. (author)

  9. Public Opinion shifts to the favour of nuclear energy due to steam generator transport

    International Nuclear Information System (INIS)

    Lengar, I.; Nemec, T.

    2000-01-01

    In late August and early September of 1999, nuclear energy topics occupied a central place in the Slovenian media because of the transport of two new steam generators to the Krsko nuclear power plant, and also due to the protest action of an Austrian Green peace group. Before these events, the public opinion in Slovenia was not in favour or nuclear energy ;and Green peace had a good reputation. In September it has lost much credibility because of their clumsy :action of protest, and in just one month this caused a shift of public opinion in Slovenia towards support of Slovenian's only nuclear power plant. The Green peace protest action occurred during the transport of the two new steam generators to Krsko. By replacement of the old steam generators the operation of the Krsko NPP will be extended until 2023. The transport envoy travelled during the first half of September '99 across a considerable part of Slovene territory, passing by the capital of Ljubljana. (authors)

  10. Nuclear Data Processing for Generation of Stainless Steel Cross-Sections Data

    International Nuclear Information System (INIS)

    Suwoto; Zuhair

    2007-01-01

    Stainless steel has been used as important material in nuclear reactor and also in non nuclear industries. Nuclear data processing for generation of composite mixture cross-sections from several nuclides have been made. Provided evaluated nuclear data file (ENDF) such as ENDF/B- VI.8, JEFF-3.1 and JENDL-3.3 files were employed. Raw nuclear data cross-sections on file ENDF should be prepared and processed before it used in calculation. Sequence of nuclear data processing for generation of mixture cross-sections data from several nuclides is started from LINEAR, RECENT, SIGMA1 and MIXER codes taken from PREPR02000 utility code. Nuclear data processing is started from linearization of nuclear cross-sections data by using LINEAR code and counting background contribution of resonance parameter (MF2) with RECENT code (0 K) at energy ranges from 10 -5 to 10 7 eV. Afterward, the neutron cross-sections data should be processed and broadened to desire temperature (300 K) by using SIGMA1 code. Consistency of each cross-sections which used in nuclear data processing is checked and verified using FIXUP code. The next step is to define the composite mixture density (gr/cm 3 ) of stainless steel SUS-310 and weight fraction of each nuclide composition prior used it in MIXER code. All of the stainless steel SUS-310 cross sections are condensed to 650 energy groups structure (TART-energy structure) by using GROUPIE code to evaluate, analysis and review it more easily. The total, elastic scattering, non-elastic scattering and capture cross- sections of stainless steel SUS-310 have been made of ENDF/B-VI.8, JEFF-3.1 and JENDL-3.3 files. The stainless steel cross-sections made of ENDF/B- VI.8 file was taken as reference during validation process. The validation result of total cross-sections for stainless steel SUS-310 is clearly observed that the differences of total cross-sections error in nuclear data processing is relatively low than 0.01%. (author)

  11. From the lab to the battlefield? Nanotechnology and fourth generation nuclear weapons

    OpenAIRE

    Gsponer, Andre

    2005-01-01

    The paper addresses some major implications of microelectromechanical systems (MEMS) engineering and nanotechnology for the improvement of existing types of nuclear weapons, and the development of more robust versions of these weapons, as well as for the development of fourth generations nuclear weapons in which nanotechnology will play an essential role.

  12. Nuclear energy cost data base: A reference data base for nuclear and coal-fired powerplant power generation cost analysis

    International Nuclear Information System (INIS)

    1988-09-01

    A reference data base and standard methodology are needed for performing comparative nuclear and fossil power generation cost analyses for the Department of Energy, Office of Nuclear Energy. This report contains such a methodology together with reference assumptions and data to be used with the methodology. It is intended to provide basic guidelines or a starting point for analyses and to serve as a focal point in establishing parameters and methods to be used in economic comparisons of nuclear systems with alternatives. The data base is applicable for economic comparisons of new base load light-water reactors on a once-through cycle, and high- and low-sulfur coal-fired plants, and oil- and natural gas-fired electric generating plants coming on line around the turn of the century. In addition to current generation light-water reactors and fossil fuel-fired plants, preliminary cost information is also presented on improved and advanced light-water reactors, liquid metal reactor plants and fuel cycle facilities. This report includes an updated data base containing proposed technical and economic assumptions to be used in analyses, discussions of a recommended methodology to be used in calculating power generation costs, a sample calculation for illustrative and benchmark purposes and projected power generation costs for fission and coal-fired alternatives. Effects of the 1986 Tax Reform Act are included. 126 refs., 17 figs., 47 tabs

  13. Design of a fault diagnosis system for next generation nuclear power plants

    International Nuclear Information System (INIS)

    Zhao, K.; Upadhyaya, B.R.; Wood, R.T.

    2004-01-01

    A new design approach for fault diagnosis is developed for next generation nuclear power plants. In the nuclear reactor design phase, data reconciliation is used as an efficient tool to determine the measurement requirements to achieve the specified goal of fault diagnosis. In the reactor operation phase, the plant measurements are collected to estimate uncertain model parameters so that a high fidelity model can be obtained for fault diagnosis. The proposed algorithm of fault detection and isolation is able to combine the strength of first principle model based fault diagnosis and the historical data based fault diagnosis. Principal component analysis on the reconciled data is used to develop a statistical model for fault detection. The updating of the principal component model based on the most recent reconciled data is a locally linearized model around the current plant measurements, so that it is applicable to any generic nonlinear systems. The sensor fault diagnosis and process fault diagnosis are decoupled through considering the process fault diagnosis as a parameter estimation problem. The developed approach has been applied to the IRIS helical coil steam generator system to monitor the operational performance of individual steam generators. This approach is general enough to design fault diagnosis systems for the next generation nuclear power plants. (authors)

  14. Nuclear Power for Electricity Generation in Ghana: Issues and Challenges

    International Nuclear Information System (INIS)

    Nyarko, B.J.B.; Akaho, E.H.K.; Ennison, I.

    2011-01-01

    Ghana's electricity demand has been estimated to be growing at a high rate of about 7% per annum over the last ten years. This is due to the relatively high population growth, economic aspiration of the country and the extension of electricity to rural areas. Electricity supply, on the contrary, has been unable to meet the demand due to high dependency on rain-fed hydropower plants, which started operating in 1965 and currently account for about 68% of the total installed capacity. Within the last 28 years, climatic changes and draughts have caused the nation to experience three major power crises. These climate changes resulted in low inflows and thus reduced power generation from hydropower systems. To complement the hydropower systems, the Government in 1997 installed thermal plants based on light crude oil. However, due to the high crude oil prices on the international market in recent times have made the operation of these plants very expensive. Ghana's crude oil find can boost its energy supply when the oil exploration begins somewhere in 2010. For rural cooking, domestic biomass is employed. Ghana has no domestic coal resources. The Government of Ghana is concerned with: limited further growth potential of domestic hydro; high cost of imported oil and gas and environmental issues associated with use of imported coal. Small Solar and wind generation exist in some sectors, but potential large-scale development is not envisioned for the near future. With these in mind, the President of Ghana set up a Committee involving Stakeholder Institutions to formulate the Nuclear Power Policy and develop the basic elements of Nuclear Infrastructure and to assess the viability of introducing the nuclear power option in Ghana's energy mix. Cabinet took a decision to include the nuclear power for electricity generation after the Committee submitted his report to the President in 2008. (author)

  15. New radionuclide generator systems for use in nuclear medicine

    International Nuclear Information System (INIS)

    Atcher, R.W.

    1979-01-01

    A current emphasis in nuclear medicine is to better match the physical lifetime of the radionuclides used in vivo for diagnosis and treatment to the biological lifetime of the diagnostic procedure or to minimize radiation dose to areas other than those to be treated. In many cases the biological lifetime is on the order of minutes. Since the direct production of radionuclides with half lives of minutes requires the user to be near a suitable reactor or accelerator, this study was undertaken to produce short-lived radionuclides indirectly. If a long-lived radionuclide decays into a short-lived radionuclide, quick separation of the daughter activity from the parent enables the user to have a short-lived daughter while freeing him from the constraint of proximity to a cyclotron. Systems where a short-lived daughter is separated from a long-lived parent are called radionuclide generators. Two generator systems were developed for use in nuclear medicine, one in diagnostic work and the other for therapeutic work. The yield and breakthrough characteristics were within the limits required to minimize unnecessary radiation exposure in patients. Two parent radionuclides were produced using 4 He beams available from medium energy cyclotrons. The yield was high enough to produce generators that would be useful in clinical applications

  16. Reactor trip on turbine trip inhibit control system for nuclear power generating system

    International Nuclear Information System (INIS)

    Torres, J.M.; Musick, C.R.

    1976-01-01

    A reactor trip on turbine trip inhibit control system for a nuclear power generating system which utilizes steam bypass valves is described. The control system inhibits a normally automatic reactor trip on turbine trip when the bypass valves have the capability of bypassing enough steam to prevent reactor trip limits from being reached and/or to prevent opening of the secondary safety pressure valves. The control system generates a bypass valve capability signal which is continuously compared with the reactor power. If the capability is greater than the reactor power, then an inhibit signal is generated which prevents a turbine trip signal from tripping the nuclear reactor. 10 claims, 4 figures

  17. Fuelling innovation: Countries look to the next generation of nuclear power

    International Nuclear Information System (INIS)

    Perera, Judith

    2004-01-01

    The past few years have seen several multinational initiatives looking at the prospects for the medium and long-term development of nuclear energy. These include: the US-led Generation IV International Forum (GIF), the IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), and the European Michelangelo network for competitiveness and sustainability of nuclear energy in the EU (Micanet). There have also been two major studies - a joint investigation by the IAEA together with the OECD's International Energy Agency (IEA) and Nuclear Energy Agency (NEA), Innovative Nuclear Reactor Development; Opportunities for International Co-operation; and an interdisciplinary study by the Massachusetts Institute of Technology (MIT) on The Future of Nuclear Energy. All these cover much of the same ground, looking at innovative nuclear systems including reactors and fuel cycles. But, while they were prompted by the same set of underlying imperatives, they also differ to some extent, not least in the importance they attach to the nuclear fuel cycle. GIF and INPRO are two initiatives where enhanced international cooperation could emerge

  18. Cost comparison of 4x500 MW coal-fuelled and 4x850 MW CANDU nuclear generating stations

    International Nuclear Information System (INIS)

    Costa, M.

    1981-01-01

    The lifetime costs for a 4x850 MW CANDU generating station are compared to those for 4x500 MW bituminous coal-fuelled generating stations. Two types of coal-fuelled stations are considered; one burning U.S. coal which includes flue gas desulfurization and one burning Western Canadian coal. Current estimates for the capital costs, operation and maintenance costs, fuel costs, decommissioning costs and irradiated fuel management costs are shown. The results show: (1) The accumulated discounted costs of nuclear generation, although initially higher, are lower than coal-fuelled generation after two or three years. (2) Fuel costs provide the major contribution to the total lifetime costs for coal-fuelled stations whereas capital costs are the major item for the nuclear station. (3) The break even lifetime capacity factor between nuclear and U.S. coal-fuelled generation is projected to be 5%; that for nuclear and Canadian coal-fuelled generation is projected to be 9%. (4) Large variations in the costs are required before the cost advantage of nuclear generation is lost. (5) Comparison with previous results shows that the nuclear alternative has a greater cost advantage in the current assessment. (6) The total unit energy cost remains approximately constant throughout the station life for nuclear generation while that for coal-fuelled generation increases significantly due to escalating fuel costs. The 1978 and 1979 actual total unit energy cost to the consumer for several Ontario Hydro stations are detailed, and projected total unit energy costs for several Ontario Hydro stations are shown in terms of escalated dollars and in 1980 constant dollars

  19. Blown by the wind. Replacing nuclear power in German electricity generation

    International Nuclear Information System (INIS)

    Lechtenböhmer, Stefan; Samadi, Sascha

    2013-01-01

    Only three days after the beginning of the nuclear catastrophe in Fukushima, Japan, on 11 March 2011, the German government ordered 8 of the country's 17 existing nuclear power plants (NPPs) to stop operating within a few days. In summer 2011 the government put forward a law – passed in parliament by a large majority – that calls for a complete nuclear phase-out by the end of 2022. These government actions were in contrast to its initial plans, laid out in fall 2010, to expand the lifetimes of the country's NPPs. The immediate closure of 8 NPPs and the plans for a complete nuclear phase-out within little more than a decade, raised concerns about Germany's ability to secure a stable supply of electricity. Some observers feared power supply shortages, increasing CO 2 -emissions and a need for Germany to become a net importer of electricity. Now – a little more than a year after the phase-out law entered into force – this paper examines these concerns using (a) recent statistical data on electricity production and demand in the first 15 months after the German government's immediate reaction to the Fukushima accident and (b) reviews the most recent projections and scenarios by different stakeholders on how the German electricity system may develop until 2025, when NPPs will no longer be in operation. The paper finds that Germany has a realistic chance of fully replacing nuclear power with additional renewable electricity generation on an annual basis by 2025 or earlier, provided that several related challenges, e.g. expansion of the grids and provision of balancing power, can be solved successfully. Already in 2012 additional electricity generation from renewable energy sources in combination with a reduced domestic demand for electricity will likely fully compensate for the reduced power generation from the NPPs shut down in March 2011. If current political targets will be realised, Germany neither has to become a net electricity importer, nor will be unable

  20. Eddy current magnetic bias x-probe qualification and inspection of steam generator Monel 400 tubing in Pickering Nuclear Generating Station

    International Nuclear Information System (INIS)

    Lepine, B.A.; Van Langen, J.; Obrutsky, L.

    2006-01-01

    This paper presents an overview of the x-probe MB 350 eddy current inspection array probe, for detection of open OD axial crack-like flaws in Monel 400 tubes at Pickering Nuclear Generating Station. This report contains a selection of inspection results from the field inspections performed with this probe during the 2003 and 2004 period at Pickering Nuclear Generating Station A and B. During the 2003 in-service eddy current inspection results of Pickering Nuclear Generating Station A (PNGS-A) Unit 2, a 13 mm (0.5 inch) long axial indication was detected by the CTR1 bobbin and CTR2-C4 array probes in Tube R25-C52 of Steam Generator (SG) 11 in the hot leg sludge pile region. An experimental magnetic bias X-probe, specially designed by Zetec for inspection of Monel 400 tubing, was deployed and the indication was characterized as a potential out diameter (OD) axially oriented crack. Post-inspection tube pulling and destructive examination confirmed the presence of an Environmentally Assisted Crack (EAC), approximately 80% deep and 13mm long. Due to the significance of this discovery, Ontario Power Generation (OPG) requested AECL to initiate a program for qualification of the X-probe MB 350 for the detection of OD axial cracks in medium to high magnetic permeability μ r Monel 400 PNGS-A and B steam generator tubing at different locations. The X-probe MB 350 subsequently has been deployed as a primary inspection probe for crack detection for PNGS steam generators. (author)

  1. Generation of floor response spectra for a model structure of nuclear power plant

    International Nuclear Information System (INIS)

    Vaidyanathan, C.V.; Kamatchi, P.; Ravichandran, R.; Lakshmanan, N.

    2003-01-01

    The importance of Nuclear power plants and the consequences of a nuclear accident require that the nuclear structures be designed for the most severe environmental conditions. Earthquakes constitutes major design consideration for the system, structures and equipment of a nuclear power plant. The design of structures on ground is based on the ground response spectra. Many important parts of a nuclear power plant facility are attached to the principal parts of the structure and respond in a manner determined by the structural response rather than by the general ground motion to which the structure is supported. Hence the seismic response of equipment is generally based on the response spectrum of the floor on which it is mounted. In this paper such floor response spectra have been generated at different nodes of a chosen model structure of a nuclear power plant. In the present study a detailed nonlinear time history analysis has been carried out on the mathematical model of the chosen Nuclear Power Plant model structure with the spectrum compatible time history. The acceleration response results of the time history analysis has been used in the spectral analysis and the response spectra are generated. Further peak broadening has been done to account for uncertainties in the material properties and soil characteristics. (author)

  2. Foundations for the Fourth Generation of Nuclear Power

    International Nuclear Information System (INIS)

    Lake, James Alan

    2000-01-01

    Plentiful, affordable electrical energy is a critically important commodity to nations wishing to grow their economy. Energy, and more specifically electricity, is the fuel of economic growth. More than one-third of the world's population (more than 2 billion people), however, live today without access to any electricity. Further, another 2 billion people in the world exist on less than 100 watts of electricity per capita. By comparison, the large economies of Japan and France use more than 800 watts of electricity per capita, and the United States uses nearly 1500 watts of electricity per capita. As the governments of developing nations strive to improve their economies, and hence the standard of living of their people, electricity use is increasing. Several forecasts of electrical generation growth have concluded that world electricity demand will roughly double in the next 20-25 years, and possibly triple by 2050. This electrical generation growth will occur primarily in the rapidly developing and growing economies in Asia and Latin America. This net growth is in addition to the need for replacement generating capacity in the United States and Europe as aging power plants (primarily fossil-fueled) are replaced. This very substantial worldwide electricity demand growth places the issue of where this new electricity generation capacity is to come from squarely in front of the developed countries. They have a fundamental desire (if not a moral obligation) to help these developing countries sustain their economic growth and improve their standard of living, while at the same time protecting the energy (and economic) security of their own countries. There are currently 435 power reactors generating about 16 percent of the world's electricity. We know full well that nuclear power shows great promise as an economical, safe, and emissions-free source of electrical energy, but it also carries at least the perception of great problems, from public safety to dealing with

  3. A panel cointegration analysis of CO2 emissions, nuclear energy and income in major nuclear generating countries

    International Nuclear Information System (INIS)

    Baek, Jungho

    2015-01-01

    Highlights: • This study revisits the nuclear-energy-growth-CO 2 emissions nexus. • A panel cointegration analysis is employed. • Nuclear energy has a beneficial effect on reducing CO 2 emissions. • CO 2 emissions decrease with economic growth. - Abstract: A number of studies have examined the effect of nuclear energy on CO 2 emissions, and a lot has been learned from these studies. Due to their weaknesses in modeling approaches and variable uses, however, properly constructed and comprehensive analyses are limited. The main objective of this study is thus to contribute to the debate over nuclear energy and the environment with an enhanced model and variables. For this, a panel cointegration analysis is applied to quantify the effects of nuclear energy, energy consumption and income on CO 2 emissions in 12 major nuclear generating countries. The results show that nuclear energy tends to reduce CO 2 emissions. It is also found that CO 2 emissions tend to decrease monotonically with income growth, providing no evidence in support of the Environmental Kuznets Curve (EKC) for CO 2 emissions

  4. "Life without nuclear power": A nuclear plant retirement formulation model and guide based on economics. San Onofre Nuclear Generating Station case: Economic impacts and reliability considerations leading to plant retirement

    Science.gov (United States)

    Wasko, Frank

    Traditionally, electric utilities have been slow to change and very bureaucratic in nature. This culture, in and of itself, has now contributed to a high percentage of United States electric utilities operating uneconomical nuclear plants (Crooks, 2014). The economic picture behind owning and operating United States nuclear plants is less than favorable for many reasons including rising fuel, capital and operating costs (EUCG, 2012). This doctoral dissertation is specifically focused on life without nuclear power. The purpose of this dissertation is to create a model and guide that will provide electric utilities who currently operate or will operate uneconomical nuclear plants the opportunity to economically assess whether or not their nuclear plant should be retired. This economic assessment and stakeholder analysis will provide local government, academia and communities the opportunity to understand how Southern California Edison (SCE) embraced system upgrade import and "voltage support" opportunities to replace "base load" generation from San Onofre Nuclear Generating Station (SONGS) versus building new replacement generation facilities. This model and guide will help eliminate the need to build large replacement generation units as demonstrated in the SONGS case analysis. The application of The Nuclear Power Retirement Model and Guide will provide electric utilities with economic assessment parameters and an evaluation assessment progression needed to better evaluate when an uneconomical nuclear plant should be retired. It will provide electric utilities the opportunity to utilize sound policy, planning and development skill sets when making this difficult decision. There are currently 62 nuclear power plants (with 100 nuclear reactors) operating in the United States (EIA, 2014). From this group, 38 are at risk of early retirement based on the work of Cooper (2013). As demonstrated in my model, 35 of the 38 nuclear power plants qualify to move to the economic

  5. Relationship between people's awareness of environmental capabilities of saving energy, photovoltaic power generation and nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Hashiba, Takashi [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan)

    2001-09-01

    In this research, relationship between people's awareness of environmental capabilities of saving energy, photovoltaic power generation (PV) and nuclear power generation was investigated using questionnaire method. The results showed that saving energy is conducted without reference to its environment preservation effect. However the older people tend to regard saving energy as contribution to environment preservation. The attitude toward usage of PV has a close relationship to awareness of energy environmental concerns. Acceptance of cost sharing for the introducing of wide-scale PV systems to society is related to environment protection image of PV and the attitude toward loss of social convenience lost as a result of saving energy activities. The older people become, the more priority people put on environment protection before the social convenience. There is little relationship between environmental capabilities of nuclear power generation, that never discharge CO{sub 2} on generation, and awareness of energy environmental concerns. (author)

  6. Nuclear power generation in competition with other sources for base load electricity generation

    International Nuclear Information System (INIS)

    Notari, C.; Rey, F.C.

    1996-01-01

    The latest studies performed by OECD and IAEA on the subject were analyzed in order to clarify the international context. Nuclear, gas and coal are compared. The general conclusion is that nuclear power is competitive for electricity generation considering new plants to be commissioned around year 2000. If the discount rate is 5% per annum it is considered the best option in most of the countries included in the studies. If 10% is chosen the levelized costs favour the gas option. In the Argentine case, the analysis of possible plants for the near future shows a clear advantage for the gas projects. This is mainly due to the low capital costs and low local gas prices. The possible evolution of this situation is considered: gas prices will most probably increase because they should approach the price of fuel oil or diesel oil which are used as substitutes in winter for electricity generation and the export projects to Chile and Brasil will also push prices up. The environmental aspects of the question and its influence on regulations and costs is a matter of speculation. Some countries have already penalized greenhouse gases emissions but it is not clear how and when this trend will affect local prices. (author). 4 refs., 6 tabs

  7. Trend analyses of the emergency diesel generator problem events in Japanese and U.S. nuclear power plants

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2011-01-01

    Up to 2009, the author and a colleague conducted trend analyses of problem events related to main generators, emergency diesel generators, breakers, motors and transformers which are more likely to cause problems than other electric components in nuclear power plants. Among the electric components with high frequency of defect occurrence, i.e., emergency diesel generators, several years have passed since the last analyses. These are very important components needed to stop a nuclear reactor safely and to cool it down during external power supply loses. Then trend analyses were conducted for the second time. The trend analyses were performed on 80 problem events with emergency diesel generators which had occurred in U.S. nuclear power plants in the five years from 2005 through 2009 among events reported in the Licensee Event Reports (LERs: event reports submitted to NRC by U.S. nuclear power plants) which have been registered in the nuclear information database of the Institute of Nuclear Safety System, Inc. (INSS) , as well as 40 events registered in the Nuclear Information Archives (NUCIA), which occurred in Japanese nuclear power plants in the same time period. It was learned from the trend analyses of the problem events with emergency diesel generators that frequency of defect occurrence are high in both Japanese and US plants during plant operations and functional tests (that is, defects can be discovered effectively in advance), so that implementation of periodical functional tests under plant operation is an important task for the future. (author)

  8. The generator coordinate method in nuclear physics

    International Nuclear Information System (INIS)

    Giraud, B.G.

    1981-01-01

    The generator coordinate method is introduced as a physical description of a N-body system in a subspace of a reduced number of degrees of freedom. Special attention is placed on the identification of these special, 'collective' degrees of freedom. It is shown in particular that the method has close links with the Born-Oppenheimer approximation and also that considerations of differential geometry are useful in the theory. A set of applications is discussed and in particular the case of nuclear collisions is considered. (Author) [pt

  9. Engineer, procure, construct (EPC) for nuclear projects in OPG

    Energy Technology Data Exchange (ETDEWEB)

    Elliott, M. [Ontario Power Generation, Toronto, Ontario (Canada)

    2011-07-01

    OPG is exploring the use of EPC contracts for Nuclear Plant Design Modifications. Although OPG has used EPC outside of the nuclear island, this new initiative will begin to use EPC inside the plant, including upgrades to existing stations and mid-life refurbishment of Darlington. Benchmarking has shown that apart from new build, nuclear utilities rarely use this method inside the plant so OPG is using a step-by-step approach starting with projects with low complexity and low plant impact. The expected benefits are reduced interfaces and a simplified accountability model leading to schedule and cost improvements and lower rework. Design packages that incorporate construction input before issue will be a significant improvement. OPG's early challenges in moving to EPC include clearly defining roles, responsibilities and interfaces between the vendors and OPG, and modifying governance to match the new model. OPG intends to oversee the work while holding the vendor accountable for needs skill development on both sides. Vendors are expected to establish an engaged organization with complete knowledge of plant conditions, processes and streamlined methods to gain operations input. Vendors are also expected to identify and fix any quality issues before the modifications are commissioned and to have an in-house corrective action program to continuously improve. Vendors' early challenges include presenting one face to OPG rather than a collection of joint venture partners. This presentation describes OPG's plans and early feedback on this exciting new initiative.

  10. Engineer, procure, construct (EPC) for nuclear projects in OPG

    International Nuclear Information System (INIS)

    Elliott, M.

    2011-01-01

    OPG is exploring the use of EPC contracts for Nuclear Plant Design Modifications. Although OPG has used EPC outside of the nuclear island, this new initiative will begin to use EPC inside the plant, including upgrades to existing stations and mid-life refurbishment of Darlington. Benchmarking has shown that apart from new build, nuclear utilities rarely use this method inside the plant so OPG is using a step-by-step approach starting with projects with low complexity and low plant impact. The expected benefits are reduced interfaces and a simplified accountability model leading to schedule and cost improvements and lower rework. Design packages that incorporate construction input before issue will be a significant improvement. OPG's early challenges in moving to EPC include clearly defining roles, responsibilities and interfaces between the vendors and OPG, and modifying governance to match the new model. OPG intends to oversee the work while holding the vendor accountable for needs skill development on both sides. Vendors are expected to establish an engaged organization with complete knowledge of plant conditions, processes and streamlined methods to gain operations input. Vendors are also expected to identify and fix any quality issues before the modifications are commissioned and to have an in-house corrective action program to continuously improve. Vendors' early challenges include presenting one face to OPG rather than a collection of joint venture partners. This presentation describes OPG's plans and early feedback on this exciting new initiative.

  11. General design criteria for diesel-generator sets for nuclear power plants

    International Nuclear Information System (INIS)

    Rangarao, G.

    1975-01-01

    The design criteria for diesel-generators for nuclear power plants are examined. Applicable standards, loading, design performance, and characteristics to be considered in the selection of diesel-generator set and its auxiliary system are discussed. Also, engineered safety features loads together with loss of power safe shutdown loads and their starting sequence, analysis of voltage and frequency response and the diesel-generator ability to start various load blocks successfully to meet the reactor emergency core cooling requirements are discussed

  12. Online control loop tuning in Pickering Nuclear Generating Stations

    International Nuclear Information System (INIS)

    Yu, K.X.; Harrington, S.

    2008-01-01

    Most analog controllers in the Pickering B Nuclear Generating Stations adopted PID control scheme. In replacing the analog controllers with digital controllers, the PID control strategies, including the original tuning parameters were retained. The replacement strategy resulted in minimum effort on control loop tuning. In a few cases, however, it was found during commissioning that control loop tuning was required as a result of poor control loop performance, typically due to slow response and controlled process oscillation. Several factors are accounted for the necessities of control loop re-tuning. Our experience in commissioning the digital controllers showed that online control tuning posted some challenges in nuclear power plant. (author)

  13. Nuclear power generation alternative for a clean energy future

    International Nuclear Information System (INIS)

    Simionov, V; Ibadula, R.; Popescu, Ion.; Bobric, Elena

    2001-01-01

    World Energy Council stated that to raise the efficiency in which energy is provided is a huge challenge for power engineering. Over 60% of primary energy is in effect, wasted. At present 63% of the world's electricity comes from thermal power (coal, oil and gas), 19% from hydro, 17% from nuclear, 0.5% from geothermal and 0.1% from solar, wind and biomass. Nuclear power almost completely avoids all the problems associated within fossil fuels: no greenhouse effect, no acid rain, no air pollution with sulfur dioxide, nitrogen oxides, no oil spills, etc. Its impact on health and environment is related to radiation and is relatively minor. Without pretending a high accuracy of numbers, if the first Romanian nuclear power reactor will be replaced by a coal plant of equivalent capacity, about 5 millions tons of CO 2 and large quantities of associated sulfur and nitrous oxides, would be discharged to the atmosphere each year. However, the acceptance of nuclear power is largely an emotional issue. Based on the environmental monitoring program this paper tries to demonstrate that the routine radioactive emissions of Cernavoda NPP, which are limited by competent national authority, constitutes an insignificant risk increase. The concept of sustainable development was elaborated in the late 1980s and defined as a development that fulfil the needs of the present, without compromising the ability of future generations to meet their own needs. Sustainable development incorporates equity within and across countries as well as across generations, and integrates economic growth, environmental protection and social welfare. To analyze nuclear energy from a sustainable development perspective it is necessary to consider its economic, environmental and social impacts characteristics, both positive and negative. It is obvious that the development of nuclear energy broadens the natural resource base usable for energy production, and increases human and man-made capital. There are also

  14. Optimal electricity generation system expansion and nuclear power option in Belarus

    International Nuclear Information System (INIS)

    Yakushau, A.; Mikhalevich, A.

    2000-01-01

    After having declared independence, the Republic of Belarus was forced to import 90% of fuel consumed and 25% of electricity. The deficit of peak electric capacity reached 40%. The imported fuel covers the last years because the drop in the production reduced the energy consumption in the Republic but not the needs of the energy sector. Annual payments for imported fuel and electricity are equal to the sum of an annual state budget of Belarus (about 1.5 billion USD) and current debts were not lower 300 million. Comparative analysis of the different scenarios of the electricity generation system expansion showed that an optimum way for electricity generation is installation of the combine cycle units and construction nuclear power plants. The results of the study also showed that the option based on replacement of deficit of the electricity generation by the way of the construction combine cycle units with capacities 450 MW turned out to be the best solution among non nuclear options. (author)

  15. Nuclear Energy - a Part of a Solution to Generate Electric Power in Croatia?

    International Nuclear Information System (INIS)

    Mikulicic, V.; Simic, Z.

    1998-01-01

    The growth in Croatian energy, particularly electricity, demand together with growing environmental considerations is such that Croatia needs to have flexibility to respond, by having the option of expanding the nuclear sector. This paper deals with nuclear energy as an option for sustainable Croatian economic development, and with the nuclear power controversy. The conclusion is that there is a necessity for extended use of nuclear energy in Croatia. Most certainly the nuclear technology can provide the energy necessary to sustain progress and, as a country without coal, Croatia should favour nuclear power utilisation as the lowest cost option for base-load electricity generation. (author)

  16. Case study on comparative assessment of nuclear and coal-fueled electricity generation options and strategy for nuclear power development in China

    International Nuclear Information System (INIS)

    Zhao Shiping; Shi Xiangjun; Bao Yunqiao; Mo Xuefeng; Wei Zhihong; Fang Dong; Ma Yuqing; Li Hong; Pan Ziqiang; Li Xutong

    2001-01-01

    China, as other countries in the world, is seeking for a way of sustainable development. In energy/electricity field, nuclear power is one of electric energy options considering the Chinese capability of nuclear industry. The purpose of this study is to investigate the role of nuclear power in Chinese energy/electricity system in future by comprehensive assessment. The main conclusions obtained from this study are: (1) China will need a total generation capacity of 750 - 879 GW in 2020, which means new power units of 460 - 590 GW generation capacity will be built from 2001 to 2020. (2) the total amount of SO 2 emission from power production will rise to 16 - 18 Mt in 2020, about 2.8 - 3.2 times of 1995, even if the measures to control SO 2 emission are taken for all new coal units. (3) CO 2 emission from electricity generation will reach 21 - 24 Gt in 2020. (4) the environmental impacts and health risks of coal-fired energy chain are greater than that of nuclear chain. The normalized health risk caused by coal chain is 20.12 deaths/GW·a but 4.63 deaths/GW·a by nuclear chain in China. (5) As estimated by experts, there will be a shortage of 200 GW in 2050 in China even if considering the maximum production of coal, the utilization of hydropower and renewable resource. Nuclear power is the only way to fill the gap between demand and supply

  17. The SGR Multipurpose - Generation IV - Transportable Cogeneration Nuclear Reactor with Innovative Shielding

    International Nuclear Information System (INIS)

    Pahladsingh, R.R.

    2002-01-01

    Deregulation and liberalization are changing the global energy-markets. At the same time innovative technologies are introduced in the electricity industry; often as a requirement from the upcoming Digital Society. Energy solutions for the future are more seen as a mix of energy-sources for generation-, transmission- and distribution energy-services. The Internet Energy-web based 'Virtual' enterprises are coming up and will gradually change our society. It the fast changing world we have to realize that there will be less time to look for the adequate solutions to anticipate on global developments and the way they will influence our own societies. Global population may reach 9 billion people by 2030; this will put tremendous pressure on energy-, water- and food supply in the global economy. It is time to think about some major issues as described below and come up with the right answers. These are needed on very short term to secure a humane global economic growth and the sustainable global environment. The DOE (Department of Energy - USA) has started the Generation IV initiative for the new generation of nuclear reactors that must lead to much better safety, economics and public acceptance the new reactors. The SGR (Simplified Gas-cooled Reactor) is being proposed as a Generation IV modular nuclear reactor, using graphite pebbles as fuel, whereby an attempt has been made to meet all the DOE requirements, to be used for future nuclear reactors. The focus in this paper is on the changing and emerging global energy-markets and shows some relevant criteria to the nuclear industry and how we can anticipate with improved and new designs towards the coming Digital Society. (author)

  18. Modular sludge collection system for a nuclear steam generator

    International Nuclear Information System (INIS)

    Appleman, R.H.; Bein, J.D.; Powasaki, F.S.

    1986-01-01

    A sludge collection system is described for a vertically oriented nuclear steam generator wherein vapors produced in the steam generator pass through means for separating entrained liquid from the vapor prior to the vapor being discharged from the steam generator. The sludge collection system comprises: an upwardly open chamber for collecting the separated liquid and feedwater entering the steam generator; upwardly open sludge collecting containers positioned within the chamber, wherein each of the containers includes a top rim encompassing an opening leading to the interior of each container; generally flat, perforated covers, each of the covers being positioned over one of the openings such that a gap is formed between the cover and the adjacent top rim; sludge agitating means on at least one of the containers; and sludge removal means on at least one of the containers

  19. Co-generation of hydrogen from nuclear and wind: the effect on costs of realistic variations in wind generation. Paper no. IGEC-1-094

    International Nuclear Information System (INIS)

    Miller, A.I.; Duffey, R.B.

    2005-01-01

    Can electricity from high-capacity nuclear reactors be blended with the variable output of wind turbines to produce electrolytic hydrogen competitively? To be competitive with alternative sources, hydrogen produced by conventional electrolysis requires low-cost electricity (likely <2.5 cents US/kW.h). One approach is to operate interruptibly, allowing an installation to sell electricity when the grid price is high and to make hydrogen when it is low. Our previous studies show that this could be cost-competitive using nuclear power generator producing electricity around 3 cents US/kW.h. Although similar unit costs are projected for wind-generated electricity, idleness of the electrolysis facility due to the variability of wind-generated electricity imposes a significant cost penalty. This paper reports on ongoing work on the economics of blending electricity from nuclear and wind sources by using wind-generated power, when available, to augment the current through electrolysis equipment that is primarily nuclear-powered - a concept we call NuWind. A voltage penalty accompanies the higher current. A 10% increase in capital cost for electrolysis equipment to enable it to accommodate the higher rate of hydrogen generation is still substantially cheaper than the capital cost of wind-dedicated electrolysis. Real-time data for electricity costs have been combined with real-time wind variability. The variability in wind fields between sites was accommodated by assigning average wind speeds that produced an average electricity generation from wind of between 32 and 42% of peak capacity, which is typical of the expectations for superior wind-generation sites. (author)

  20. Tritium emissions from a detritiation facility

    International Nuclear Information System (INIS)

    Rodrigo, L.; El-Behairy, O.; Boniface, H.; Hotrum, C.; McCrimmon, K.

    2010-01-01

    Tritium is produced in heavy-water reactors through neutron capture by the deuterium atom. Annual production of tritium in a CANDU reactor is typically 52-74 TBq/MW(e). Some CANDU reactor operators have implemented detritiation technology to reduce both tritium emissions and dose to workers and the public from reactor operations. However, tritium removal facilities also have the potential to emit both elemental tritium and tritiated water vapor during operation. Authorized releases to the environment, in Canada, are governed by Derived Release Limits (DRLs). DRLs represent an estimate of a release that could result in a dose of 1 mSv to an exposed member of the public. For the Darlington Nuclear Generating Station, the DRLs for airborne elemental tritium and tritiated water emissions are ~15.6 PBq/week and ~825 TBq/week respectively. The actual tritium emissions from Darlington Tritium Removal Facility (DTRF) are below 0.1% of the DRL for elemental tritium and below 0.2% of the DRL for tritiated water vapor. As part of an ongoing effort to further reduce tritium emissions from the DTRF, we have undertaken a review and assessment of the systems design, operating performance, and tritium control methods in effect at the DTRF on tritium emissions. This paper discusses the results of this study. (author)

  1. Annual report, 1978

    International Nuclear Information System (INIS)

    1979-04-01

    In 1978, for the first time, nuclear generators supplied more electricity than coal-fired units: 30 percent of the total compared with 28 percent for coal. Energy demand in Ontario was up by 2.7 percent. No new commitments for generating stations were made, and work on committed stations was to be slowed until the generation expansion program had been fully reviewed. Atomic Energy of Canada Ltd. and Ontario Hydro have agreed to develop a nuclear wastes demonstration facility. The Select Committee of the Ontario Legislature on Ontario Hydro affairs investigated the costs of the Bruce heavy water plants and found no evidence of mismanagement. The Royal Commission on Electric Power Planning issued an interim report on nuclear power which recognized the need for and safety of the CANDU system. Reactors at Pickering and Bruce achieved an overall capacity factor of 81 percent. The third Bruce A unit was started up. Work on Bruce B and Pickering B was well underway. Bruce Heavy Water Plant B was virtually complete, but work was stopped on the second half of the Bruce D plant. Plans for the first half of Bruce D will be reviewed. Site preparation and excavation continued for the Darlington generating station. (LL)

  2. The next generation(s) of Europeans facing nuclear weapons: forgetful, indifferent but supportive? EU Non-Proliferation Consortium, Non-Proliferation Papers No. 56 March 2017

    International Nuclear Information System (INIS)

    Pelopidas, Benoit

    2017-04-01

    The post-cold war generation of citizens is forgetting nuclear weapon-related dangers and becoming indifferent to the issue. At the same time, the absence of mass grassroots, anti-nuclear protest suggests tacit support for current nuclear weapon policies. These three common diagnoses are potentially contradictory and, more importantly, are only assumptions. This paper is the first systematic attempt at assessing the attitude of the under 30's generation of European Union (EU) citizens with regard to nuclear weapons. It is based on a poll of over 10 000 citizens across the 28 EU member countries. The paper finds that none of these assumptions holds. Except for the cases of near nuclear use, the lack of knowledge about nuclear danger is not that widespread; it only increases slowly and not uniformly. Similarly, the lack of popular engagement in the nuclear weapon debate does not mean support for existing policies. In this paper, the sentiment of support is assessed with a set of three criteria: the feeling of safety attained from nuclear weapons; satisfaction with policies taken in one's name; and acceptance of vulnerabilities arising from the possession of nuclear weapons. This paper finds that overall support in these areas is below 30 per cent in every country for which there was a representative sample of respondents. Neither do the youth express a lack of concern, but rather a strong feeling of inability to affect the outcome. This suggests the need for both a research agenda and a reform of EU educational policies aimed at this generation on nuclear weapons

  3. Challenges in education and qualification of human resources for next nuclear generation

    International Nuclear Information System (INIS)

    Pupak, Marcia Orrico

    2009-01-01

    The general goal of this paper is to present an overview of Higher Education and personnel qualification for Nuclear Field by the perspective of the International Atomic Energy Agency (IAEA), also by the Organization for Economic Co-operation and Development (OECD and by the United Nations Educational Scientific and Cultural Organization (UNESCO). On the other hand to present the challenge of the Brazilian Government in redesigning, since 2003, the role of the state in order to make it active for younger generations, while promoting growth and social justice, has guided in all actions carried out under the Policy of Human Resources Management of public personnel. The government should be able to formulate and implement public policies and decide among various options, what is the most appropriate for its Human Resources. For this, they require the strengthening of strategic intelligence and government adoption of new ways of interaction and participation. The role played by the Brazilian Nuclear Energy Commission (CNEN) in looking forward to replace and qualify its nuclear staff, as soon as up, since that the qualification of a human resource in this field demands more than one decade. Last but not least the proactive work of IPEN-CNEN/SP to encourage young generation to enter nuclear area, and the efforts of the Brazilian government to implement an integrated Nuclear Programme to form human resources, to attract and retain students in nuclear engineering and related specialized fields, and how this problem should attract the attention of the entire nuclear community, government and industry. (author)

  4. Policy and practices in the United States of America for DOE-generated nuclear wastes

    International Nuclear Information System (INIS)

    Gilbert, F.C.

    1984-01-01

    Throughout the history of attempts to utilize atomic power in the USA, health and safety have been primary considerations in programme policy formulation. A brief historical review of the US nuclear waste management policy formulation over the years aids understanding of our current management strategy for government-generated (primarily defence-related) nuclear wastes. Scientists involved in the Manhattan project during World War II were aware of the dangers of radioactive wastes. The first reaction to this concern was the establishment of a health physics programme to monitor radioactive hazards in Manhattan District Laboratories. The Atomic Energy Act of 1946, which established the Atomic Energy Commission, called for protection of the health and safety of the public as well as atomic workers. That concept has been continued and strengthened, throughout the history of nuclear waste management in the USA. Passage of the Atomic Energy Act of 1954 required consideration of radioactive wastes generated by private industry as well as those produced by the Manhattan projects. Commercial waste management policy was based on the already established policy for management of government-generated wastes and is the subject of a separate paper at this symposium. Current US policy is to maintain separate but complementary programmes for nuclear wastes generated by government activities and those from commercial sources. US policy and practices for management of government-generated radioactive waste are summarized. Key organizational structure relating to waste management responsibility is presented. (author)

  5. Life cycle analysis on carbon emissions from power generation – The nuclear energy example

    International Nuclear Information System (INIS)

    Nian, Victor; Chou, S.K.; Su, Bin; Bauly, John

    2014-01-01

    Highlights: • This paper discusses about a methodology on the life cycle analysis of power generation using nuclear as an example. • The methodology encompasses generic system, input–output, and boundaries definitions. • The boundaries facilitate the use of Kaya Identity and decomposition technique to identify carbon emission streams. - Abstract: A common value of carbon emission factor, t-CO 2 /GWh, in nuclear power generation reported in the literature varies by more than a factor of 100. Such a variation suggests a margin of uncertainty and reliability. In this study, we employ a bottom-up approach to better define the system, its input and output, and boundaries. This approach offers improved granularity at the process level and consistency in the results. Based on this approach, we have developed a methodology to enable comparison of carbon emissions from nuclear power generation. The proposed methodology employs the principle of energy balance on a defined power generation system. The resulting system boundary facilitates the use of the “Kaya Identity” and the decomposition technique to identify the carbon emission streams. Using nuclear power as a case study, we obtained a carbon emission factor of 22.80 t-CO 2 /GWh, which falls to within 2.5% of the median of globally reported LCA results. We demonstrate that the resulting methodology could be used as a generic tool for life cycle analysis of carbon emissions from other power generation technologies and systems

  6. Comparative costs of coal and nuclear-generated electricity in the united states

    International Nuclear Information System (INIS)

    Brandfon, W.W.

    1987-01-01

    This paper compares the future first-year operating costs and lifetime levelized costs of producing baseload coal- and nuclear-generated electricity under schedules shorter than those recently experienced at U.S. plants. Nuclear appears to have a clear economic advantage. Coal is favorable only when it is assumed that the units will operate at very low capacity factors and/or when the capital cost differential between nuclear and coal is increased far above the recent historical level. Nuclear is therefore a cost-competitive electric energy option for utilities and should be considered as an alternative to coal when large baseload capacity is required. (author)

  7. Awareness of the general public relations strategy for nuclear power generation in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chano-Ok

    1989-02-01

    Ten years has passed since the first nuclear power plant was established in Korea. During the period, the total nuclear power generation capacity has increased to 5,716,000 kW, and additional two 950,000 kW plants currently under construction will start operating in 1988 and 1989, respectively. As of the end of 1987, nuclear power generation accounted for 53.1 % of the total power generated in the nation. The average utilization rate of the plants increased continuously from 46.3 % ten years ago up to 79.7 % in 1987. Public opinion polls were conducted in August and October of 1986, the year when the Chernobyl accident took place. The first survey covered 2,000 residents in urban and rural areas while the second one covered a total 1,000 nuclear-related engineers, scientists, administrative officials, businessmen, journalists and writers. The surveys have shown that 74.4 % of the general public agree on the construction of more nuclear power plants. The corresponding figure was 75 % for engineers and 50 % for journalists and writers. However, 73 % of the respondents who are for their construction did not want such a plant to be constructed near their residences. Concerning the safety of these plants, 79.5 % of the experts gave a positive reply while the corresponding figure was only 48.3 % for the general public. It is concluded that more active public relations activities are required in the future. (Nogami, K.).

  8. Awareness of the general public relations strategy for nuclear power generation in Korea

    International Nuclear Information System (INIS)

    Kim, Chano-Ok

    1989-01-01

    Ten years has passed since the first nuclear power plant was established in Korea. During the period, the total nuclear power generation capacity has increased to 5,716,000 kW, and additional two 950,000 kW plants currently under construction will start operating in 1988 and 1989, respectively. As of the end of 1987, nuclear power generation accounted for 53.1 % of the total power generated in the nation. The average utilization rate of the plants increased continuously from 46.3 % ten years ago up to 79.7 % in 1987. Public opinion polls were conducted in August and October of 1986, the year when the Chernobyl accident took place. The first survey covered 2,000 residents in urban and rural areas while the second one covered a total 1,000 nuclear-related engineers, scientists, administrative officials, businessmen, journalists and writers. The surveys have shown that 74.4 % of the general public agree on the construction of more nuclear power plants. The corresponding figure was 75 % for engineers and 50 % for journalists and writers. However, 73 % of the respondents who are for their construction did not want such a plant to be constructed near their residences. Concerning the safety of these plants, 79.5 % of the experts gave a positive reply while the corresponding figure was only 48.3 % for the general public. It is concluded that more active public relations activities are required in the future. (Nogami, K.)

  9. Present and future nuclear power generation as a reflection of individual countries' resources and objectives

    International Nuclear Information System (INIS)

    Borg, I.Y.

    1987-01-01

    The nuclear reactor industry has been in a state of decline for more than a decade in most of the world. The reasons are numerous and often unique to the energy situation of individual countries. Two commonly cited issues influence decisions relating to construction of reactors: costs and the need, or lack thereof, for additional generating capacity. Public concern has ''politicized'' the nuclear industry in many non-communist countries, causing a profound effect on the economics of the option. The nuclear installations and future plans are reviewed on a country-by-country basis for 36 countries in the light of the resources and objectives of each. Because oil and gas for power production throughout the world are being phased out as much as possible, coal-fired generation currently tends to be the chosen alternative to nuclear power production. Exceptions occur in many of the less developed countries that collectively have a very limited operating experience with nuclear reactors. The Chernobyl accident in the USSR alarmed the public; however, national strategies and plans to build reactors have not changed markedly in the interim. Assuming that the next decade of nuclear power generation is uneventful, additional electrical demand would cause the nuclear power industry to experience a rejuvenation in Europe as well as in the US. 80 refs., 3 figs., 22 tabs

  10. Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study

    International Nuclear Information System (INIS)

    Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

    1987-08-01

    Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators

  11. Electrosleeve process for in-situ nuclear steam generator repair

    International Nuclear Information System (INIS)

    Barton, R.A.; Moran, T.E.; Renaud, E.

    1997-01-01

    Degradation of steam generator (SG) tubing by localized corrosion is a widespread problem in the nuclear industry that can lead to costly forced out-ages, unit de-rating, SG replacement or even the permanent shutdown of a reactor. In response to the onset of SG tubing degradation at Ontario Hydro's Pickering Nuclear Generating Station (PNGS) Unit 5, and the determined unsuitability of conventional repair methods (mechanically expanded or welded sleeves) for Alloy 400, an alternative repair technology was developed. Electrosleeve is a non-intrusive, low-temperature process that involves the electrodeposition of a nanocrystalline nickel microalloy forming a continuously bonded, structural layer over the internal diameter of the degraded region. This technology is designed to provide a long-term pressure boundary repair, fully restoring the structural integrity of the damaged region to its original state. This paper describes the Electrosleeve process for SG tubing repair and the unique properties of the advanced sleeve material. The successful installation of Electrosleeves that have been in service for more than three years in Alloy 400 SG tubing at the Pickering-5 CANDU unit, the more recent extension of the technology to Alloy 600 and its demonstration in a U.S. pressurized water reactor (PWR), is presented. A number of PWR operators have requested plant operating technical specification changes to permit Electrosleeve SG tube repair. Licensing of the Electrosleeve by the U.S. Nuclear Regulatory Commission (NRC) is expected imminently. (author)

  12. Effect of nuclear power generation on the electricity price in Korea

    International Nuclear Information System (INIS)

    Lee, Man Kee; Song, Kee Dong; Kim, Seung Soo; Kim, Sung Kee; Lee, Yung Kun

    1994-12-01

    The main purpose of this study is to estimate the effect of nuclear power generation on the electricity price by analysing electricity supply sector. The effects on electricity price changes are estimated in terms of following respects: - Restriction on the additional introduction of nuclear power plant. - CO 2 emission quantity control and carbon tax. A computer model by using Linear Programming optimization technique was also developed for these analyses. 10 figs, 12 tabs, 32 refs. (Author)

  13. Planning of the steam generators for nuclear applications using optimization techniques

    International Nuclear Information System (INIS)

    Sakai, M.; Silvares, O.M.

    1978-01-01

    Procedure for the maximization of the net power of a nuclear power plant through the application of the optimal control theory of dynamic systems is presented. The problem is formulated in the steam generator which links the primary and the secondary cycle. The solution of the steam generator, optimization problem is obtained simultaneously with the heat balance in both primary and secondary cycle, through an iterative process. By this way the optimal parameters are obtained for the steam generator, the vapor and the cooling gas cycle [pt

  14. The future of nuclear power and fourth-generation reactors

    International Nuclear Information System (INIS)

    Carre, F.; Renault, C.

    2006-01-01

    Faced with the exhaustion of fossil fuel resources, the output of existing nuclear power must quadruple between now and 2050, and the Commissariat a l'Energie atomique (CEA) and its industrial partners are cooperating in a programme of R and D on future nuclear power. France strategy puts rapid neutron reactors (RNR) at the forefront, in view of their possible introduction by 2040. These reactors allow a more efficient use of uranium resources and minimise the production of long-life nuclear waste. Two technologies which use respectively, sodium and gas as their coolant are being studied. For the sodium RNR, which benefits from significant existing experience, the key is to first improve its economic performance. For the gas RNR, which draws on the principles and the generic assets of the RNR, for those using helium as the coolant, and those with applications at high temperature, it is important firstly to demonstrate the key technologies such as the fuel. The decision of President Chirac to launch the study of a prototype, fourth-generation reactor for 2020 is stimulating the research effort into France future nuclear power. (author)

  15. Economic impacts of electricity liberalization on the status of nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Hattori, Toru

    2015-01-01

    This paper discusses the economic impact of electricity liberalization on the status of nuclear power generation in the United States. Nuclear power plants have been treated equally with other types of power plants in the liberalized electricity market. The existing nuclear power plants were thought to be competitive in liberalized wholesale electricity market. Competitive pressure from the market also facilitated efficiency improvement among the existing nuclear power plants. Although it was difficult to build new reactor, the U.S. nuclear power generators expanded capacity through up rates. In recent years, however, nuclear power plants suffer from the decline in wholesale power prices and some of them are forced to retire early. Although there are some market design issues that could be improved to maintain the efficient nuclear power plants in competitive environment, it is now argued that some additional arrangements to mitigate the investment risks of the nuclear power plants are necessary. (author)

  16. On the economics of nuclear and coal-fired electric generation

    International Nuclear Information System (INIS)

    Pouris, A.

    1987-01-01

    This article addresses the relative merit of nuclear versus coal-fired electricity generation for plants beginning base-load service in South Africa after the year 2000. Emphasis is placed on the economic merits of the two technologies, and environmental and social implications are taken into account only in so far as legislation, security, and other considerations affect the economics of the technologies. It is assumed that nuclear and coal-fired generating plants wil represent the most cost-effective and feasible options for base-load service in the foreseeable future. Socio-political consideration and lack of indigenous oil production forbid the use of oil for the production of electricity, independently of economic merits. Similarly, the absence of local research on alternative renewable technologies, their stage of development abroad and their current economics limit the possibility of their extensive use in the time horizon under examination. The measure of economic merit used in the study is the 'levelized busbar cost' over the lifetime of the station

  17. Electric energy: global perspective, the brazilian desires and the nuclear generation role

    International Nuclear Information System (INIS)

    Barroso, Antonio Carlos de Oliveira; Dieguez, Jose Antonio Diaz; Imakuma, Kengo

    2003-01-01

    An evaluation of nuclear power perspectives considering the concepts of sustainable development and energy needs for developed and under development countries was made. It is clear that the role of nuclear energy - as an economical, safe and emissions-free source of electric energy - will depend on the solution of some fundamental questions. Expanding capacity of nuclear energy should focus primarily on the need for innovation in nuclear fuel cycles and nuclear power plants. In connection with these evaluations a foresight study on the nuclear area was conducted in Brazil with a small group of experts in order to find out the requirements for the future reactors. This paper describes the purpose, methodology, results and conclusions of this prospective exercise. A comparison is also made with the preliminary results obtained by GIF and INPRO international initiatives whose main objective is to identify the mos promising technologies for future generations of nuclear reactors. (author)

  18. Controlled energy generation from nuclear fusion. 60th year atw

    Energy Technology Data Exchange (ETDEWEB)

    Weiss, Georg [Pintsch Bamag AG, Frankfurt am Main (Germany)

    2015-02-15

    Prospects increase, that with a controlled process of nuclear fusion one day an additional nuclear energy source will be commercially exploitable. In what follows, scientific principles according to the most recent research will be presented. Since approximately 30 years we are aware of the fact, that energy in form of light and heat provided by the sun and other fixed stars since over four billions years resulted from reactions of atomic nuclei. A series of such reactions became known which are considered for 'thermonuclear' processes, for example the carbon cycle by Bethe, where hydrogen is converted into helium. Most of the reflections and experiments dealt until 1938 with the reaction between nuclei of light elements. The possibility of splitting heavy nuclei was not anticipated. Its discovery by Hahn and Strassmann was a complete surprise - so to speak a rash reaction to release energy at the end of the element row. This 'way out' captured the interest of nuclear physicist for more than a decade. Only today, by starting to construct big nuclear power plants - only today, being able to assess the possibilities and limitations of this technology, the idea of energy generation through nuclear fusion steps into the foreground of nuclear research.

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

    Directory of Open Access Journals (Sweden)

    Andrzej Reński

    2016-09-01

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

  20. Electric utilities deregulation and its impact on nuclear power generating stations

    International Nuclear Information System (INIS)

    Trehan, N.K.

    1998-01-01

    Under restructuring and deregulation, it is not clear as to who would have the responsibility, and what obligations the market participants would have to ensure that the electrical system reliability (stability) is maintained. Due to the dynamic nature of the electrical grid, especially with the implementation of restructuring and deregulation, vulnerabilities exist which may impact the reliability (stability) of the offsite electrical power system. In a nuclear power generating unit, an offsite electric power system and an onsite electric power system are required to permit the functioning of structures, systems, and components which are important to safety. The safety function for each system is to provide sufficient capacity and capability to assure that the containment integrity is maintained during power operation or in the event of a postulated accident. Analyses performed by the applicants must verify that the electrical grid remains stable in the event of a loss of the nuclear unit generator, the largest other unit on the grid or the most critical transmission line. The stability of the electric grid is assumed in the safety analyses and a change in it would impact those analyses. However, it may impact the availability of a stable electric power to the safety buses because of the limited number of available transmission lines. This paper discusses electrical power generation and demand, reserve margins, power transfer capability, development of new innovative technologies to compensate for lack of the construction of transmission lines, legislation for the formulation of a self regulation organization (SRO), grid disturbances that may lead to a voltage collapse, and the vulnerabilities which may impact the availability of a stable power to the nuclear power generating stations

  1. Experiences from maintaining the reliability of a nuclear standby diesel generator system

    International Nuclear Information System (INIS)

    Tammi, P.

    1982-01-01

    The nuclear standby diesel generator system is quite complicated comprising several mechanical and electrotechnical components, on which the reliability of the system is depending. It is an important support system of the plant safety system, and like the safety system it is composed of separate redundant units. The Loviisa nuclear power station has eight diesel generators. The first four of them were taken into operation in 1976. When the frequency of some mechanical failures showed increase, a project was started at the end of 1980 with the intention to find out potential failure possibilities and means for prevention of failures. The work has been mainly concentrated on improving the reliability of the diesel engines. (Auth.)

  2. Next Generation Nuclear Plant Materials Research and Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  3. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  4. Acoustic analysis of a piping system

    International Nuclear Information System (INIS)

    Misra, A.S.; Vijay, D.K.

    1996-01-01

    Acoustic pulsations in the Darlington Nuclear Generating Station, a 881 MW CANDU, primary heat transport piping system caused fuel bundle failures under short term operations. The problem was successfully analyzed using the steady-state acoustic analysis capability of the ABAQUS program. This paper describes in general, modelling of low amplitude acoustic pulsations in a liquid filled piping system using ABAQUS. The paper gives techniques for estimating the acoustic medium properties--bulk modulus, fluid density and acoustic damping--and modelling fluid-structure interactions at orifices and elbows. The formulations and techniques developed are benchmarked against the experiments given in 3 cited references. The benchmark analysis shows that the ABAQUS results are in excellent agreement with the experiments

  5. Trends on nuclear power generation and industry in European and American nations

    International Nuclear Information System (INIS)

    Tokai, Kunihiro

    2001-01-01

    In European and American nations, competitive principle was also recently introduced to electric industry allowed its local exclusion as a public business before today by liberalization of electric power market due to regulative relaxation, and then the existing electric power companies are now under serious competition with the other companies, of course with IPP which is its new comer. And, as nuclear power generation has already established there its position for an important source essential for electric power supply, by liberalization of electric power economy has also been severely required to the nuclear power generation. Then, the electric power companies intend to carry out cost-down by various means such as contraction of periodical inspection, and so on. Especially, in U.S.A., not only rationalization effort at a pace of every company but also various cost-down procedures ranging to reorganization of business such as purchase of other company power station, establishment of operation company integrally carrying out operation management of some companies, and so on, As a result, the nuclear power generation has come to obtain an evaluation to be an electric source sufficiently capable of competing with the other sources even at competitive market. On the other hand, its new construction continues at difficult condition. By adding to traditional objection against nuclear energy, in general, by recently entering of environmental protection party to the regime in some nations of western Europe, political environment around nuclear energy becomes unstable. And, liberalization of electric power also forms an investment environment advantageous for natural gas burning thermal power plants capable of carrying out short term capital recovery, in general. Therefore, the electric companies tend strongly to correspond to rather life elongation of the present plant than new plan construction. (G.K.)

  6. Examination of nuclear systems of fourth generation

    International Nuclear Information System (INIS)

    2015-01-01

    This report proposes a detailed discussion of the six nuclear systems selected by the Generation IV International Forum with the objective of coordinating research and development activities which should result in the deployment of nuclear systems (reactors and associated fuel cycle installations) of fourth generation by the second half of the 21. century. These systems are: sodium cooled fast reactors (SFR), very high temperature reactors (VHTR), gas cooled fast reactors (GFR), lead cooled fast reactors (LFR) or lead bismuth eutectic reactors (LBE), molten salt reactors (MSR), and supercritical water reactors (SCWR). Fast systems are interesting as they favour the transmutation of fertile materials into fissile materials. History and perspectives of development, main characteristics, management of safety functions, risk analysis, impact on the environment, radiation protection and decommissioning, concept maturity and R and D needs are discussed for each of these systems. A comparison is reported in terms of main characteristics of reactors, of neutron characteristics and reactivity control, of sensitivity to cooling losses, of confinement function, of exploitation safety, of in-service inspection, of behaviour in case of severe accident, of toxicity of chemical substances, of sensitivity to aggressions (seism), of concept maturity and technological difficulties. The report also proposes a review of the various fuels which can be used in these different systems and which have been considered as eligible by the International Forum: oxides, carbides, nitrides, metals, waste processing. The last part addresses the transmutation of long life radioactive elements: physics, context, assessment of scenarios soundness, influence of transmutation on installations and transports

  7. Process for superheating the steam generated by a light water nuclear reactor

    International Nuclear Information System (INIS)

    Vakil, H.B.; Brown, D.H.

    1976-01-01

    A process is submitted for superheating the pressurised steam generated in a light water nuclear reactor in which the steam is brought to 340 0 C at least. This superheated steam is used to operate a turbo-generator unit. The characteristic of the process is that an exothermal chemical reaction is used to generate the heat utilised during the superheating stage. The chemical reaction is a mechanisation, oxidation-reduction or hydrogenation reaction [fr

  8. Nuclear power generation and global heating

    International Nuclear Information System (INIS)

    Taboada, Horacio

    1999-01-01

    The Professionals Association and Nuclear Activity of National Atomic Energy Commission (CNEA) are following with great interest the worldwide discussions on global heating and the role that nuclear power is going to play. The Association has an active presence, as part of the WONUC (recognized by the United Nations as a Non-Governmental Organization) in the COP4, which was held in Buenos Aires in November 1998. The environmental problems are closely related to human development, the way of power production, the techniques for industrial production and exploitation fields. CO 2 is the most important gas with hothouse effects, responsible of progressive climatic changes, as floods, desertification, increase of average global temperature, thermal expansion in seas and even polar casks melting and ice falls. The consequences that global heating will have on the life and economy of human society cannot be sufficiently emphasized, great economical impact, destruction of ecosystems, loss of great coast areas and complete disappearance of islands owing to water level rise. The increase of power retained in the atmosphere generates more violent hurricanes and storms. In this work, the topics presented in the former AATN Meeting is analyzed in detail and different technological options and perspectives to mitigate CO 2 emission, as well as economical-financial aspects, are explored. (author)

  9. Comparing the sustainability parameters of renewable, nuclear and fossil fuel electricity generation technologies

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Annette; Strezov, Vladimir; Evans, Tim

    2010-09-15

    The sustainability parameters of electricity generation have been assessed by the application of eight key indicators. Photovoltaics, wind, hydro, geothermal, biomass, natural gas, coal and nuclear power have been assessed according to their price, greenhouse gas emissions, efficiency, land use, water use, availability, limitations and social impacts on a per kilowatt hour basis. The relevance of this information to the Australian context is discussed. Also included are the results of a survey on Australian opinions regarding electricity generation, which found that Australian prefer solar electricity above any other method, however coal, biomass and nuclear power have low acceptance.

  10. Vibrations measurement at the Embalse nuclear power plant's electrical generator

    International Nuclear Information System (INIS)

    Salomoni, R.C.; Belinco, C.G.; Pastorini, A.J.; Sacchi, M.A.

    1987-01-01

    After the modifications made at the Embalse nuclear power plant's electrical generator to reduce its vibration level produced by electromagnetic phenomena, it was necessary to perform measurements at the new levels, under different areas and power conditions. To this purpose, a work was performed jointly with the 'Vibrations Team' of the ANSALDO Company (the generator constructor) and the Hydrodynamic Assays Division under the coordination and supervision of the plant's electrical maintenance responsible. This paper includes the main results obtained and the instrumentation criteria and analysis performed. (Author)

  11. Calcium signals can freely cross the nuclear envelope in hippocampal neurons: somatic calcium increases generate nuclear calcium transients

    Directory of Open Access Journals (Sweden)

    Bading Hilmar

    2007-07-01

    Full Text Available Abstract Background In hippocampal neurons, nuclear calcium signaling is important for learning- and neuronal survival-associated gene expression. However, it is unknown whether calcium signals generated by neuronal activity at the cell membrane and propagated to the soma can unrestrictedly cross the nuclear envelope to invade the nucleus. The nuclear envelope, which allows ion transit via the nuclear pore complex, may represent a barrier for calcium and has been suggested to insulate the nucleus from activity-induced cytoplasmic calcium transients in some cell types. Results Using laser-assisted uncaging of caged calcium compounds in defined sub-cellular domains, we show here that the nuclear compartment border does not represent a barrier for calcium signals in hippocampal neurons. Although passive diffusion of molecules between the cytosol and the nucleoplasm may be modulated through changes in conformational state of the nuclear pore complex, we found no evidence for a gating mechanism for calcium movement across the nuclear border. Conclusion Thus, the nuclear envelope does not spatially restrict calcium transients to the somatic cytosol but allows calcium signals to freely enter the cell nucleus to trigger genomic events.

  12. Nuclear Power for Future Electricity Generation in Ghana: Issues and Challenges

    International Nuclear Information System (INIS)

    Nyarko, B.J.B.; Akaho, E.H.K.; Ennison, I.

    2011-01-01

    Ghana's electricity demand has been estimated to be growing at a high rate of about 7% per annum over the last ten years. This is due to the relatively high population growth, economic aspiration of the country and the extension of electricity to rural areas. Electricity supply, on the contrary, has been unable to meet the demand due to high dependency on rain-fed hydropower plants, which started operating in 1965 and currently account for about 68% of the total installed capacity. Within the last 28 years, climatic changes and draughts have caused the nation to experience three major power crises. These climate changes resulted in low inflows and thus reduced power generation from hydropower systems. To complement the hydropower systems, the Government in 1997 installed thermal plants based on light crude oil. However, due to the high crude oil prices on the international market in recent times have made the operation of these plants very expensive. Ghana's crude oil find can boost its energy supply when the oil exploration begins somewhere in 2010. For rural cooking, domestic biomass is employed. Ghana has no domestic coal resources. The Government of Ghana is concerned with: limited further growth potential of domestic hydro; high cost of imported oil and gas and environmental issues associated with use of imported coal. Small Solar and wind generation exist in some sectors, but potential large-scale development is not envisioned for the near future. With these in mind, the President of Ghana set up a Committee involving Stakeholder Institutions to formulate the Nuclear Power Policy and develop the basic elements of Nuclear Infrastructure and to assess the viability of introducing the nuclear power option in Ghana's energy mix. Cabinet took a decision to include the nuclear power for electricity generation after the Committee submitted his report to the President in 2008. (author)

  13. On the reliability of steam generator performance at nuclear power plants with WWER type reactors

    International Nuclear Information System (INIS)

    Styrikovich, M.A.; Margulova, T.Kh.

    1974-01-01

    The problem of ensuring reliable operation of steam generators in a nuclear power plant with a water-cooled, water-moderated reactor (WWER) was studied. At a nuclear power plant with a vertical steam generator (specifically, a Westinghouse product) the steam generator tubes were found to have been penetrated. Shutdown was due to corrosion disintegration of the austenitic stainless steel, type 18/8, used as pipe material for the heater surface. The corrosion was the result of the action of chlorine ions concentrated in the moisture contained in the iron oxide films deposited in low parts of the tube bundle, directly at the tube plate. Blowing through did not ensure complete removal of the film, and in some cases the construction features of the steam generator made removal of the film practically impossible. Replacement of type 18/8 stainless steel by other construction material, e.g., Inconel, did not give good results. To ensure reliable operation of vertical steam generators in domestic practice, the generators are designed without a low tube plate (a variant diagram of the vertical steam generator of such construction for the water-cooled, water-moderated reactor 1000 is presented). When low tube plates are used the film deposition is intolerable. For organization of a non-film regime a complex treatment of the feed water is used, in which the amount of complexion is calculated from the stoichmetric ratios with the composition of the feed water. It is noted that, if 100% condensate purification is used with complexon processing of the feed water to the generator, we can calculate the surface of the steam-generator heater without considering the outer placement on the tubes. In this the cost of the steam generator and all the nuclear power plants with WWER type reactors is decreased even with installation of a 100% condensate purification. It is concluded that only simultaneous solution of construction and water-regime problems will ensure relaible operation of

  14. Use of the Safety Monitor in operational decision-making at a nuclear generating facility

    International Nuclear Information System (INIS)

    Chien, Shan H.; Hook, Thomas G.; Lee, Roger J.

    1998-01-01

    The utilization of Safety Monitor at a nuclear generating facility in 1994 revolutionized the way US nuclear power plants manage configuration risks. At Southern California Edison (SCE) Company's San Onofre Nuclear Generating Station, it transformed probabilistic risk assessment (PRA) from a retrospective tool for understanding past risk into a prospective tool for controlling future risk. Since that time, many other nuclear utilities have taken aggressive steps in using PRA better to understand and manage risks associated with plant operation and maintenance. These utilities have employed a variety of methods ranging from systems similar to San Onofre's Safety Monitor to systems dramatically different in both technology and philosophy. In the development and use of its Safety Monitor, SCE has been guided by two philosophical goals: (1) maximize the objectivity of PRA-informed decision-making relative to managing configuration risks, and (2) ensure that risks are managed conservatively

  15. Nuclear energy cost data base. A reference data base for nuclear and coal-fired powerplant power-generation cost analysis

    International Nuclear Information System (INIS)

    1982-10-01

    A reference data base and standard methodology are needed for performing comparative nuclear and fossil power generation cost analyses for DOE/NE. Proposals are presented for such a methodology and for reference assumptions and data to be used with the methodology. This report is intended to provide basic guidelines or a starting point for analysis and to serve as a focal point in establishing parameters and methods to be used in economic comparisons of nuclear systems with alternatives. The data base is applicable for economic comparisons of new base-load light water reactors on either a current once-through cycle or self-generated recycle, high- and low-sulfur coal-fired plants, and oil and natural gas-fired electric generating plant coming on line in the last decade of this century. This paper includes a data base containing proposed technical and economic assumptions to be used in analyses, discussions of a recommended methodology to be used in calculating power generation costs, and a sample calculation for illustrative and benchmark purposes

  16. From reliability to maintenance of emergency generator sets in nuclear plants

    International Nuclear Information System (INIS)

    Reyraud, Y.

    1986-01-01

    The particular conditions of operation of emergency generator sets in a nuclear energy plant induce to take up a strategy of supervision and of maintenance very different of the one recommended for production generator sets. Mechanical and thermal pulls are affected by the size of the set and the choice of rotation running in respect of the wanted power and the response time requirements for the security of nuclear reactor. Reliability studies are helpful to define the strategy of supervision tests. The importance of the number of starts with respect to the running time requires the introduction of the idea of equivalent hours for the definition of maintenance periods. The security of the equipment and the upholding of the reliability at a value close to the optimum impose rigorous choices and strict conditions of supervision and maintenance [fr

  17. FIND: Douglas Point Nuclear Generating Station, Units 1 and 2

    International Nuclear Information System (INIS)

    Moore, M.M.

    1975-12-01

    This index is presented as a guide to microfiche items 1 through 136 in Docket 50448, which was assigned to Potomac Electric Power Company's Application for Licenses to construct and operate Douglas Point Nuclear Generating Station, Units 1 and 2. Information received from August, 1973 through July, 1975 is included

  18. The role of nuclear power generation in aspects of the foreign currency outflow

    International Nuclear Information System (INIS)

    Kim, Seung Su; Lee, Man Ki

    2005-01-01

    Korea has little domestic energy resources and so imported almost all of the primary energy consumed from the foreign countries, with the foreign energy dependency being about more than 97% in recent years. In the meantime, the import amount of energy together with the rapid economic growth has increased continuously during the past 30 years to be 49.6 billion dollar in 2004 while the Current Account Balance was 27.6 billion dollar in the same year. Especially, the growth rate of electric consumption greatly surpassed ones in GDP and primary energy over the past 20 years. Nuclear power generation has played an important role in Korean society by supporting the industrial development as well as stabilizing downward the electricity price. The steady progress in the localization of nuclear construction has decreased the amount of foreign currency outflow by the nuclear power plant construction. In addition, nuclear fuel cost is the most competitive among those of the other fossil fuel power sources, so that this situation resulted in the large decrease of foreign currency outflow in power sector. In this thesis, we focused on the savings effect in foreign currency outflow by nuclear power generation using the scenario method. We tried to evaluate what amount of foreign currency has been saved by the introduction of nuclear power plant instead of the other fossil fuel power plants

  19. An Axiomatic Design Approach of Nanofluid-Engineered Nuclear Safety Features for Generation III+ React

    International Nuclear Information System (INIS)

    Bang, In Cheol; Heo, Gyun Young; Jeong, Yong Hoon; Heo, Sun

    2009-01-01

    A variety of Generation III/III+ reactor designs featuring enhanced safety and improved economics are being proposed by nuclear power industries around the world to solve the future energy supply shortfall. Nanofluid coolants showing an improved thermal performance are being considered as a new key technology to secure nuclear safety and economics. However, it should be noted that there is a lack of comprehensible design works to apply nanofluids to Generation III+ reactor designs. In this work, the review of accident scenarios that consider expected nanofluid mechanisms is carried out to seek detailed application spots. The Axiomatic Design (AD) theory is then applied to systemize the design of nanofluid-engineered nuclear safety systems such as Emergency Core Cooling System (ECCS) and External Reactor Vessel Cooling System (ERVCS). The various couplings between Gen-III/III+ nuclear safety features and nanofluids are investigated and they try to be reduced from the perspective of the AD in terms of prevention/mitigation of severe accidents. This study contributes to the establishment of a standard communication protocol in the design of nanofluid-engineered nuclear safety systems

  20. 78 FR 79709 - Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown...

    Science.gov (United States)

    2013-12-31

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-302; NRC-2013-0283] Duke Energy Florida, Inc., Crystal River Unit 3 Nuclear Generating Plant Post-Shutdown Decommissioning Activities Report AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of receipt; availability; public meeting; and request...

  1. Effects of the criticality accident at Tokai-mura on the public's attitude to nuclear power generation

    Energy Technology Data Exchange (ETDEWEB)

    Kitada, Atsuko [Institute of Social Research, Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Hayashi, Chikio [The Institute of Statistical Mathematics, Tokyo (Japan)

    2000-09-01

    The objective of our study was to clarify the effects on the public's attitude of nuclear power and the criticality accident that occurred at the JCO plant in Tokai-mura, Ibaraki Prefecture. For this purpose, we conducted an awareness survey in the Kansai and Kanto areas two months after the accident. Analysis was made on the basis of the comparison of the survey results with the data that the Institute of Nuclear Safety System had accumulated through continuous awareness surveys on nuclear power generation (regular surveys) since 1993. The public's reactions were twofold. On one hand, there were emotional reactions about accidents in nuclear facilities and a reduction in the sense of security. On the other hand, there were reactions concerning the image of nuclear power plant workers and demand on electricity utilities for enhanced employee education and training. The latter reactions correspond to the problems pointed out after the JCO accident. Regarding the utilization of nuclear power generation, the opinion that 'the utilization of nuclear power generation is unavoidable' accounts for 60% of those surveyed. With the opinion that 'nuclear power generation should be utilized' added, 70% of those surveyed take an affirmative attitude to nuclear power utilization. This situation has remained about the same since 1998, the year before the JCO accident. Using the quantification method III to analyze a number of questionnaires about nuclear power generation such as the anxiety about it, we determined overall attitude indexes regarding nuclear power to perform a time sequence comparison. The comparison shows that the attitude after the JCO accident tended to be more negative than in 1998. However, no significant difference in the overall indexes is seen between 1993 and 1998. Judging the comparison results on the basis of the time span starting in 1993 allows us to conclude that the JCO accident has not greatly contributed to worsening

  2. Nuclear power and sustainable development. Maintaining and increasing the overall assets available to future generations

    International Nuclear Information System (INIS)

    2002-01-01

    A central goal of sustainable development is to maintain or increase the overall assets available to future generations, while minimizing consumption of finite resources and not exceeding the carrying capacities of ecosystems. The development of nuclear power broadens the natural resource base usable for energy production, increases human and man-made capital, and, when safely handled, has little impact on ecosystems. Energy is essential for sustainable development. With continuing population and economic growth, and increasing needs in the developing world, substantially greater energy demand is a given, even taking into account continuing and accelerated energy efficiency and intensity improvements. Today, nuclear power is mostly utilized in industrialized countries that have the necessary technological, institutional and financial resources. Many of the industrialized countries that are able and willing to use nuclear power are also large energy consumers. Nuclear power currently generates 16% of the world's electricity. It produces virtually no sulfur dioxide, particulates, nitrogen oxides, volatile organic compounds or greenhouse gases. Globally, nuclear power currently avoids approximately 600 million tonnes of carbon emissions annually, about the same as hydropower. The 600 MtC avoided by nuclear power equals 8% of current global greenhouse gases emissions. In the OECD countries, nuclear power has for 35 years accounted for most of the reduction in the carbon intensity per unit of delivered energy. Existing operating nuclear power plants (NPPs) for which initial capital investments are largely depreciated are also often the most cost-effective way to reduce carbon emissions from electricity generation. In fact in the United States in 2000, NPPs were the most cost-effective way to generate electricity, irrespective of avoided carbon emissions. In other countries the advantages of existing nuclear generating stations are also increasingly recognized. Interest

  3. IEEE Std 649-1980: IEEE standard for qualifying Class 1E motor control centers for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the basic principles, requirements, and methods for qualifying Class 1E motor control centers for outside containment applications in nuclear power generating stations. Qualification of motor control centers located inside containment in a nuclear power generating station is beyond the scope of this standard. The purpose of this standard is (1) to define specific qualification requirements for Class 1E motor control centers in accordance with the more general qualification requirements of IEEE Std 323-1974, IEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations; (2) to provide guidance in establishing a qualification program for demonstrating the design adequacy of Class 1E motor control centers in nuclear power generating station applications

  4. S100 lathe bed pulse generator applied to pulsed nuclear magnetic resonance

    International Nuclear Information System (INIS)

    Cernicchiaro, G.R.C.; Rudge, M.G.; Albuquerque, M.P.

    1989-01-01

    The project and construction of four channel pulse generator in the S100 standard plate and its control software for microcomputer are described. The microcomputer has total control on the pulse generator, which has seven programable parameters, defining the position of four pulses and the width for the three first ones. This pulse generator is controlled by a software developed in c language, and is used in pulsed nuclear magnetic resonance experiences. (M.C.K.) [pt

  5. Protection device for use in stopping a turbine generator in nuclear power plant

    International Nuclear Information System (INIS)

    Nagahama, Mizuo.

    1974-01-01

    Object: To supply to as great an extent as possible the residual output of a nuclear reactor to a turbine after the reactor is shutdown and to prevent overpower and motoring of a turbine by connecting a power direction relay to a secondary circuit of a current transformer and an instrumentation transformer at the high voltage side of a main transformer of a transmission bus line. Structure: When the output power of a generator after shuttingdown a nuclear reactor decreases below the sum of the mechanical losses of the turbine and the generator and the power for the house-auxiliaries connected to a fixed bus line, the direction of the current is reversed and the power is supplied from the transmission bus line through a circuit breaker for the generator and a main transformer onto the house-side, whereby a time limit relay of the power direction relay is actuated to disconnect the generator and the turbine. (Kamimura, M.)

  6. BWIP-RANDOM-SAMPLING, Random Sample Generation for Nuclear Waste Disposal

    International Nuclear Information System (INIS)

    Sagar, B.

    1989-01-01

    1 - Description of program or function: Random samples for different distribution types are generated. Distribution types as required for performance assessment modeling of geologic nuclear waste disposal are provided. These are: - Uniform, - Log-uniform (base 10 or natural), - Normal, - Lognormal (base 10 or natural), - Exponential, - Bernoulli, - User defined continuous distribution. 2 - Method of solution: A linear congruential generator is used for uniform random numbers. A set of functions is used to transform the uniform distribution to the other distributions. Stratified, rather than random, sampling can be chosen. Truncated limits can be specified on many distributions, whose usual definition has an infinite support. 3 - Restrictions on the complexity of the problem: Generation of correlated random variables is not included

  7. Automatic motion inhibit system for a nuclear power generating system

    International Nuclear Information System (INIS)

    Musick, C.R.; Torres, J.M.

    1977-01-01

    Disclosed is an automatic motion inhibit system for a nuclear power generating system for inhibiting automatic motion of the control elements to reduce reactor power in response to a turbine load reduction. The system generates a final reactor power level setpoint signal which is continuously compared with a reactor power signal. The final reactor power level setpoint is a setpoint within the capacity of the bypass valves to bypass steam which in no event is lower in value than the lower limit of automatic control of the reactor. If the final reactor power level setpoint is greater than the reactor power, an inhibit signal is generated to inhibit automatic control of the reactor. 6 claims, 5 figures

  8. Introduction to the methods of estimating nuclear power generating costs

    Energy Technology Data Exchange (ETDEWEB)

    1961-11-01

    The present report prepared by the Agency with the guidance and assistance of a panel of experts from Member States, the names of whom will be found at the end of this report, represents the first step in the methods of cost evaluation. The main objectives of the report are: (1) The preparation of a full list of the cost items likely to be encountered so that the preliminary estimates for a given nuclear power system can be relied upon in deciding on its economic merits. (2) A survey of the methods currently used for the estimation of the generating costs of the power produced by a nuclear station. The survey is intended for a wide audience ranging from engineers to public officials with an interest in the prospects of nuclear power. An attempt has therefore been made to refrain from detailed technical discussions in order to make the presentation easily understandable to readers with only a very general knowledge of the principles of nuclear engineering. 3 figs, tabs.

  9. Introduction to the methods of estimating nuclear power generating costs

    International Nuclear Information System (INIS)

    1961-01-01

    The present report prepared by the Agency with the guidance and assistance of a panel of experts from Member States, the names of whom will be found at the end of this report, represents the first step in the methods of cost evaluation. The main objectives of the report are: (1) The preparation of a full list of the cost items likely to be encountered so that the preliminary estimates for a given nuclear power system can be relied upon in deciding on its economic merits. (2) A survey of the methods currently used for the estimation of the generating costs of the power produced by a nuclear station. The survey is intended for a wide audience ranging from engineers to public officials with an interest in the prospects of nuclear power. An attempt has therefore been made to refrain from detailed technical discussions in order to make the presentation easily understandable to readers with only a very general knowledge of the principles of nuclear engineering. 3 figs, tabs

  10. State-of-the-art review of OPG steam generator tubing degradation mechanisms

    International Nuclear Information System (INIS)

    Brennenstuhl, A.M.; Ramamurthy, S.; Good, G.M.

    2009-01-01

    Steam generator (SG) degradation has been a major cause of pressurized water reactor (PWR) incapability world-wide and has limited the useful life of SGs at some utilities. The vast majority of the degradation has been the result of SCC of the thin walled nickel alloy SG tubes and has been most prevalent in mill annealed (MA) Alloy 600. Fortunately, Ontario Power Generation (OPG) SG tubes are manufactured from alloys that have much better resistance to this form of localized corrosion than Alloy 600MA and as a consequence have not encountered SCC to date. Other forms of degradation nevertheless have been experienced; some units at Pickering - B in particular have had many Alloy 400 SG tubes removed from service due to severe underdeposit corrosion (UDC) and costly modifications have been made to Darlington SGs to prevent leaks as a result of SG tube fretting-wear at tube supports. Degradation other than UDC and fretting-wear which could pose a threat to the future reliable operation of OPG's nuclear fleet has also been observed. Important activities in effectively managing SG degradation include determining the mode of degradation and arriving at an understanding of the contributing factors. This is done by a combination of non-destructive examination (NDE) of SG tubing in-situ, SG tube removals for metallurgical examination and research and development. SG tube metallurgical examinations provide information that can be used in the timely development of a strategy dealing with the degradation in the short to intermediate timeframe. Determining the main causative factors at a mechanistic level helps to improve the predictive capability and increases the probability of dealing with the problem in the most cost-effective way. OPG has used this approach together with in-situ NDE inspections during planned outages of its nuclear reactors to minimize the possibility of unscheduled outages and provide the best possible fitness-for-service assessments. Many metallurgical

  11. Ethics Beyond Finitude: Responsibility towards Future Generations and Nuclear Waste Management

    International Nuclear Information System (INIS)

    Loefquist, Lars

    2008-01-01

    This dissertation has three aims: 1. To evaluate several ethical theories about responsibility towards future generations. 2. To construct a theory about responsibility towards future generations. 3. To carry out an ethical evaluation of different nuclear waste management methods. Five theories are evaluated with the help of evaluative criteria, primarily: A theory must provide future generations with some independent moral status. A theory should acknowledge moral pluralism. A theory should provide some normative claims about real-world problems. Derek Parfit's theory provides future generations with full moral status. But it is incompatible with moral pluralism, and does not provide reasonable normative claims about real-world problems. Brian Barry's theory provides such claims and a useful idea about risk management, but it does not provide an argument why future generations ought to exist. Avner de-Shalit's theory explains why they ought to exist; however, his theory can not easily explain why we ought to care for other people than those in our own community. Emmanuel Agius' theory gives an ontological explanation for mankind's unity, but reduces conflicts of interests to a common good. Finally, Hans Jonas' theory shifts the focus from the situation of future generations to the preconditions of human life generally. However, his theory presupposes a specific ontology, which might be unable to motivate people to act. The concluding chapters describe a narrative theory of responsibility. It claims that we should comprehend ourselves as parts of the common story of mankind and that we ought to provide future generations with equal opportunities. This implies that we should avoid transferring risks and focus on reducing the long-term risks associated with the nuclear waste

  12. The downstream side of the nuclear fuel cycle. Tome II: Electricity generating costs

    International Nuclear Information System (INIS)

    Bataille, Ch.; Galley, R.

    1999-01-01

    As part of the Office's continuing work in the nuclear field, Mr. Christian Bataille and Mr. Robert Galley, Members of Parliament for the Nord and Aube departements respectively, published in June 1998 the first part of their investigation into the downstream side of the nuclear fuel cycle, focusing on the work done in application of the law of 30 December 1991 concerning research into radioactive waste management. This document supplements that initial technical approach with a technical and economic study of the costs of generating electricity. To begin with, the performance of existing nuclear generating plant is examined, in particular the past, present and future contributions of this plant to the growth and competitiveness of the French economy. Secondly, the competitiveness of the different generating systems is analysed with a view to the construction of new facilities, using the method of discounted average costs which is at present the standard approach governing investment decisions, and identifying the different ways in which the said systems are dealt with as regards the cost categories considered. The potential contributions of external factor analysis and the calculation of external costs are then reviewed in order to evaluate the advantages and drawbacks of the different electricity generating systems on a more global basis. The report includes more than a hundred tables of data and cost curves upon which the Rapporteurs base their comments, conclusions and recommendations

  13. Use of intelligent loop diagrams at San Onofre Nuclear Generation Station (SONGS)

    International Nuclear Information System (INIS)

    Groves, J.E.; Johnson, K.I.; Foulk, J.; Reinschmidt, K.F.; Tutos, N.C.

    1991-01-01

    The use of advanced information systems will result in five million dollars potential cost reduction and two years less time for producing over 2000 Instrumentation and Control Loop Diagrams for the three nuclear units at San Onofre Nuclear Generating Station (SONGS). This new information technology will also assist plant management at SONGS in generating even larger savings from reduction in operations and maintenance costs. The key element of the new solution is the use of plant drawings, the traditional primary source of plant information, for on-line access to all plant databases and information systems, by replacing paper drawings with intelligent electronic drawings. The implementation of this concept for the Instrumentation and Control Loop Diagrams, presently in progress, is part of the Integrated Nuclear Data Management Systems (INDAMS) program at SONGS, a joint effort which includes support from Stone and Webster Advanced Systems Development Services, International Business Machines Corporation (IBM), and Dassault Systems of France. The initial results have encouraged plant management to speed up the implementation process

  14. Safety improvement technologies for nuclear power generation

    International Nuclear Information System (INIS)

    Nishida, Koji; Adachi, Hirokazu; Kinoshita, Hirofumi; Takeshi, Noriaki; Yoshikawa, Kazuhiro; Itou, Kanta; Kurihara, Takao; Hino, Tetsushi

    2015-01-01

    As the Hitachi Group's efforts in nuclear power generation, this paper explains the safety improvement technologies that are currently under development or promotion. As efforts for the decommissioning of Fukushima Daiichi Nuclear Power Station, the following items have been developed. (1) As for the spent fuel removal of Unit 4, the following items have mainly been conducted: removal of the debris piled up on the top surface of existing reactor building (R/B), removal of the debris deposited in spent fuel pool (SFP), and fuel transfer operation by means of remote underwater work. The removal of all spent fuels was completed in 2014. (2) The survey robots inside R/B, which are composed of a basement survey robot to check leaking spots at upper pressure suppression chamber and a floor running robot to check leaking spots in water, were verified with a field demonstration test at Unit 1. These robots were able to find the leaking spots at midair pipe expansion joint. (3) As the survey robot for reactor containment shells, robots of I-letter posture and horizontal U-letter posture were developed, and the survey on the upper part of first-floor grating inside the containment shells was performed. (4) As the facilities for contaminated water measures, sub-drain purification equipment, Advanced Liquid Processing System, etc. were developed and supplied, which are now showing good performance. On the other hand, an advanced boiling water reactor with high safety of the United Kingdom (UK ABWR) is under procedure of approval for introduction. In addition, a next-generation light-water reactor of transuranic element combustion type is under development. (A.O.)

  15. A cohort analysis of nuclear generation cost data

    International Nuclear Information System (INIS)

    Ono, Kenji; Nakamura, Takashi

    2002-01-01

    At the Nuclear Energy Information Center of the Central Research Institute of Electric Power Industry, Ltd., cost analysis of nuclear power generation has been carried out. In general, it is frequently carried out to analyze timely changing trends on various indexes on management of power stations such as annual O and M (operation and management) costs, apparatus using ratio, and so on, in nuclear power stations. Main aims of such analyses are to obtain knowledge useful for future policies and management decision making by grasping factors causing such changes to evaluate effects based on them as quantitatively as possible. Effects of the timely changing factors on various indexes on management of power stations can consider by dividing them to three types shown as follows; (1) effects of every years, (2) effects of every elapsed years, and (3) effects of operation beginning year. By separating these three effects to evaluate them, grasping of factors at background of the changes and their quantitative evaluations can be carried out more correctly, to be expected to obtain more useful knowledge. Here were described results applied on engineering method called by the 'Bayes type Cohort model' developed at a field of social science to trend analysis on indexes of such power stations. (G.K.)

  16. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 1. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

    International Nuclear Information System (INIS)

    Nero, A.V. Jr.

    1977-01-01

    This report presents an overview of a project on the health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. In addition to presenting an executive summary of the project, it sets forth the main results of the four tasks of the project: to review the health impacts (and related standards) of these forms of power generation, to review the status of standards related to plant safety (with an emphasis on nuclear power), to consider the role of the California Energy Resources Conservation and Development Commission in selection of standards, and to set forth methodologies whereby that Commission may review the health and safety aspects of proposed sites and facilities

  17. Technological studies for obtaining lead oxide compacts used in generation IV nuclear reactors

    International Nuclear Information System (INIS)

    Paraschiv, I.; Benga, D.

    2016-01-01

    One of the main concerns of the nuclear research at this moment is the development of the necessary technologies for Generation IV reactors. The main candidate as coolant agent in these reactors is molten lead but this material involves ensuring the oxygen control, due to potential contamination of coolant through the formation of solid oxides and the influence on the corrosion rate of structural parts and for this reason, the oxygen concentration must be kept in a well specified domain. One of the proposed methods for oxygen monitoring and control in the technology of Generation IV reactors, is the use of PbO compacts. For this paper technological tests were performed for developing and setting the optimal parameters in order to attain lead oxide compacts necessary for the oxygen control technology in Generation IV nuclear reactors. (authors)

  18. The steam generator repair project of the Donald C. Cook Nuclear Plant, Unit 2

    International Nuclear Information System (INIS)

    White, J.D.

    1993-01-01

    Donald C. Cook Nuclear Plant Unit 2 is part of a two unit nuclear complex located in southwestern Michigan and owned and operated by the Indiana Michigan Power Company. The Cook Nuclear Plant is a pressurized water reactor (PWR) plant with four Westinghouse Series 51 steam generators housed in an ice condenser containment. This paper describes the program undertaken by Indiana Michigan Power and the American Electric Power Service Corporation (AEPSC) to repair the Unit 2 steam generators. (Both Indiana Michigan Power and AEPSC arc subsidiaries of American Electric Power Company, Incorporated (AEP). AEPSC provides management and technical support services to Indiana Michigan Power and the other AEP operating companies.) Eddy current examinations, in a series of refueling and forced outages between November 1983 and July 1986 resulted in 763 (5.6%) plugged tubes. In order to maintain adequate reactor core cooling, a limit of 10% is placed on the allowable percentage of steam generator tubes that can be removed from service by plugging. Additionally, sections of tubes were removed for metallurgical analysis and confirmed that the degradation was due to intergranular stress corrosion cracking. In developing the decision on how to repair the steam generators, four alternative actions were considered for addressing these problems: retubing in place, sleeving, operating at 80% reactor power to lower temperature and thus reduce the rate of corrosion, replacing steam generator lower assemblies

  19. Load following generation in nuclear power plants by latent thermal energy storage

    International Nuclear Information System (INIS)

    Abe, Yoshiyuki; Takahashi, Yoshio; Kamimoto, Masayuki; Sakamoto, Ryuji; Kanari, Katsuhiko; Ozawa, Takeo

    1985-01-01

    The recent increase in nuclear power plants and the growing difference between peak and off-peak demands imperatively need load following generation in nuclear power plants to meet the time-variant demands. One possible way to resolve the problem is, obviously, a prompt reaction conrol in the reactors. Alternatively, energy storage gives another sophisticated path to make load following generation in more effective manner. Latent thermal energy storage enjoys high storage density and allows thermal extraction at nearly constant temperature, i.e. phase change temperature. The present report is an attempt to evaluate the feasibility of load following electric power generation in nuclear plants (actually Pressurized Water Reactors) by latent thermal energy storage. In this concept, the excess thermal energy in the off-peak period is stored in molten salt latent thermal energy storage unit, and additional power output is generated in auxiliary generator in the peak demand duration using the stored thermal energy. The present evaluation gives encouraging results and shows the primary subject to be taken up at first is the compatibility of candidate storage materials with inexpensive structural metal materials. Chapter 1 denotes the background of the present report, and Chapter 2 reviews the previous studies on the peak load coverage by thermal energy storage. To figure out the concept of the storage systems, present power plant systems and possible constitution of storage systems are briefly shown in Chapter 3. The details of the evaluation of the candidate storage media, and the compilation of the materials' properties are presented in Chapter 4. In Chapter 5, the concept of the storage systems is depicted, and the economical feasibility of the systems is evaluated. The concluding remarks are summarized in Chapter 6. (author)

  20. Nuclear Knowledge to the Next Generation

    International Nuclear Information System (INIS)

    Mazour, Thomas; Kossilov, Andrei

    2004-01-01

    The safe, reliable, and cost-effective operation of Nuclear Power Plants (NPPs) requires that personnel possess and maintain the requisite knowledge, skills, and attitudes to do their jobs properly. Such knowledge includes not only the technical competencies required by the nature of the technology and particular engineering designs, but also the softer competencies associated with effective management, communication and teamwork. Recent studies have shown that there has been a loss of corporate knowledge and memory. Both explicit knowledge and tacit knowledge must be passed on to the next generation of workers in the industry to ensure a quality workforce. New and different techniques may be required to ensure timely and effective knowledge retention and transfer. The IAEA prepared a report on this subject. The main conclusions from the report regarding strategies for managing the aging workforce are included. Also included are main conclusions from the report regarding the capture an d preservation of mission critical knowledge, and the effective transfer of this knowledge to the next generation of NPP personnel. The nuclear industry due to its need for well-documented procedures, specifications, design basis, safety analyses, etc., has a greater fraction of its mission critical knowledge as explicit knowledge than do many other industries. This facilitates the task of knowledge transfer. For older plants in particular, there may be a need for additional efforts to transfer tacit knowledge to explicit knowledge to support major strategic initiatives such as plant license extensions/renewals, periodic safety reviews, major plant upgrades, and plant specific control room simulator development. The challenge in disseminating explicit knowledge is to make employees aware that it is available and provide easy access in formats and forms that are usable. Tacit knowledge is more difficult to identify and disseminate. The challenge is to identify what can be converted to

  1. Limerick Nuclear Generating Station vibration monitoring system

    International Nuclear Information System (INIS)

    Mikulski, R.

    1988-01-01

    Philadelphia Electric Company utilizes a vibration monitoring computer system at its Limerick Nuclear Generating Station to evaluate machine performance. Performance can be evaluated through instantaneous sampling, online static and transient data. The system functions as an alarm monitor, displaying timely alarm data to the control area. The passage of time since the system's inception has been a learning period. Evaluation through continuous use has led to many enhancements in alarm handling and in the acquisition and display of machine data. Due to the system's sophistication, a routine maintenance program is a necessity. This paper describes the system's diagnostic tools and current utilization. System development and maintenance techniques will also be discussed

  2. Public acceptance of nuclear power generation in the United States

    International Nuclear Information System (INIS)

    Liverman, J.L.; Thorne, R.D.

    1977-01-01

    Within the United States environmental awareness has spread and matured since the early 1960's. Evidence of this is found in cautious attitudes toward the installation of nuclear power reactors and other components of the nuclear fuel cycle. Hazards associated with nuclear energy technologies appear to attract a greater share of public attention than the hazards of nonnuclear counterparts. The association of nuclear power with nuclear weapons may be at the root of this concern. The explicit identification of increased incidences of cancer and genetic effects in humans as potential consequences of exposure to ionizing radiation and knowledge that radiation exposures and health consequences arising from nuclear power operations might occur many generations after operations cease also underlie this concern. Based in large part on these concerns, a number of actions have been taken in the United States to prevent and to delay installation and development of nuclear technology. These actions are reviewed and analyzed with emphasis on the 1976 California nuclear moratorium referendum and other more recent actions at state and national levels. They are compared with the status and outcome of similar actions in other nations as is possible. Additionally, ERDA's current approaches to public involvement in the decision making process is discussed, including the value of comprehensive analyses of health, environmental, and socioeconomic aspects of alternative energy sources in responding to public needs. U.S. plans for providing such analyses for all installed and developing energy technologies are presented with special reference to areas which require international cooperation for implementation. The value of international analysis and internationally accepted environmental control strategies for all energy technologies is also addressed

  3. Neutron excess generation by fusion neutron source for self-consistency of nuclear energy system

    International Nuclear Information System (INIS)

    Saito, Masaki; Artisyuk, V.; Chmelev, A.

    1999-01-01

    The present day fission energy technology faces with the problem of transmutation of dangerous radionuclides that requires neutron excess generation. Nuclear energy system based on fission reactors needs fuel breeding and, therefore, suffers from lack of neutron excess to apply large-scale transmutation option including elimination of fission products. Fusion neutron source (FNS) was proposed to improve neutron balance in the nuclear energy system. Energy associated with the performance of FNS should be small enough to keep the position of neutron excess generator, thus, leaving the role of dominant energy producers to fission reactors. The present paper deals with development of general methodology to estimate the effect of neutron excess generation by FNS on the performance of nuclear energy system as a whole. Multiplication of fusion neutrons in both non-fissionable and fissionable multipliers was considered. Based on the present methodology it was concluded that neutron self-consistency with respect to fuel breeding and transmutation of fission products can be attained with small fraction of energy associated with innovated fusion facilities. (author)

  4. Nuclear power investment and generating costs from a utility point of view

    International Nuclear Information System (INIS)

    Roth, B.F.

    1975-01-01

    Nuclear power stations presently in operation in the Federal Republic of Germany have electricity generating costs between 3.5 Pf/kWh and 4.5 Pf/kWh. The higher electricity generating costs are due mainly to the increased expenditure required for the protection of plants against airplane crashes, earthquakes and sabotage, and to the higher costs of the entire fuel cycle. (orig./RW) [de

  5. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    John Collins

    2009-01-01

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  6. Applications of nuclear-powered thermoelectric generators in space

    International Nuclear Information System (INIS)

    Rowe, D.M.

    1991-01-01

    The source of electrical power which enables information to be transmitted from the space crafts Voyager 1 and 2 back to Earth after a time period of more than a decade and at a distance of more than a billion miles is known as an RTG (radioisotope thermoelectric generator). It utilises the Seebeck effect in producing electricity from heat. In essence it consists of a large number of semiconductor thermocouples connected electrically in series and thermally in parallel. A temperature difference is maintained across the thermocouples by providing a heat source, which in the case of an RTG is a radioactive isotope, and the heat sink is space. The combination of an energy-conversion system, free of moving parts and a long-life, high energy-density heat source, provides a supply of electrical power typically in the range of tens to hundred of watts and which operates reliably over extended periods of time. An electric power source, based upon thermoelectric conversion by which utilises a nuclear reactor as a heat source, has also been deployed in space and a 100-kW system is being developed to provide electrical power to a variety of commercial and military projects including SDI. Developments in thermoelectrics that have taken place in the western world during the past 30 years are primarily due to United States interest and involvement in the exploration of space. This paper reviews US applications of nuclear-powered thermoelectric generators in space. (author)

  7. On fire risk/methodology for the next generation of reactors and nuclear facilities

    International Nuclear Information System (INIS)

    Majumdar, K.C.; Alesso, H.P.; Altenbach, T.J.

    1992-01-01

    Methodologies for including fire in probabilistic risk assessments (PRAs) have been evolving during the last ten years. Many of these studies show that fire risk constitutes a significant percentage of external events, as well as the total core damage frequency. This paper summarizes the methodologies used in the fire risk analysis of the next generation of reactors and existing DOE nuclear facilities. Methodologies used in other industries, as well as existing nuclear power plants, are also discussed. Results of fire risk studies for various nuclear plants and facilities are shown and compared

  8. Quantifying the costs of electricity generation in Alberta - modelling Alberta with nuclear power generation in place of coal and natural gas

    Energy Technology Data Exchange (ETDEWEB)

    Toor, J.; Donev, J.M.K.C., E-mail: jstoor@ucalgary.ca, E-mail: jmdonev@ucalgary.ca [Univ. of Calgary, Calgary, AB (Canada)

    2014-07-01

    The study determines the externality impacts on Alberta assuming the use nuclear power instead of coal and natural gas. For historical time (1976-2006) it was found that replacing coal generation with nuclear power could have displaced over a million kilotons (kt) of Carbon dioxide (CO{sub 2}) release to the atmosphere, prevented at least 7000 premature deaths and saved a mean value of over $33.1 Billion dollars (2007 USD) at the cost of storing 20.7 kt of spent nuclear fuel ($11.5 Billion). The same calculations were also made for a projection period (2006-2101) and also for the replacement of natural gas with nuclear power. (author)

  9. Quantifying the costs of electricity generation in Alberta - modelling Alberta with nuclear power generation in place of coal and natural gas

    International Nuclear Information System (INIS)

    Toor, J.; Donev, J.M.K.C.

    2014-01-01

    The study determines the externality impacts on Alberta assuming the use nuclear power instead of coal and natural gas. For historical time (1976-2006) it was found that replacing coal generation with nuclear power could have displaced over a million kilotons (kt) of Carbon dioxide (CO 2 ) release to the atmosphere, prevented at least 7000 premature deaths and saved a mean value of over $33.1 Billion dollars (2007 USD) at the cost of storing 20.7 kt of spent nuclear fuel ($11.5 Billion). The same calculations were also made for a projection period (2006-2101) and also for the replacement of natural gas with nuclear power. (author)

  10. Nuclear Power and Environment Comparative Assessment of Environmental and Health Impacts of Electricity Generating Systems

    International Nuclear Information System (INIS)

    Rashed, S.M.

    1999-01-01

    This paper deals with comparative assessment of the environmental and health impacts of nuclear and other electricity generation systems. The study including normal operations and accidents in full energy chain analysis. The comparison of the environmental impacts arising from the waste management cycles associated with non emission waste are also discussed. Nuclear Power while economically feasible and meeting 17% of the world,s demand for electricity is almost free of the air polluting gases that threaten the global climate. Comparing nuclear power with other sources for electricity generation in terms of their associated environmental releases of pollutant such as SO 2 , NOX, CO 2 , CH 4 and radioisotopes, taking into account the full fuel chains chains of supply option, nuclear power will help to reduce environmental degradation due to electricity generation activities. In view of CO 2 emission, the ranking order commences with hydro, followed by nuclear, wind and photovoltaic Power Plants. CO 2 emissions from a nuclear power plant are by two orders of magnitude lower than those of fossil fueled power plants. A consequent risk comparison between different energy sources has to include al phases of the whole energy cycle. Coal mines accidents have resulted in several 1000 acute deaths over the years. Later fatalities have never been estimated. Then came hydropower, also resulting in many catastrophes and losses of human lives. Followed oil and gas energy industry, its tribute in acute fatalities is expressed in more than 1000 life lost. No estimate is available concerning later fatalities. latest in the list is commercial nuclear energy, badly illustrated by the Chernobyl accident resulting officially in 31 acute fatalities, 145 latent fatalities, and 135000 evacuated individuals. The paper offers some findings and conclusions on the role of nuclear power in protecting the global environment

  11. High-speed particle tracking in nuclear emulsion by last-generation automatic microscopes

    International Nuclear Information System (INIS)

    Armenise, N.; De Serio, M.; Ieva, M.; Muciaccia, M.T.; Pastore, A.; Simone, S.; Damet, J.; Kreslo, I.; Savvinov, N.; Waelchli, T.; Consiglio, L.; Cozzi, M.; Di Ferdinando, D.; Esposito, L.S.; Giacomelli, G.; Giorgini, M.; Mandrioli, G.; Patrizii, L.; Sioli, M.; Sirri, G.; Arrabito, L.; Laktineh, I.; Royole-Degieux, P.; Buontempo, S.; D'Ambrosio, N.; De Lellis, G.; De Rosa, G.; Di Capua, F.; Coppola, D.; Formisano, F.; Marotta, A.; Migliozzi, P.; Pistillo, C.; Scotto Lavina, L.; Sorrentino, G.; Strolin, P.; Tioukov, V.; Juget, F.; Hauger, M.; Rosa, G.; Barbuto, E.; Bozza, C.; Grella, G.; Romano, G.; Sirignano, C.

    2005-01-01

    The technique of nuclear emulsions for high-energy physics experiments is being revived, thanks to the remarkable progress in measurement automation achieved in the past years. The present paper describes the features and performances of the European Scanning System, a last-generation automatic microscope working at a scanning speed of 20cm 2 /h. The system has been developed in the framework of the OPERA experiment, designed to unambigously detect ν μ ->ν τ oscillations in nuclear emulsions

  12. Technical characteristics of new generation of nuclear power plants; Charakterystyka techniczna elektrowni jadrowych nowej generacji

    Energy Technology Data Exchange (ETDEWEB)

    Janczak, R.; Mikulski, A.; Staron, E. [Instytut Energii Atomowej, Swierk-Otwock (Poland)

    1997-12-31

    The concept of Advanced Light Water Reactors (ALWR) as a new generation of nuclear reactors for energetics have been presented. The influence of reactor accidents (TMI and Chernobyl) on technical and scientific development of nuclear reactors has been discussed from the view point of safety assurance and requirements being defined by American and European Nuclear Regulatory commission. 12 refs, 14 figs.

  13. Inner conflict between nuclear power generation and electricity rates: A Japanese case study

    International Nuclear Information System (INIS)

    Ida, Takanori; Takemura, Kosuke; Sato, Masayuki

    2015-01-01

    Since the March 11 earthquake, Japanese households have been facing a trade-off problem between decreasing dependency on nuclear power generation and avoiding an increase in electricity rates. We analyze this inner conflict quantitatively, adopting two economic–psychological approaches: First, we note that the trade-off causes cognitive dissonance after making a choice that results in a wider desirability gap between the chosen and rejected alternatives. Second, the consumer surplus improves by 11.2% with a no-choice option for suspending judgment in the presence of cognitive dissonance. Third, individual characteristics such as gender and annual household income are significantly correlated with both cognitive dissonance and a preference for the no-choice option. - Highlights: • The Fukushima crisis shocked Japanese citizens' attitudes on nuclear power plants. • Citizens' attitudes toward nuclear power generation and electricity rates surveyed • The trade-off caused cognitive dissonance resulting in a hardline stance. • The consumer surplus improves with a no-choice option for suspending judgment

  14. The design and installation of a core discharge monitor for CANDU-type reactors

    International Nuclear Information System (INIS)

    Halbig, J.K.; Monticone, A.C.; Ksiezak, L.; Smiltnieks, V.

    1990-01-01

    A new type of surveillance systems that monitors neutron and gamma radiation in a reactor containment is being installed at the Ontario Hydro Darlington Nuclear Generating Station A, Unit 2. Unlike video or film surveillance that monitors mechanical motion, this system measures fuel-specific radiation emanating from irradiated fuel as it is pushed from the core of CANDU-type reactors. Proof-of-principle measurements have been carried out at Bruce Nuclear Generating Station A, Unit 3. The system uses (γ,n) threshold detectors and ionization detectors. A microprocessor-based electronics package, GRAND-II (Gamma Ray and Neutron Detector electronics package), provides detector bias, preamplifier power, and signal processing. Firmware in the GRAND-2 controls the surveillance activities, including data acquisition and a level of detector authentication, and it handles authenticated communication with a central data logging computer. Data from the GRAND-II are transferred to an MS-DOS-compatible computer and stored. These data are collected and reviewed for fuel-specific radiation signatures from the primary detector and proper ratios of signals from secondary detectors. 5 figs

  15. A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats

    International Nuclear Information System (INIS)

    Nelson, K.; Sokkappa, P.

    2008-01-01

    This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the

  16. Ethics Beyond Finitude: Responsibility towards Future Generations and Nuclear Waste Management

    Energy Technology Data Exchange (ETDEWEB)

    Loefquist, Lars

    2008-05-15

    This dissertation has three aims: 1. To evaluate several ethical theories about responsibility towards future generations. 2. To construct a theory about responsibility towards future generations. 3. To carry out an ethical evaluation of different nuclear waste management methods. Five theories are evaluated with the help of evaluative criteria, primarily: A theory must provide future generations with some independent moral status. A theory should acknowledge moral pluralism. A theory should provide some normative claims about real-world problems. Derek Parfit's theory provides future generations with full moral status. But it is incompatible with moral pluralism, and does not provide reasonable normative claims about real-world problems. Brian Barry's theory provides such claims and a useful idea about risk management, but it does not provide an argument why future generations ought to exist. Avner de-Shalit's theory explains why they ought to exist; however, his theory can not easily explain why we ought to care for other people than those in our own community. Emmanuel Agius' theory gives an ontological explanation for mankind's unity, but reduces conflicts of interests to a common good. Finally, Hans Jonas' theory shifts the focus from the situation of future generations to the preconditions of human life generally. However, his theory presupposes a specific ontology, which might be unable to motivate people to act. The concluding chapters describe a narrative theory of responsibility. It claims that we should comprehend ourselves as parts of the common story of mankind and that we ought to provide future generations with equal opportunities. This implies that we should avoid transferring risks and focus on reducing the long-term risks associated with the nuclear waste

  17. Measuring the linear heat generation rate of a nuclear reactor fuel pin

    International Nuclear Information System (INIS)

    Smith, R.D.

    1981-01-01

    A miniature gamma thermometer is described which is capable of travelling through bores distributed in an array through a nuclear reactor core and measure the linear heat generation rate of the fuel pins. (U.K.)

  18. Development and tests of large nuclear turbo-generator welded rotors

    International Nuclear Information System (INIS)

    Colombie, H.; Thiery, M.; Rotzinger, R.; Pelissou, C.; Tabacco, C.; Fernagut, V.

    2015-01-01

    Turbo-generators require large forgings for the rotor and it is a worldwide practice to manufacture turbo-generator rotor bodies as single piece forgings. Rotors for nuclear applications (4-pole rotors design, 1500/1800 rpm) require forgings of up to 2.0 m diameter and ultra large ingots with weight more than 500 tons. Nowadays only few forge masters can deliver such forgings in the world. Based on the large welding experience Alstom has gained over decades on steam and gas turbines and Alstom's multi piece shrunk turbo-generator rotors, it was suggested to manufacture 4-pole turbo-generator rotors by welding the shaft from aligned cylindrical forgings. Compared to turbine welded rotors, the shaft of a turbo-generator rotor presents differences linked to dimensions/weight, weld depth and electrical application. The manufacture of a 2 disc model allowed to prove through electrical and mechanical analysis the reliability of the concept as well as the reliability of the manufacturing processes through material tests, micro sections, electrical component tests, weld geometry, welding processes (TIG,SAW,...), weld inspection (Ultrasonic testing, radiographic inspection,...) weld heat treatments and machining. Then a full rotor able to replace a single forging rotor was manufactured in order to validate and prove to potential customers the validity of the welded rotor technology. During the first order from EDF of a welded 900 MW spare rotor, the procedure for the Non Destructive Test on a slotted rotor was developed upon EDF request in order to compare future Non Destructive Testing with the finger print of the new rotor. This complete rotor was delivered to EDF in January 2013. This rotor is in operation in a nuclear unit since November 2013. (authors)

  19. Korea's choice of a new generation of nuclear plants

    International Nuclear Information System (INIS)

    Redding, J.R.

    1994-01-01

    The ABWR and SBWR design, both under development at GE, provide the best platform for developing the next generation advanced plants. The ABWR, which is rapidly setting the standard for new nuclear reactor plants, is clearly the best choice to meet the present energy needs of Korea. And through a GE/Korea partnership to develop the plant of the next century, Korea will establish itself as a leader in innovative reactor technology

  20. Economic assessment of coal-fired and nuclear power generation in the year 2000 -Equal health hazard risk basis-

    International Nuclear Information System (INIS)

    Seong, Ki Bong; Lee, Byong Whi

    1989-01-01

    On the basis of equal health hazard risk, economic assessment of nuclear was compared with that of coal for the expansion planning of electric power generation in the year 2000. In comparing health risks, the risk of coal was roughly ten times higher than that of nuclear according to various previous risk assessments of energy system. The zero risk condition can never be achievable. Therefore, only excess relative health risk of coal over nuclear was considered as social cost. The social cost of health risk was estimated by calculation of mortality and morbidity costs. Mortality cost was $250,000 and morbidity cost was $90,000 in the year 2000.(1986US$) Through Cost/Benefit Analysis, the optimal emission standards of coal-fired power generation were predicted. These were obtained at the point of least social cost for power generation. In the year 2000, the optimal emission standard of SO x was analyzed as 165ppm for coal-fired power plants in Korea. From this assessment, economic comparison of nuclear and coal in the year 2000 showed that nuclear would be more economical than coal, whereas uncertainty of future power generation cost of nuclear would be larger than that of coal. (Author)